NUREG-1432 

Vol 1, Rev. 3.0 

Standard Technical Specifications 

Combustion Engineering Plants

Specifications

Manuscript Completed: March 2004 

Date Published: June 2004 

Division of Regulatory Improvement Programs 

Office of Nuclear Reactor Regulation 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001
CEOG STS ii Rev. 3.0, 03/31/04 

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CEOG STS iii Rev. 3.0, 03/31/04 

PREFACE 

This NUREG contains the improved Standard Technical Specifications (STS) for Combustion 

Engineering plants. Revision 3 incorporates the cumulative changes to Revision 1 and 2, which 

was published in April 1995 and April 2001, respectively. The changes reflected in Revision 3 

resulted from the experience gained from license amendment applications to convert to these 

improved STS or to adopt partial improvements to existing technical specifications. This 

publication is the result of extensive public technical meetings and discussions among the 

Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear 

Steam Supply System (NSSS) Owners Groups, and the Nuclear Energy Institute (NEI). The 

improved STS were developed based on the criteria in the Final Commission Policy Statement 

on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 

(58 FR 39132), which was subsequently codified by changes to Section 36 of Part 50 of Title 10 

of the Code of Federal Regulations (10 CFR 50.36) (60 FR 36953). Licensees are encouraged 

to upgrade their technical specifications consistent with those criteria and conforming, to the 

practical extent, to Revision 3 to the improved STS. The Commission continues to place the 

highest priority on requests for complete conversions to the improved STS. Licensees adopting 

portions of the improved STS to existing technical specifications should adopt all related 

requirements, as applicable, to achieve a high degree of standardization and consistency. 

The Table of Contents is now a Table of Contents / Revision Summary where the revision 

number and date are listed for each specification and bases, in lieu of traditional page numbers. 

Each limiting condition for operation (LCO) starts with page 1, with a specification, e.g., "2.0" or 

bases "B 2.0" number prefix. Subsequent approved revisions to sections will be noted in the 

Table of Contents, as well as on each affected page, using a decimal number to indicate the 

number of revisions to that section, along with the date, e.g., (Rev 3.3, 04/01/04) indicates the 

third approved change and date since Revision 3.0 was published. Additionally, the final page 

of each LCO section will be a historical listing of the changes affecting that section. This 

publication will be maintained in electronic format. Subsequent revisions will not be printed in 

hard copy. Users may access the subsequent revisions to the STS in the PDF format at 

(http://www.nrc.gov/NRR/sts/sts.htm). This Web site will be updated as needed and the 

contents may differ from the last printed version. Users may print or download copies from the 

NRC Web site. 

PAPERWORK REDUCTION ACT STATEMENT 

The information collections contained in this NUREG are covered by the requirements of 

10 CFR Parts 20 and 50, which were approved by the Office of Management and Budget, 

approval numbers 3150-0014 and 0011. 

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to, the information collection. 
CEOG STS v Rev. 3.0, 03/31/04 

TABLE OF CONTENTS / REVISION SUMMARY Revision - Date 

1.0 USE AND APPLICATION 

1.1 Definitions.................................................................................................3.0, 03/31/04 

1.2 Logical Connectors...................................................................................3.0, 03/31/04 

1.3 Completion Times ....................................................................................3.0, 03/31/04 

1.4 Frequency ................................................................................................3.0, 03/31/04 

2.0 SAFETY LIMITS (Analog) ..............................................................................3.0, 03/31/04 

2.1 SLs 

2.2 SL Violations 

2.0 SAFETY LIMITS (Digital) ...............................................................................3.0, 03/31/04 

2.1 SLs 

2.2 SL Violations 

3.0 LIMITING CONDITION FOR OPERATION APPLICABILITY.........................3.0, 03/31/04 

3.0 SURVEILLANCE REQUIREMENT APPLICABILITY .....................................3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.1 SHUTDOWN MARGIN (Analog) ........................................................3.0, 03/31/04 

3.1.2 Reactivity Balance (Analog) ...............................................................3.0, 03/31/04 

3.1.3 Moderator Temperature Coefficient (Analog).....................................3.0, 03/31/04 

3.1.4 Control Element Assembly Alignment (Analog)..................................3.0, 03/31/04 

3.1.5 Shutdown Control Element Assembly Insertion Limits (Analog) ........3.0, 03/31/04 

3.1.6 Regulating Control Element Assembly Insertion Limits (Analog) .......3.0, 03/31/04 

3.1.7 Special Test Exceptions - SHUTDOWN MARGIN (Analog)...............3.0, 03/31/04 

3.1.8 Special Test Exceptions - MODES 1 and 2 (Analog) .........................3.0, 03/31/04 

3.1.1 SHUTDOWN MARGIN (Digital)..........................................................3.0, 03/31/04 

3.1.2 Reactivity Balance (Digital) ................................................................3.0, 03/31/04 

3.1.3 Moderator Temperature Coefficient (Digital) ......................................3.0, 03/31/04 

3.1.4 Control Element Assembly Alignment (Digital)...................................3.0, 03/31/04 

3.1.5 Shutdown Control Element Assembly Insertion Limits (Digital)..........3.0, 03/31/04 

3.1.6 Regulating Control Element Assembly Insertion Limits (Digital) ........3.0, 03/31/04 

3.1.7 Part Length Control Element Assembly Insertion Limits (Digital).......3.0, 03/31/04 

3.1.8 Special Test Exceptions - SHUTDOWN MARGIN (Digital)................3.0, 03/31/04 

3.1.9 Special Test Exceptions - MODES 1 and 2 (Digital) ..........................3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.1 Linear Heat Rate (LHR) (Analog) .......................................................3.0, 03/31/04 

3.2.2 Total Planar Radial Peaking Factor ( T FXY ) (Analog)............................3.0, 03/31/04 

3.2.3 Total Integrated Radial Peaking Factor ( T Fr ) (Analog) .......................3.0, 03/31/04 

3.2.4 AZIMUTHAL POWER TILT (Tq) (Analog)...........................................3.0, 03/31/04 

3.2.5 AXIAL SHAPE INDEX (ASI) (Analog) ................................................3.0, 03/31/04 

3.2.1 Linear Heat Rate (LHR) (Digital) ........................................................3.0, 03/31/04 

3.2.2 Planar Radial Peaking Factors (Fxy) (Digital)......................................3.0, 03/31/04 

3.2.3 AZIMUTHAL POWER TILT (Tq) (Digital)............................................3.0, 03/31/04 
CEOG STS vi Rev. 3.0, 03/31/04 

TABLE OF CONTENTS / REVISION SUMMARY Revision - Date 

3.2.4 Departure From Nucleate Boiling Ratio (DNBR) (Digital)..................3.0, 03/31/04 

3.2.5 AXIAL SHAPE INDEX (ASI) (Digital)..................................................3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.1 Reactor Protective System Instrumentation - Operating (Analog)......3.0, 03/31/04 

3.3.2 Reactor Protective System Instrumentation - Shutdown (Analog) .....3.0, 03/31/04 

3.3.3 Reactor Protective System Logic and Trip Initiation (Analog) ............3.0, 03/31/04 

3.3.4 Engineered Safety Features Actuation System Instrumentation 

 (Analog)........................................................................................3.0, 03/31/04 

3.3.5 Engineered Safety Features Actuation System Logic and Manual 

 Trip (Analog).................................................................................3.0, 03/31/04 

3.3.6 Diesel Generator (DG) - Loss of Voltage Start (LOVS) (Analog) .......3.0, 03/31/04 

3.3.7 Containment Purge Isolation Signal (CPIS) (Analog).........................3.0, 03/31/04 

3.3.8 Control Room Isolation Signal (CRIS) (Analog) .................................3.0, 03/31/04 

3.3.9 Chemical and Volume Control System (CVCS) Isolation Signal 

 (Analog)........................................................................................3.0, 03/31/04 

3.3.10 Shield Building Filtration Actuation Signal (SBFAS) (Analog) ............3.0, 03/31/04 

3.3.11 Post Accident Monitoring (PAM) Instrumentation (Analog) ................3.0, 03/31/04 

3.3.12 Remote Shutdown System (Analog) ..................................................3.0, 03/31/04 

3.3.13 [Logarithmic] Power Monitoring Channels (Analog) ...........................3.0, 03/31/04 

3.3.1 Reactor Protective System Instrumentation - Operating (Digital).......3.0, 03/31/04 

3.3.2 Reactor Protective System Instrumentation - Shutdown (Digital).......3.0, 03/31/04 

3.3.3 Control Element Assembly Calculators (CEACs) (Digital)..................3.0, 03/31/04 

3.3.4 Reactor Protective System Logic and Trip Initiation (Digital) .............3.0, 03/31/04 

3.3.5 Engineered Safety Features Actuation System Instrumentation 

 (Digital) .........................................................................................3.0, 03/31/04 

3.3.6 Engineered Safety Features Actuation System Logic and Manual 

 Trip (Digital)..................................................................................3.0, 03/31/04 

3.3.7 Diesel Generator (DG) - Loss of Voltage Start (LOVS) (Digital).........3.0, 03/31/04 

3.3.8 Containment Purge Isolation Signal (CPIS) (Digital)..........................3.0, 03/31/04 

3.3.9 Control Room Isolation Signal (CRIS) (Digital)...................................3.0, 03/31/04 

3.3.10 Fuel Handling Isolation Signal (FHIS) (Digital)...................................3.0, 03/31/04 

3.3.11 Post Accident Monitoring (PAM) Instrumentation (Digital) .................3.0, 03/31/04 

3.3.12 Remote Shutdown System (Digital)....................................................3.0, 03/31/04 

3.3.13 [Logarithmic] Power Monitoring Channels (Digital) ............................3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.1 RCS Pressure, Temperature, and Flow [Departure from Nucleate 

 Boiling (DNB)] Limits ....................................................................3.0, 03/31/04 

3.4.2 RCS Minimum Temperature for Criticality..........................................3.0, 03/31/04 

3.4.3 RCS Pressure and Temperature (P/T) Limits.....................................3.0, 03/31/04 

3.4.4 RCS Loops - MODES 1 and 2............................................................3.0, 03/31/04 

3.4.5 RCS Loops - MODE 3 ........................................................................3.0, 03/31/04 

3.4.6 RCS Loops - MODE 4 ........................................................................3.0, 03/31/04 

3.4.7 RCS Loops - MODE 5, Loops Filled...................................................3.0, 03/31/04 
CEOG STS vii Rev. 3.0, 03/31/04 

TABLE OF CONTENTS / REVISION SUMMARY Revision - Date 

3.4 REACTOR COOLANT SYSTEM (RCS) (continued) 

3.4.8 RCS Loops - MODE 5, Loops Not Filled ............................................3.0, 03/31/04 

3.4.9 Pressurizer .........................................................................................3.0, 03/31/04 

3.4.10 Pressurizer Safety Valves ..................................................................3.0, 03/31/04 

3.4.11 Pressurizer Power Operated Relief Valves (PORVs).........................3.0, 03/31/04 

3.4.12 Low Temperature Overpressure Protection (LTOP) System..............3.0, 03/31/04 

3.4.13 RCS Operational LEAKAGE...............................................................3.0, 03/31/04 

3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ....................................3.0, 03/31/04 

3.4.15 RCS Leakage Detection Instrumentation ...........................................3.0, 03/31/04 

3.4.16 RCS Specific Activity..........................................................................3.0, 03/31/04 

3.4.17 Special Test Exceptions (STE) RCS Loops .......................................3.0, 03/31/04 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.1 Safety Injection Tanks (SITs) .............................................................3.0, 03/31/04 

3.5.2 ECCS - Operating ..............................................................................3.0, 03/31/04 

3.5.3 ECCS - Shutdown ..............................................................................3.0, 03/31/04 

3.5.4 Refueling Water Tank (RWT) .............................................................3.0, 03/31/04 

3.5.5 Trisodium Phosphate (TSP) ...............................................................3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.1 Containment (Atmospheric and Dual) ................................................3.0, 03/31/04 

3.6.2 Containment Air Locks (Atmospheric and Dual).................................3.0, 03/31/04 

3.6.3 Containment Isolation Valves (Atmospheric and Dual) ......................3.0, 03/31/04 

3.6.4 Containment Pressure (Atmospheric and Dual).................................3.0, 03/31/04 

3.6.5 Containment Air Temperature (Atmospheric and Dual) .....................3.0, 03/31/04 

3.6.6A Containment Spray and Cooling System (Atmospheric and Dual) 

 (Credit taken for iodine removal by the Containment Spray 

 System) ........................................................................................3.0, 03/31/04 

3.6.6B Containment Spray and Cooling Systems (Atmospheric and Dual) 

 (Credit not taken for iodine removal by the Containment Spray 

 System) ........................................................................................3.0, 03/31/04 

3.6.7 Spray Additive System (Atmospheric and Dual).................................3.0, 03/31/04 

3.6.8 Shield Building Exhaust Air Cleanup System (SBEACS) (Dual) ........3.0, 03/31/04 

3.6.9 Hydrogen Mixing System (HMS) (Atmospheric and Dual) .................3.0, 03/31/04 

3.6.10 Iodine Cleanup System (ICS) (Atmospheric and Dual) ......................3.0, 03/31/04 

3.6.11 Shield Building (Dual).........................................................................3.0, 03/31/04 

3.6.12 Vacuum Relief Valves (Dual) .............................................................3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.1 Main Steam Safety Valves (MSSVs)..................................................3.0, 03/31/04 

3.7.2 Main Steam Isolation Valves (MSIVs) ................................................3.0, 03/31/04 

3.7.3 Main Feedwater Isolation Valves (MFIVs) [and [MFIV] Bypass 

 Valves...........................................................................................3.0, 03/31/04 

3.7.4 Atmospheric Dump Valves (ADVs).....................................................3.0, 03/31/04 

3.7.5 Auxiliary Feedwater (AFW) System....................................................3.0, 03/31/04 
CEOG STS viii Rev. 3.0, 03/31/04 

TABLE OF CONTENTS / REVISION SUMMARY Revision - Date 

3.7 PLANT SYSTEMS (continued) 

3.7.6 Condensate Storage Tank (CST).......................................................3.0, 03/31/04 

3.7.7 Component Cooling Water (CCW) System ........................................3.0, 03/31/04 

3.7.8 Service Water System (SWS) ............................................................3.0, 03/31/04 

3.7.9 Ultimate Heat Sink (UHS)...................................................................3.0, 03/31/04 

3.7.10 Essential Chilled Water (ECW)...........................................................3.0, 03/31/04 

3.7.11 Control Room Emergency Air Cleanup System (CREACS)...............3.0, 03/31/04 

3.7.12 Control Room Emergency Air Temperature Control System 

 (CREATCS) ..................................................................................3.0, 03/31/04 

3.7.13 Emergency Core Cooling System (ECCS) Pump Room Exhaust 

 Air Cleanup System (PREACS)....................................................3.0, 03/31/04 

3.7.14 Fuel Building Air Cleanup System (FBACS).......................................3.0, 03/31/04 

3.7.15 Penetration Room Exhaust Air Cleanup System (PREACS)..............3.0, 03/31/04 

3.7.16 Fuel Storage Pool Water Level ..........................................................3.0, 03/31/04 

[ 3.7.17 Fuel Storage Pool Boron Concentration............................................3.0, 03/31/04] 

[ 3.7.18 Spent Fuel Assembly Storage...........................................................3.0, 03/31/04] 

3.7.19 Secondary Specific Activity ................................................................3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.1 AC Sources - Operating .....................................................................3.0, 03/31/04 

3.8.2 AC Sources - Shutdown .....................................................................3.0, 03/31/04 

3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air..........................................3.0, 03/31/04 

3.8.4 DC Sources - Operating .....................................................................3.0, 03/31/04 

3.8.5 DC Sources - Shutdown.....................................................................3.0, 03/31/04 

3.8.6 Battery Parameters ............................................................................3.0, 03/31/04 

3.8.7 Inverters - Operating ..........................................................................3.0, 03/31/04 

3.8.8 Inverters - Shutdown ..........................................................................3.0, 03/31/04 

3.8.9 Distribution Systems - Operating........................................................3.0, 03/31/04 

3.8.10 Distribution Systems - Shutdown........................................................3.0, 03/31/04 

3.9 REFUELING OPERATIONS 

3.9.1 Boron Concentration ..........................................................................3.0, 03/31/04 

3.9.2 Nuclear Instrumentation .....................................................................3.0, 03/31/04 

3.9.3 Containment Penetrations..................................................................3.0, 03/31/04 

3.9.4 Shutdown Cooling (SDC) and Coolant Circulation - High Water 

 Level.............................................................................................3.0, 03/31/04 

3.9.5 Shutdown Cooling (SDC) and Coolant Circulation - Low Water 

 Level.............................................................................................3.0, 03/31/04 

3.9.6 Refueling Water Level ........................................................................3.0, 03/31/04 

4.0 DESIGN FEATURES .....................................................................................3.0, 03/31/04 

4.1 Site Location 

4.2 Reactor Core 

4.3 Fuel Storage 
CEOG STS ix Rev. 3.0, 03/31/04 

TABLE OF CONTENTS / REVISION SUMMARY Revision - Date 

5.0 ADMINISTRATIVE CONTROLS 

5.1 Responsibility ...........................................................................................3.0, 03/31/04 

5.2 Organization.............................................................................................3.0, 03/31/04 

5.3 Unit Staff Qualifications............................................................................3.0, 03/31/04 

5.4 Procedures...............................................................................................3.0, 03/31/04 

5.5 Programs and Manuals ............................................................................3.0, 03/31/04 

5.6 Reporting Requirements ..........................................................................3.0, 03/31/04 

[ 5.7 High Radiation Area ................................................................................3.0, 03/31/04] 
Definitions 

1.1 

CEOG STS 1.1-1 Rev. 3.0, 03/31/04 

1.0 USE AND APPLICATION 

1.1 Definitions 

------------------------------------------------------------NOTE----------------------------------------------------------- 

The defined terms of this section appear in capitalized type and are applicable throughout these 

Technical Specifications and Bases. 

-------------------------------------------------------------------------------------------------------------------------------

Term Definition

ACTIONS ACTIONS shall be that part of a Specification that prescribes 

Required Actions to be taken under designated Conditions 

within specified Completion Times. 

AXIAL SHAPE INDEX (ASI) ASI shall be the power generated in the lower half of the core 

less the power generated in the upper half of the core, divided 

by the sum of the power generated in the lower and upper 

halves of the core. 

 ASI = (LOWER - UPPER) / (LOWER + UPPER) 

AZIMUTHAL POWER TILT (Tq) AZIMUTHAL POWER TILT shall be the power asymmetry 

- Digital between azimuthally symmetric fuel assemblies. 

AZIMUTHAL POWER TILT (Tq) AZIMUTHAL POWER TILT shall be the maximum of the 

- Analog difference between the power generated in any core quadrant 

(upper or lower) (Pquad) and the average power of all quadrants 

(Pavg) in that half (upper or lower) of the core, divided by the 

average power of all quadrants in that half (upper or lower) of 

the core. 

 Tq = Max | (Pquad - Pavg) / Pavg | 

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as 

necessary, of the channel output such that it responds within 

the necessary range and accuracy to known values of the 

parameter that the channel monitors. The CHANNEL 

CALIBRATION shall encompass all devices in the channel 

required for channel OPERABILITY and the CHANNEL 

FUNCTIONAL TEST. Calibration of instrument channels with 

resistance temperature detector (RTD) or thermocouple 

sensors may consist of an inplace qualitative assessment of 

sensor behavior and normal calibration of the remaining 

adjustable devices in the channel. The CHANNEL 

CALIBRATION may be performed by means of any series of 

sequential, overlapping, or total channel steps. 
Definitions 

1.1 

CEOG STS 1.1-2 Rev. 3.0, 03/31/04 

1.1 Definitions 

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by 

observation, of channel behavior during operation. This 

determination shall include, where possible, comparison of the 

channel indication and status to other indications or status 

derived from independent instrument channels measuring the 

same parameter. 

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be: 

 a. Analog and bistable channels - the injection of a 

simulated or actual signal into the channel as close to 

the sensor as practicable to verify OPERABILITY of all 

devices in the channel required for channel 

OPERABILITY, and 

 b. Digital computer channels - the use of diagnostic 

programs to test digital computer hardware and the 

injection of simulated process data into the channel to 

verify OPERABILITY of all devices in the channel 

required for channel OPERABILITY. 

 The CHANNEL FUNCTIONAL TEST may be performed by 

means of any series of sequential, overlapping, or total 

channel steps so that the entire channel is tested. 

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, 

sources, or reactivity control components [excluding control 

element assemblies (CEAs) withdrawn into the upper guide 

structure], within the reactor vessel with the vessel head 

removed and fuel in the vessel. Suspension of CORE 

ALTERATIONS shall not preclude completion of movement of 

a component to a safe position. 

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle 

REPORT (COLR) specific parameter limits for the current reload cycle. These 

cycle specific parameter limits shall be determined for each 

reload cycle in accordance with Specification 5.6.5. Plant 

operation within these limits is addressed in individual 

Specifications. 

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 

(microcuries/gram) that alone would produce the same thyroid 

dose as the quantity and isotopic mixture of I-131, I-132, I-133, 

I-134, and I-135 actually present. The thyroid dose conversion 

factors used for this calculation shall be those listed in 
Definitions 

1.1 

CEOG STS 1.1-3 Rev. 3.0, 03/31/04 

1.1 Definitions 

DOSE EQUIVALENT I-131 (continued) 

 [Table III of TID-14844, AEC, 1962, "Calculation of Distance 

Factors for Power and Test Reactor Sites," or those listed in 

Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977, or 

ICRP 30, Supplement to Part 1, page 192-212, Table titled, 

"Committed Dose Equivalent in Target Organs or Tissues per 

Intake of Unit Activity"]. 

Ē - AVERAGE Ē shall be the average (weighted in proportion to the 

DISINTEGRATION ENERGY concentration of each radionuclide in the reactor coolant at the 

time of sampling) of the sum of the average beta and gamma 

energies per disintegration (in MeV) for isotopes, other than 

iodines, with half lives > [15] minutes, making up at least 95% 

of the total noniodine activity in the coolant. 

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from 

FEATURE (ESF) RESPONSE when the monitored parameter exceeds its ESF actuation 

TIME setpoint at the channel sensor until the ESF equipment is 

capable of performing its safety function (i.e., the valves travel 

to their required positions, pump discharge pressures reach 

their required values, etc.). Times shall include diesel 

generator starting and sequence loading delays, where 

applicable. The response time may be measured by means of 

any series of sequential, overlapping, or total steps so that the 

entire response time is measured. In lieu of measurement, 

response time may be verified for selected components 

provided that the components and methodology for verification 

have been previously reviewed and approved by the NRC. 

LEAKAGE LEAKAGE shall be: 

 a. Identified LEAKAGE

 1. LEAKAGE, such as that from pump seals or valve 

packing (except reactor coolant pump (RCP) seal 

water injection or leakoff), that is captured and 

conducted to collection systems or a sump or 

collecting tank, 

 2. LEAKAGE into the containment atmosphere from 

sources that are both specifically located and 

known either not to interfere with the operation of 

leakage detection systems or not to be pressure 

boundary LEAKAGE, or 
Definitions 

1.1 

CEOG STS 1.1-4 Rev. 3.0, 03/31/04 

1.1 Definitions 

LEAKAGE (continued) 

 3. Reactor Coolant System (RCS) LEAKAGE through 

a steam generator (SG) to the Secondary System, 

 b. Unidentified LEAKAGE

 All LEAKAGE (except RCP seal water injection or 

leakoff) that is not identified LEAKAGE, and 

 c. Pressure Boundary LEAKAGE

 LEAKAGE (except SG LEAKAGE) through a nonisolable 

fault in an RCS component body, pipe wall, or vessel 

wall. 

MODE A MODE shall correspond to any one inclusive combination of 

core reactivity condition, power level, average reactor coolant 

temperature, and reactor vessel head closure bolt tensioning 

specified in Table 1.1-1 with fuel in the reactor vessel. 

OPERABLE – OPERABILITY A system, subsystem, train, component, or device shall be 

OPERABLE or have OPERABILITY when it is capable of 

performing its specified safety function(s) and when all 

necessary attendant instrumentation, controls, normal or 

emergency electrical power, cooling and seal water, 

lubrication, and other auxiliary equipment that are required for 

the system, subsystem, train, component, or device to perform 

its specified safety function(s) are also capable of performing 

their related support function(s). 

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure 

the fundamental nuclear characteristics of the reactor core and 

related instrumentation. 

 These tests are: 

 a. Described in Chapter [14, Initial Test Program] of the 

FSAR, 

 b. Authorized under the provisions of 10 CFR 50.59, or 

 c. Otherwise approved by the Nuclear Regulatory 

Commission. 
Definitions 

1.1 

CEOG STS 1.1-5 Rev. 3.0, 03/31/04 

1.1 Definitions 

PRESSURE AND The PTLR is the unit specific document that provides the 

TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including 

REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel 

fluence period. These pressure and temperature limits shall 

be determined for each fluence period in accordance with 

Specification 5.6.6. 

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the 

(RTP) reactor coolant of [3410] MWt. 

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from 

SYSTEM (RPS) RESPONSE when the monitored parameter exceeds its RPS trip setpoint at 

TIME the channel sensor until electrical power to the CEAs drive 

mechanism is interrupted. The response time may be 

measured by means of any series of sequential, overlapping, 

or total steps so that the entire response time is measured. In 

lieu of measurement, response time may be verified for 

selected components provided that the components and 

methodology for verification have been previously reviewed 

and approved by the NRC. 

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which 

the reactor is subcritical or would be subcritical from its 

present condition assuming: 

 a. All full length CEAs (shutdown and regulating) are fully 

inserted except for the single CEA of highest reactivity 

worth, which is assumed to be fully withdrawn. However, 

with all CEAs verified fully inserted by two independent 

means, it is not necessary to account for a stuck CEA in 

the SDM calculation. With any CEAs not capable of 

being fully inserted, the reactivity worth of these CEAs 

must be accounted for in the determination of SDM, and 

 [ b. There is no change in part length CEA position. ] 

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of 

one of the systems, subsystems, channels, or other 

designated components during the interval specified by the 

Surveillance Frequency, so that all systems, subsystems, 

channels, or other designated components are tested during 

n Surveillance Frequency intervals, where n is the total 

number of systems, subsystems, channels, or other 

designated components in the associated function. 
Definitions 

1.1 

CEOG STS 1.1-6 Rev. 3.0, 03/31/04 

1.1 Definitions 

THERMAL POWER THERMAL POWER shall be the total reactor core heat 

transfer rate to the reactor coolant. 
Definitions 

1.1 

CEOG STS 1.1-7 Rev. 3.0, 03/31/04 

Table 1.1-1 (page 1 of 1) 

MODES 

MODE TITLE 

REACTIVITY 

CONDITION 

(keff) 

% RATED 

THERMAL 

POWER(a)

AVERAGE 

REACTOR COOLANT 

TEMPERATURE 

(°F) 

1 Power Operation ≥ 0.99 > 5 NA 

2 Startup ≥ 0.99 ≤ 5 NA 

3 Hot Standby < 0.99 NA ≥ [350] 

4 Hot Shutdown(b) < 0.99 NA [350] > Tavg > [200] 

5 Cold Shutdown(b) < 0.99 NA ≤ [200] 

6 Refueling(c) NA NA NA 

(a) Excluding decay heat. 

(b) All reactor vessel head closure bolts fully tensioned. 

(c) One or more reactor vessel head closure bolts less than fully tensioned. 
Logical Connectors 

1.2 

CEOG STS 1.2-1 Rev. 3.0, 03/31/04 

1.0 USE AND APPLICATION 

1.2 Logical Connectors 

PURPOSE The purpose of this section is to explain the meaning of logical 

connectors. 

 Logical connectors are used in Technical Specifications (TS) to 

discriminate between, and yet connect, discrete Conditions, Required 

Actions, Completion Times, Surveillances, and Frequencies. The only 

logical connectors that appear in TS are AND and OR. The physical 

arrangement of these connectors constitutes logical conventions with 

specific meanings. 

BACKGROUND Several levels of logic may be used to state Required Actions. These 

levels are identified by the placement (or nesting) of the logical 

connectors and by the number assigned to each Required Action. The 

first level of logic is identified by the first digit of the number assigned to a 

Required Action and the placement of the logical connector in the first 

level of nesting (i.e., left justified with the number of the Required Action). 

The successive levels of logic are identified by additional digits of the 

Required Action number and by successive indentions of the logical 

connectors. 

 When logical connectors are used to state a Condition, Completion Time, 

Surveillance, or Frequency, only the first level of logic is used, and the 

logical connector is left justified with the statement of the Condition, 

Completion Time, Surveillance, or Frequency. 

EXAMPLES The following examples illustrate the use of logical connectors. 
Logical Connectors 

1.2 

CEOG STS 1.2-2 Rev. 3.0, 03/31/04 

1.2 Logical Connectors 

EXAMPLES (continued) 

 EXAMPLE 1.2-1

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. LCO not met. A.1 Verify . . . 

AND

A.2 Restore . . . 

 In this example the logical connector AND is used to indicate that when in 

Condition A, both Required Actions A.1 and A.2 must be completed. 
Logical Connectors 

1.2 

CEOG STS 1.2-3 Rev. 3.0, 03/31/04 

1.2 Logical Connectors 

EXAMPLES (continued) 

 EXAMPLE 1.2-2

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. LCO not met. A.1 Trip . . . 

OR

A.2.1 Verify . . . 

 AND

A.2.2.1 Reduce . . . 

 OR

A.2.2.2 Perform . . . 

OR

A.3 Align . . . 

 This example represents a more complicated use of logical connectors. 

Required Actions A.1, A.2, and A.3 are alternative choices, only one of 

which must be performed as indicated by the use of the logical connector 

OR and the left justified placement. Any one of these three Actions may 

be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be 

performed as indicated by the logical connector AND. Required 

Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented 

position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are 

alternative choices, only one of which must be performed. 
Completion Times 

1.3 

CEOG STS 1.3-1 Rev. 3.0, 03/31/04 

1.0 USE AND APPLICATION 

1.3 Completion Times 

PURPOSE The purpose of this section is to establish the Completion Time 

convention and to provide guidance for its use. 

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements 

for ensuring safe operation of the unit. The ACTIONS associated with an 

LCO state Conditions that typically describe the ways in which the 

requirements of the LCO can fail to be met. Specified with each stated 

Condition are Required Action(s) and Completion Time(s). 

DESCRIPTION The Completion Time is the amount of time allowed for completing a 

Required Action. It is referenced to the time of discovery of a situation 

(e.g., inoperable equipment or variable not within limits) that requires 

entering an ACTIONS Condition unless otherwise specified, providing the 

unit is in a MODE or specified condition stated in the Applicability of the 

LCO. Required Actions must be completed prior to the expiration of the 

specified Completion Time. An ACTIONS Condition remains in effect and 

the Required Actions apply until the Condition no longer exists or the unit 

is not within the LCO Applicability. 

 If situations are discovered that require entry into more than one 

Condition at a time within a single LCO (multiple Conditions), the 

Required Actions for each Condition must be performed within the 

associated Completion Time. When in multiple Conditions, separate 

Completion Times are tracked for each Condition starting from the time of 

discovery of the situation that required entry into the Condition. 

 Once a Condition has been entered, subsequent trains, subsystems, 

components, or variables expressed in the Condition, discovered to be 

inoperable or not within limits, will not result in separate entry into the 

Condition, unless specifically stated. The Required Actions of the 

Condition continue to apply to each additional failure, with Completion 

Times based on initial entry into the Condition. 

 However, when a subsequent train, subsystem, component, or variable 

expressed in the Condition is discovered to be inoperable or not within 

limits, the Completion Time(s) may be extended. To apply this 

Completion Time extension, two criteria must first be met. The 

subsequent inoperability: 

 a. Must exist concurrent with the first inoperability and 

 b. Must remain inoperable or not within limits after the first inoperability 

is resolved. 
Completion Times 

1.3 

CEOG STS 1.3-2 Rev. 3.0, 03/31/04 

1.3 Completion Times 

DESCRIPTION (continued) 

 The total Completion Time allowed for completing a Required Action to 

address the subsequent inoperability shall be limited to the more 

restrictive of either: 

 a. The stated Completion Time, as measured from the initial entry into 

the Condition, plus an additional 24 hours or 

 b. The stated Completion Time as measured from discovery of the 

subsequent inoperability. 

 The above Completion Time extensions do not apply to those 

Specifications that have exceptions that allow completely separate reentry into the Condition (for each train, subsystem, component, or 

variable expressed in the Condition) and separate tracking of Completion 

Times based on this re-entry. These exceptions are stated in individual 

Specifications. 

 The above Completion Time extension does not apply to a Completion 

Time with a modified "time zero." This modified "time zero" may be 

expressed as a repetitive time (i.e., "once per 8 hours," where the 

Completion Time is referenced from a previous completion of the 

Required Action versus the time of Condition entry) or as a time modified 

by the phrase "from discovery . . ." Example 1.3-3 illustrates one use of 

this type of Completion Time. The 10 day Completion Time specified for 

Conditions A and B in Example 1.3-3 may not be extended. 

EXAMPLES The following examples illustrate the use of Completion Times with 

different types of Conditions and changing Conditions. 
Completion Times 

1.3 

CEOG STS 1.3-3 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 EXAMPLE 1.3-1

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. Required 

Action and 

associated 

Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

 Condition B has two Required Actions. Each Required Action has its own 

separate Completion Time. Each Completion Time is referenced to the 

time that Condition B is entered. 

 The Required Actions of Condition B are to be in MODE 3 within 6 hours 

AND in MODE 5 within 36 hours. A total of 6 hours is allowed for 

reaching MODE 3 and a total of 36 hours (not 42 hours) is allowed for 

reaching MODE 5 from the time that Condition B was entered. If MODE 3 

is reached within 3 hours, the time allowed for reaching MODE 5 is the 

next 33 hours because the total time allowed for reaching MODE 5 is 

36 hours. 

 If Condition B is entered while in MODE 3, the time allowed for reaching 

MODE 5 is the next 36 hours. 
Completion Times 

1.3 

CEOG STS 1.3-4 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 EXAMPLE 1.3-2

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One pump 

inoperable. 

A.1 Restore pump to 

OPERABLE status. 

7 days 

B. Required 

Action and 

associated 

Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

 When a pump is declared inoperable, Condition A is entered. If the pump 

is not restored to OPERABLE status within 7 days, Condition B is also 

entered and the Completion Time clocks for Required Actions B.1 

and B.2 start. If the inoperable pump is restored to OPERABLE status 

after Condition B is entered, Conditions A and B are exited, and therefore, 

the Required Actions of Condition B may be terminated. 

 When a second pump is declared inoperable while the first pump is still 

inoperable, Condition A is not re-entered for the second pump. 

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for 

more than one inoperable pump. The Completion Time clock for 

Condition A does not stop after LCO 3.0.3 is entered, but continues to be 

tracked from the time Condition A was initially entered. 

 While in LCO 3.0.3, if one of the inoperable pumps is restored to 

OPERABLE status and the Completion Time for Condition A has not 

expired, LCO 3.0.3 may be exited and operation continued in accordance 

with Condition A. 

 While in LCO 3.0.3, if one of the inoperable pumps is restored to 

OPERABLE status and the Completion Time for Condition A has expired, 

LCO 3.0.3 may be exited and operation continued in accordance with 

Condition B. The Completion Time for Condition B is tracked from the 

time the Condition A Completion Time expired. 
Completion Times 

1.3 

CEOG STS 1.3-5 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 On restoring one of the pumps to OPERABLE status, the Condition A 

Completion Time is not reset, but continues from the time the first pump 

was declared inoperable. This Completion Time may be extended if the 

pump restored to OPERABLE status was the first inoperable pump. A 

24 hour extension to the stated 7 days is allowed, provided this does not 

result in the second pump being inoperable for > 7 days. 

 EXAMPLE 1.3-3

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One 

Function X 

train 

inoperable. 

A.1 Restore Function X 

train to OPERABLE 

status. 

7 days 

AND

10 days from discovery 

of failure to meet the 

LCO 

B. One 

Function Y 

train 

inoperable. 

B.1 Restore Function Y 

train to OPERABLE 

status. 

72 hours 

AND

10 days from discovery 

of failure to meet the 

LCO 

C. One 

Function X 

train 

inoperable. 

 AND

 One 

Function Y 

train 

inoperable. 

C.1 Restore Function X 

train to OPERABLE 

status. 

OR

C.2 Restore Function Y 

train to OPERABLE 

status. 

72 hours 

72 hours 
Completion Times 

1.3 

CEOG STS 1.3-6 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 When one Function X train and one Function Y train are inoperable, 

Condition A and Condition B are concurrently applicable. The Completion 

Times for Condition A and Condition B are tracked separately for each 

train starting from the time each train was declared inoperable and the 

Condition was entered. A separate Completion Time is established for 

Condition C and tracked from the time the second train was declared 

inoperable (i.e., the time the situation described in Condition C was 

discovered). 

 If Required Action C.2 is completed within the specified Completion Time, 

Conditions B and C are exited. If the Completion Time for Required 

Action A.1 has not expired, operation may continue in accordance with 

Condition A. The remaining Completion Time in Condition A is measured 

from the time the affected train was declared inoperable (i.e., initial entry 

into Condition A). 

 The Completion Times of Conditions A and B are modified by a logical 

connector, with a separate 10 day Completion Time measured from the 

time it was discovered the LCO was not met. In this example, without the 

separate Completion Time, it would be possible to alternate between 

Conditions A, B, and C in such a manner that operation could continue 

indefinitely without ever restoring systems to meet the LCO. The 

separate Completion Time modified by the phrase "from discovery of 

failure to meet the LCO" is designed to prevent indefinite continued 

operation while not meeting the LCO. This Completion Time allows for an 

exception to the normal "time zero" for beginning the Completion Time 

"clock." In this instance, the Completion Time "time zero" is specified as 

commencing at the time the LCO was initially not met, instead of at the 

time the associated Condition was entered. 
Completion Times 

1.3 

CEOG STS 1.3-7 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 EXAMPLE 1.3-4

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more 

valves 

inoperable. 

A.1 Restore valve(s) to 

OPERABLE status. 

4 hours 

B. Required 

Action and 

associated 

Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4. 

6 hours 

12 hours 

 A single Completion Time is used for any number of valves inoperable at 

the same time. The Completion Time associated with Condition A is 

based on the initial entry into Condition A and is not tracked on a per 

valve basis. Declaring subsequent valves inoperable, while Condition A 

is still in effect, does not trigger the tracking of separate Completion 

Times. 

 Once one of the valves has been restored to OPERABLE status, the 

Condition A Completion Time is not reset, but continues from the time the 

first valve was declared inoperable. The Completion Time may be 

extended if the valve restored to OPERABLE status was the first 

inoperable valve. The Condition A Completion Time may be extended for 

up to 4 hours provided this does not result in any subsequent valve being 

inoperable for > 4 hours. 

 If the Completion Time of 4 hours (including the extension) expires while 

one or more valves are still inoperable, Condition B is entered. 
Completion Times 

1.3 

CEOG STS 1.3-8 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 EXAMPLE 1.3-5

 ACTIONS 

 ---------------------------------------------NOTE-------------------------------------------- 

 Separate Condition entry is allowed for each inoperable valve. 

 -------------------------------------------------------------------------------------------------- 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more 

valves 

inoperable. 

A.1 Restore valve to 

OPERABLE status. 

4 hours 

B. Required 

Action and 

associated 

Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4. 

6 hours 

12 hours 

 The Note above the ACTIONS Table is a method of modifying how the 

Completion Time is tracked. If this method of modifying how the 

Completion Time is tracked was applicable only to a specific Condition, 

the Note would appear in that Condition rather than at the top of the 

ACTIONS Table. 

 The Note allows Condition A to be entered separately for each inoperable 

valve, and Completion Times tracked on a per valve basis. When a valve 

is declared inoperable, Condition A is entered and its Completion Time 

starts. If subsequent valves are declared inoperable, Condition A is 

entered for each valve and separate Completion Times start and are 

tracked for each valve. 

 If the Completion Time associated with a valve in Condition A expires, 

Condition B is entered for that valve. If the Completion Times associated 

with subsequent valves in Condition A expire, Condition B is entered 

separately for each valve and separate Completion Times start and are 

tracked for each valve. If a valve that caused entry into Condition B is 

restored to OPERABLE status, Condition B is exited for that valve. 
Completion Times 

1.3 

CEOG STS 1.3-9 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 Since the Note in this example allows multiple Condition entry and 

tracking of separate Completion Times, Completion Time extensions do 

not apply. 

 EXAMPLE 1.3-6

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One channel 

inoperable. 

A.1 Perform SR 3.x.x.x. 

OR

A.2 Reduce THERMAL 

POWER to 

≤ 50% RTP. 

Once per 8 hours 

8 hours 

B. Required 

Action and 

associated 

Completion 

Time not met. 

B.1 Be in MODE 3. 6 hours 

 Entry into Condition A offers a choice between Required Action A.1 

or A.2. Required Action A.1 has a "once per" Completion Time, which 

qualifies for the 25% extension, per SR 3.0.2, to each performance after 

the initial performance. The initial 8 hour interval of Required Action A.1 

begins when Condition A is entered and the initial performance of 

Required Action A.1 must be complete within the first 8 hour interval. If 

Required Action A.1 is followed and the Required Action is not met within 

the Completion Time (plus the extension allowed by SR 3.0.2), 

Condition B is entered. If Required Action A.2 is followed and the 

Completion Time of 8 hours is not met, Condition B is entered. 

 If after entry into Condition B, Required Action A.1 or A.2 is met, 

Condition B is exited and operation may then continue in Condition A. 
Completion Times 

1.3 

CEOG STS 1.3-10 Rev. 3.0, 03/31/04 

1.3 Completion Times 

EXAMPLES (continued) 

 EXAMPLE 1.3-7

 ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One 

subsystem 

inoperable. 

A.1 Verify affected 

subsystem 

isolated. 

AND

A.2 Restore subsystem 

to OPERABLE 

status. 

1 hour 

AND

Once per 8 hours 

thereafter 

72 hours 

B. Required 

Action and 

associated 

Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

 Required Action A.1 has two Completion Times. The 1 hour Completion 

Time begins at the time the Condition is entered and each "Once per 

8 hours thereafter" interval begins upon performance of Required 

Action A.1. 

 If after Condition A is entered, Required Action A.1 is not met within either 

the initial 1 hour or any subsequent 8 hour interval from the previous 

performance (plus the extension allowed by SR 3.0.2), Condition B is 

entered. The Completion Time clock for Condition A does not stop after 

Condition B is entered, but continues from the time Condition A was 

initially entered. If Required Action A.1 is met after Condition B is 

entered, Condition B is exited and operation may continue in accordance 

with Condition A, provided the Completion Time for Required Action A.2 

has not expired. 
Completion Times 

1.3 

CEOG STS 1.3-11 Rev. 3.0, 03/31/04 

1.3 Completion Times 

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action 

COMPLETION TIME should be pursued without delay and in a controlled manner. 
Frequency 

1.4 

CEOG STS 1.4-1 Rev. 3.0, 03/31/04 

1.0 USE AND APPLICATION 

1.4 Frequency 

PURPOSE The purpose of this section is to define the proper use and application of 

Frequency requirements. 

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which 

the Surveillance must be met in order to meet the associated LCO. An 

understanding of the correct application of the specified Frequency is 

necessary for compliance with the SR. 

 The "specified Frequency" is referred to throughout this section and each 

of the Specifications of Section 3.0.2, Surveillance Requirement (SR) 

Applicability. The "specified Frequency" consists of the requirements of 

the Frequency column of each SR, as well as certain Notes in the 

Surveillance column that modify performance requirements. 

 Sometimes special situations dictate when the requirements of a 

Surveillance are to be met. They are "otherwise stated" conditions 

allowed by SR 3.0.1. They may be stated as clarifying Notes in the 

Surveillance, as part of the Surveillances, or both. 

 Situations where a Surveillance could be required (i.e., its Frequency 

could expire), but where it is not possible or not desired that it be 

performed until sometime after the associated LCO is within its 

Applicability, represent potential SR 3.0.4 conflicts. To avoid these 

conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such 

that it is only "required" when it can be and should be performed. With an 

SR satisfied, SR 3.0.4 imposes no restriction. 

 The use of "met" or "performed" in these instances conveys specific 

meanings. A Surveillance is "met" only when the acceptance criteria are 

satisfied. Known failure of the requirements of a Surveillance, even 

without a Surveillance specifically being "performed," constitutes a 

Surveillance not "met." "Performance" refers only to the requirement to 

specifically determine the ability to meet the acceptance criteria. 

 Some Surveillances contain Notes that modify the Frequency of 

performance or the conditions during which the acceptance criteria must 

be satisfied. For these Surveillances, the MODE-entry restrictions of 

SR 3.0.4 may not apply. Such a Surveillance is not required to be 

performed prior to entering a MODE or other specified condition in the 

Applicability of the associated LCO if any of the following three conditions 

are satisfied: 
Frequency 

1.4 

CEOG STS 1.4-2 Rev. 3.0, 03/31/04 

1.4 Frequency 

DESCRIPTION (continued) 

 a. The Surveillance is not required to be met in the MODE or other 

specified condition to be entered; or 

 b. The Surveillance is required to be met in the MODE or other 

specified condition to be entered, but has been performed within the 

specified Frequency (i.e., it is current) and is known not to be failed; 

or 

 c. The Surveillance is required to be met, but not performed, in the 

MODE or other specified condition to be entered, and is known not 

to be failed. 

 Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations. 

EXAMPLES The following examples illustrate the various ways that Frequencies are 

specified. In these examples, the Applicability of the LCO (LCO not 

shown) is MODES 1, 2, and 3. 
Frequency 

1.4 

CEOG STS 1.4-3 Rev. 3.0, 03/31/04 

1.4 Frequency 

EXAMPLES (continued) 

 EXAMPLE 1.4-1

 SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

Perform CHANNEL CHECK. 12 hours 

 Example 1.4-1 contains the type of SR most often encountered in the 

Technical Specifications (TS). The Frequency specifies an interval 

(12 hours) during which the associated Surveillance must be performed at 

least one time. Performance of the Surveillance initiates the subsequent 

interval. Although the Frequency is stated as 12 hours, an extension of 

the time interval to 1.25 times the stated Frequency is allowed by 

SR 3.0.2 for operational flexibility. The measurement of this interval 

continues at all times, even when the SR is not required to be met per 

SR 3.0.1 (such as when the equipment is inoperable, a variable is outside 

specified limits, or the unit is outside the Applicability of the LCO). If the 

interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or 

other specified condition in the Applicability of the LCO, and the 

performance of the Surveillance is not otherwise modified (refer to 

Example 1.4-3), then SR 3.0.3 becomes applicable. 

 If the interval as specified by SR 3.0.2 is exceeded while the unit is not in 

a MODE or other specified condition in the Applicability of the LCO for 

which performance of the SR is required, the Surveillance must be 

performed within the Frequency requirements of SR 3.0.2 prior to entry 

into the MODE or other specified condition. Failure to do so would result 

in a violation of SR 3.0.4. 
Frequency 

1.4 

CEOG STS 1.4-4 Rev. 3.0, 03/31/04 

1.4 Frequency 

EXAMPLES (continued) 

 EXAMPLE 1.4-2

 SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

Verify flow is within limits. Once within 

12 hours after 

≥ 25% RTP 

AND

24 hours thereafter 

 Example 1.4-2 has two Frequencies. The first is a one time performance 

Frequency, and the second is of the type shown in Example 1.4-1. The 

logical connector "AND" indicates that both Frequency requirements must 

be met. Each time reactor power is increased from a power level 

< 25% RTP to ≥ 25% RTP, the Surveillance must be performed within 

12 hours. 

 The use of "once" indicates a single performance will satisfy the specified 

Frequency (assuming no other Frequencies are connected by "AND"). 

This type of Frequency does not qualify for the extension allowed by 

SR 3.0.2. "Thereafter" indicates future performances must be established 

per SR 3.0.2, but only after a specified condition is first met (i.e., the 

"once" performance in this example). If reactor power decreases to 

< 25% RTP, the measurement of both intervals stops. New intervals start 

upon reactor power reaching 25% RTP. 
Frequency 

1.4 

CEOG STS 1.4-5 Rev. 3.0, 03/31/04 

1.4 Frequency 

EXAMPLES (continued) 

 EXAMPLE 1.4-3

 SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

-----------------------------NOTE----------------------------- 

Not required to be performed until 12 hours after 

≥ 25% RTP. 

------------------------------------------------------------------ 

Perform channel adjustment. 7 days 

 The interval continues, whether or not the unit operation is < 25% RTP 

between performances. 

 As the Note modifies the required performance of the Surveillance, it is 

construed to be part of the "specified Frequency." Should the 7 day 

interval be exceeded while operation is < 25% RTP, this Note allows 

12 hours after power reaches ≥ 25% RTP to perform the Surveillance. 

The Surveillance is still considered to be performed within the "specified 

Frequency." Therefore, if the Surveillance were not performed within the 

7 day (plus the extension allowed by SR 3.0.2) interval, but operation was 

< 25% RTP, it would not constitute a failure of the SR or failure to meet 

the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, 

even with the 7 day Frequency not met, provided operation does not 

exceed 12 hours with power ≥ 25% RTP. 

 Once the unit reaches 25% RTP, 12 hours would be allowed for 

completing the Surveillance. If the Surveillance were not performed 

within this 12 hour interval, there would then be a failure to perform a 

Surveillance within the specified Frequency, and the provisions of 

SR 3.0.3 would apply. 
Frequency 

1.4 

CEOG STS 1.4-6 Rev. 3.0, 03/31/04 

1.4 Frequency 

EXAMPLES (continued) 

 EXAMPLE 1.4-4

 SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

-----------------------------NOTE----------------------------- 

Only required to be met in MODE 1. 

------------------------------------------------------------------ 

Verify leakage rates are within limits. 24 hours 

 Example 1.4-4 specifies that the requirements of this Surveillance do not 

have to be met until the unit is in MODE 1. The interval measurement for 

the Frequency of this Surveillance continues at all times, as described in 

Example 1.4-1. However, the Note constitutes an "otherwise stated" 

exception to the Applicability of this Surveillance. Therefore, if the 

Surveillance were not performed within the 24 hour interval (plus the 

extension allowed by SR 3.0.2), but the unit was not in MODE 1, there 

would be no failure of the SR nor failure to meet the LCO. Therefore, no 

violation of SR 3.0.4 occurs when changing MODES, even with the 

24 hour Frequency exceeded, provided the MODE change was not made 

into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour 

Frequency were not met), SR 3.0.4 would require satisfying the SR. 
Frequency 

1.4 

CEOG STS 1.4-7 Rev. 3.0, 03/31/04 

1.4 Frequency 

EXAMPLES (continued) 

 EXAMPLE 1.4-5

 SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

-----------------------------NOTE----------------------------- 

Only required to be performed in MODE 1. 

------------------------------------------------------------------ 

Perform complete cycle of the valve. 7 days 

 The interval continues, whether or not the unit operation is in MODE 1, 2, 

or 3 (the assumed Applicability of the associated LCO) between 

performances. 

 As the Note modifies the required performance of the Surveillance, the 

Note is construed to be part of the "specified Frequency." Should the 

7 day interval be exceeded while operation is not in MODE 1, this Note 

allows entry into and operation in MODES 2 and 3 to perform the 

Surveillance. The Surveillance is still considered to be performed within 

the "specified Frequency" if completed prior to entering MODE 1. 

Therefore, if the Surveillance were not performed within the 7 day (plus 

the extension allowed by SR 3.0.2) interval, but operation was not in 

MODE 1, it would not constitute a failure of the SR or failure to meet the 

LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even 

with the 7 day Frequency not met, provided operation does not result in 

entry into MODE 1. 

 Once the unit reaches MODE 1, the requirement for the Surveillance to 

be performed within its specified Frequency applies and would require 

that the Surveillance had been performed. If the Surveillance were not 

performed prior to entering MODE 1, there would then be a failure to 

perform a Surveillance within the specified Frequency, and the provisions 

of SR 3.0.3 would apply. 
Frequency 

1.4 

CEOG STS 1.4-8 Rev. 3.0, 03/31/04 

1.4 Frequency 

EXAMPLES (continued) 

 EXAMPLE 1.4-6

 SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

-----------------------------NOTE----------------------------- 

Only required to be met in MODE 3. 

------------------------------------------------------------------ 

Verify parameter is within limits. 24 hours 

 Example 1.4-[6] specifies that the requirements of this Surveillance do not 

have to be met while the unit is in MODE 3 (the assumed Applicability of 

the associated LCO is MODES 1, 2, and 3). The interval measurement 

for the Frequency of this Surveillance continues at all times, as described 

in Example 1.4-1. However, the Note constitutes an "otherwise stated" 

exception to the Applicability of this Surveillance. Therefore, if the 

Surveillance were not performed within the 24 hour interval (plus the 

extension allowed by SR 3.0.2), and the unit was in MODE 3, there would 

be no failure of the SR nor failure to meet the LCO. Therefore, no 

violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, 

even with the 24 hour Frequency exceeded, provided the MODE change 

does not result in entry into MODE 2. Prior to entering MODE 2 

(assuming again that the 24 hour Frequency were not met), SR 3.0.4 

would require satisfying the SR. 
SLs (Analog) 

2.0 

CEOG STS 2.0-1 Rev. 3.0, 03/31/04 

2.0 SAFETY LIMITS (SLs) (Analog) 

2.1 SLs 

 2.1.1 Reactor Core SLs

 2.1.1.1 In MODES 1 and 2, the combination of THERMAL POWER, 

pressurizer pressure, and the highest operating loop cold leg coolant 

temperature shall not exceed the limits shown in Figure 2.1.1-1. 

 2.1.1.2 In MODES 1 and 2, peak fuel centerline temperature shall be 

maintained at < [5080]°F, decreasing by [58°F per 10,000 MWD/MTU] 

and adjusted for burnable poison per [CENPD-275-P, Revision 1-P-A 

or CENPD-382-P-A]. 

 2.1.2 Reactor Coolant System Pressure SL

 In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained ≤ [2750] psia. 

2.2 SAFETY LIMIT VIOLATIONS 

 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour. 

 2.2.2 If SL 2.1.2 is violated: 

 2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour. 

 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes. 
SLs (Analog) 

2.0 

CEOG STS 2.0-2 Rev. 3.0, 03/31/04 
SLs (Digital) 

2.0 

CEOG STS 2.0-1 Rev. 3.0, 03/31/04 

2.0 SAFETY LIMITS (SLs) (Digital) 

2.1 SLs 

 2.1.1 Reactor Core SLs

 2.1.1.1 In MODES 1 and 2, departure from nucleate boiling ratio (DNBR) shall 

be maintained at ≥ [1.19]. 

 2.1.1.2 In MODES 1 and 2, the peak fuel centerline temperature shall be 

maintained at < [5080]°F, decreasing by [58°F per 10,000 MWD/MTU] 

and adjusted for burnable poison per [CENPD-275-P, Revision 1-P-A 

or CENPD-382-P-A]. 

 2.1.2 Reactor Coolant System Pressure SL

 In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained ≤ [2750] psia. 

2.2 SAFETY LIMIT VIOLATIONS 

 2.2.1 If SL 2.1.1.1 or SL 2.1.1.2 is violated, restore compliance and be in MODE 3 

within 1 hour. 

 2.2.2 If SL 2.1.2 is violated: 

 2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour. 

 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes. 
LCO Applicability 

3.0 

CEOG STS 3.0-1 Rev. 3.0, 03/31/04 

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 

LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the 

Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7. 

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the 

associated Conditions shall be met, except as provided in LCO 3.0.5 and 

LCO 3.0.6. 

 If the LCO is met or is no longer applicable prior to expiration of the 

specified Completion Time(s), completion of the Required Action(s) is not 

required, unless otherwise stated. 

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an 

associated ACTION is not provided, or if directed by the associated 

ACTIONS, the unit shall be placed in a MODE or other specified condition 

in which the LCO is not applicable. Action shall be initiated within 1 hour 

to place the unit, as applicable, in: 

 a. MODE 3 within 7 hours, 

 b. [MODE 4 within 13] hours, and 

 c. MODE 5 within 37 hours. 

 Exceptions to this Specification are stated in the individual Specifications. 

 Where corrective measures are completed that permit operation in 

accordance with the LCO or ACTIONS, completion of the actions required 

by LCO 3.0.3 is not required. 

 LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4. 

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition 

in the Applicability shall only be made: 

 a. When the associated ACTIONS to be entered permit continued 

operation in the MODE or other specified condition in the 

Applicability for an unlimited period of time; 

 b. After performance of a risk assessment addressing inoperable 

systems and components, consideration of the results, 

determination of the acceptability of entering the MODE or other 

specified condition in the Applicability, and establishment of risk 

management actions, if appropriate; exceptions to this Specification 

are stated in the individual Specifications, or 

 c. When an allowance is stated in the individual value, parameter, or 

other Specification. 
LCO Applicability 

3.0 

CEOG STS 3.0-2 Rev. 3.0, 03/31/04 

3.0 LCO Applicability 

LCO 3.0.4 (continued) 

 This Specification shall not prevent changes in MODES or other specified 

conditions in the Applicability that are required to comply with ACTIONS 

or that are part of a shutdown of the unit. 

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with 

ACTIONS may be returned to service under administrative control solely 

to perform testing required to demonstrate its OPERABILITY or the 

OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for 

the system returned to service under administrative control to perform the 

testing required to demonstrate OPERABILITY. 

LCO 3.0.6 When a supported system LCO is not met solely due to a support system 

LCO not being met, the Conditions and Required Actions associated with 

this supported system are not required to be entered. Only the support 

system LCO ACTIONS are required to be entered. This is an exception 

to LCO 3.0.2 for the supported system. In this event, an evaluation shall 

be performed in accordance with Specification 5.5.15, "Safety Function 

Determination Program (SFDP)." If a loss of safety function is determined 

to exist by this program, the appropriate Conditions and Required Actions 

of the LCO in which the loss of safety function exists are required to be 

entered. 

 When a support system's Required Action directs a supported system to 

be declared inoperable or directs entry into Conditions and Required 

Actions for a supported system, the applicable Conditions and Required 

Actions shall be entered in accordance with LCO 3.0.2. 

LCO 3.0.7 Special test exception (STE) LCOs [in each applicable LCO section] allow 

specified Technical Specifications (TS) requirements to be changed to 

permit performance of special tests and operations. Unless otherwise 

specified, all other TS requirements remain unchanged. Compliance with 
LCO Applicability 

3.0 

CEOG STS 3.0-3 Rev. 3.0, 03/31/04 

3.0 LCO Applicability 

LCO 3.0.7 (continued) 

 STE LCOs is optional. When an STE LCO is desired to be met but is not 

met, the ACTIONS of the STE LCO shall be met. When an STE LCO is 

not desired to be met, entry into a MODE or other specified condition in 

the Applicability shall only be made in accordance with the other 

applicable Specifications. 
SR Applicability 

3.0 

CEOG STS 3.0-4 Rev. 3.0, 03/31/04 

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 

SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the 

Applicability for individual LCOs, unless otherwise stated in the SR. 

Failure to meet a Surveillance, whether such failure is experienced during 

the performance of the Surveillance or between performances of the 

Surveillance, shall be failure to meet the LCO. Failure to perform a 

Surveillance within the specified Frequency shall be failure to meet the 

LCO except as provided in SR 3.0.3. Surveillances do not have to be 

performed on inoperable equipment or variables outside specified limits. 

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is 

performed within 1.25 times the interval specified in the Frequency, as 

measured from the previous performance or as measured from the time a 

specified condition of the Frequency is met. 

 For Frequencies specified as "once," the above interval extension does 

not apply. 

 If a Completion Time requires periodic performance on a "once per . . ." 

basis, the above Frequency extension applies to each performance after 

the initial performance. 

 Exceptions to this Specification are stated in the individual Specifications. 

SR 3.0.3 If it is discovered that a Surveillance was not performed within its 

specified Frequency, then compliance with the requirement to declare the 

LCO not met may be delayed, from the time of discovery, up to 24 hours 

or up to the limit of the specified Frequency, whichever is greater. This 

delay period is permitted to allow performance of the Surveillance. A risk 

evaluation shall be performed for any Surveillance delayed greater than 

24 hours and the risk impact shall be managed. 

 If the Surveillance is not performed within the delay period, the LCO must 

immediately be declared not met, and the applicable Condition(s) must be 

entered. 

 When the Surveillance is performed within the delay period and the 

Surveillance is not met, the LCO must immediately be declared not met, 

and the applicable Condition(s) must be entered. 
SR Applicability 

3.0 

CEOG STS 3.0-5 Rev. 3.0, 03/31/04 

3.0 SR Applicability 

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an 

LCO shall only be made when the LCO's Surveillances have been met 

within their specified Frequency, except as provided by SR 3.0.3. When 

an LCO is not met due to Surveillances not having been met, entry into a 

MODE or other specified condition in the Applicability shall only be made 

in accordance with LCO 3.0.4. 

 This provision shall not prevent entry into MODES or other specified 

conditions in the Applicability that are required to comply with ACTIONS 

or that are part of a shutdown of the unit. 
SDM (Analog) 

3.1.1 

CEOG STS 3.1.1-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.1 SHUTDOWN MARGIN (SDM) (Analog) 

LCO 3.1.1 SDM shall be within the limits specified in the COLR. 

APPLICABILITY: MODES 3, 4, and 5. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. SDM not within limits. A.1 Initiate boration to restore 

SDM to within limits. 

15 minutes 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.1.1 Verify SDM to be within the limits specified in the 

COLR. 

24 hours 
SDM (Digital) 

3.1.1 

CEOG STS 3.1.1-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.1 SHUTDOWN MARGIN (SDM) (Digital) 

LCO 3.1.1 SDM shall be within the limits specified in the COLR. 

APPLICABILITY: MODES 3, 4, and 5. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. SDM not within limit. A.1 Initiate boration to restore 

SDM to within limit. 

15 minutes 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.1.1 Verify SDM to be within the limits specified in the 

COLR. 

24 hours 
Reactivity Balance (Analog) 

3.1.2 

CEOG STS 3.1.2-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.2 Reactivity Balance (Analog) 

LCO 3.1.2 The core reactivity balance shall be within ± 1% ∆k/k of predicted values. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Core reactivity balance 

not within limit. 

A.1 Re-evaluate core design 

and safety analysis and 

determine that the reactor 

core is acceptable for 

continued operation. 

AND

A.2 Establish appropriate 

operating restrictions and 

SRs. 

7 days 

7 days 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 6 hours 
Reactivity Balance (Analog) 

3.1.2 

CEOG STS 3.1.2-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.2.1 ------------------------------NOTES----------------------------- 

 1. The predicted reactivity values may be adjusted 

(normalized) to correspond to the measured 

core reactivity prior to exceeding a fuel burnup 

of 60 effective full power days (EFPD) after 

each fuel loading. 

 2. This Surveillance is not required to be 

performed prior to entry into MODE 2. 

 --------------------------------------------------------------------- 

 Verify overall core reactivity balance is within 

± 1.0% ∆k/k of predicted values. 

Prior to entering 

MODE 1 after fuel 

loading 

AND

--------NOTE-------- 

Only required 

after 60 EFPD 

------------------------ 

31 EFPD 
Reactivity Balance (Digital) 

3.1.2 

CEOG STS 3.1.2-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.2 Reactivity Balance (Digital) 

LCO 3.1.2 The core reactivity balance shall be within ± 1% ∆k/k of predicted values. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Core reactivity balance 

not within limit. 

A.1 Re-evaluate core design 

and safety analysis and 

determine that the reactor 

core is acceptable for 

continued operation. 

AND

A.2 Establish appropriate 

operating restrictions and 

SRs. 

7 days 

7 days 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 6 hours 
Reactivity Balance (Digital) 

3.1.2 

CEOG STS 3.1.2-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.2.1 ------------------------------NOTES----------------------------- 

 1. The predicted reactivity values may be adjusted 

(normalized) to correspond to the measured 

core reactivity prior to exceeding a fuel burnup 

of 60 effective full power days (EFPD) after 

each fuel loading. 

 2. This Surveillance is not required to be 

performed prior to entry into MODE 2. 

 --------------------------------------------------------------------- 

 Verify overall core reactivity balance is within 

± 1.0% ∆k/k of predicted values. 

Prior to entering 

MODE 1 after fuel 

loading 

AND

--------NOTE-------- 

Only required 

after 60 EFPD 

------------------------ 

31 EFPD 
MTC (Analog) 

3.1.3 

CEOG STS 3.1.3-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.3 Moderator Temperature Coefficient (MTC) (Analog) 

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR. The 

maximum positive limit shall be that specified in Figure 3.1.3-1. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. MTC not within limits. A.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.3.1 Verify MTC is within the upper limit. Prior to entering 

MODE 1 after 

each fuel loading 
MTC (Analog) 

3.1.3 

CEOG STS 3.1.3-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.1.3.2 -------------------------------NOTE------------------------------ 

 If the MTC is more negative than the COLR limit 

when extrapolated to the end of cycle, SR 3.1.3.2 

may be repeated. Shutdown must occur prior to 

exceeding the minimum allowable boron 

concentration at which MTC is projected to exceed 

the lower limit. 

 --------------------------------------------------------------------- 

 Verify MTC is within the lower limit specified in the 

COLR. 

Each fuel cycle 

within 7 effective 

full power days 

(EFPD) of 

reaching 40 EFPD 

core burnup 

AND

Each fuel cycle 

within 7 EFPD of 

reaching 2/3 of 

expected core 

burnup 
MTC (Analog) 

3.1.3 

CEOG STS 3.1.3-3 Rev. 3.0, 03/31/04 

Figure 3.1.3-1 (page 1 of 1) 

Allowable Positive MTC Limit 
MTC (Digital) 

3.1.3 

CEOG STS 3.1.3-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.3 Moderator Temperature Coefficient (MTC) (Digital) 

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR, and 

a maximum positive limit as specified below: 

 a. [0.5 E-4 ∆k/k/°F] when THERMAL POWER is ≤ 70% RTP and 

 b. [0.0 ∆k/k/°F] when THERMAL POWER is > 70% RTP. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. MTC not within limits. A.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.3.1 Verify MTC is within the upper limit. Prior to entering 

MODE 1 after 

each fuel loading 
MTC (Digital) 

3.1.3 

CEOG STS 3.1.3-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.1.3.2 -------------------------------NOTE------------------------------ 

 If the MTC is more negative than the COLR limit 

when extrapolated to the end of cycle, SR 3.1.3.2 

may be repeated. Shutdown must occur prior to 

exceeding the minimum allowable boron 

concentration at which MTC is projected to exceed 

the lower limit. 

 --------------------------------------------------------------------- 

 Verify MTC is within the lower limit. Each fuel cycle 

within 7 effective 

full power days 

(EFPD) of 

reaching 40 EFPD 

core burnup 

AND

Each fuel cycle 

within 7 EFPD of 

reaching 2/3 of 

expected core 

burnup 
CEA Alignment (Analog) 

3.1.4 

CEOG STS 3.1.4-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.4 Control Element Assembly (CEA) Alignment (Analog) 

LCO 3.1.4 All CEAs shall be OPERABLE. 

 AND

 All CEAs shall be aligned to within [7] inches (indicated position) of their 

respective group, and [the CEA motion inhibit and the CEA deviation 

circuit shall be OPERABLE]. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more CEAs 

misaligned from its 

group by > [7 inches] 

and ≤ [15 inches]. 

 OR

 One CEA misaligned 

from its group by 

> [15 inches]. 

A.1 Reduce THERMAL 

POWER to ≤ 70% RTP. 

AND

A.2 Restore CEA Alignment. 

1 hour 

2 hours 

B. CEA motion inhibit 

inoperable. 

B.1 Perform SR 3.1.4.1. 

AND

B.2.1 Restore CEA motion inhibit 

to OPERABLE status. 

 OR

1 hour 

AND

Every 4 hours 

thereafter 

6 hours 
CEA Alignment (Analog) 

3.1.4 

CEOG STS 3.1.4-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.2.2 --------------NOTE-------------- 

 Required Action B.2.2 shall 

not be performed when in 

conflict with either Required 

Action A.1, A.2, or C.1. 

 ------------------------------------- 

 Place and maintain the 

CEA drive switch in either 

the "off" or "manual" 

position, [and fully withdraw 

all CEAs in groups 3 and 4 

and withdraw all CEAs in 

group 5 to < 5% insertion]. 

6 hours 

C. CEA deviation circuit 

inoperable. 

C.1 Perform SR 3.1.4.1. 1 hour 

AND

Every 4 hours 

thereafter 

D. Required Action and 

associated Completion 

Time of Conditions A, B, 

or C not met. 

 OR

 One or more CEAs 

inoperable. 

 OR

 Two or more CEAs 

misaligned by 

> [15 inches]. 

D.1 Be in MODE 3. 6 hours 
CEA Alignment (Analog) 

3.1.4 

CEOG STS 3.1.4-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.4.1 Verify the indicated position of each CEA to be 

within [7 inches] of all other CEAs in its group. 

Within 1 hour 

following any CEA 

movement of 

> [7 inches] 

AND

12 hours 

SR 3.1.4.2 Verify the CEA motion inhibit is OPERABLE. 92 days 

SR 3.1.4.3 Verify the CEA deviation circuit is OPERABLE. 92 days 

SR 3.1.4.4 Verify CEA freedom of movement (trippability) by 

moving each individual CEA that is not fully inserted 

into the reactor core [5 inches] in either direction. 

92 days 

SR 3.1.4.5 Perform a CHANNEL FUNCTIONAL TEST of the 

reed switch position transmitter channel. 

18 months 

SR 3.1.4.6 Verify each CEA drop time is ≤ [3.1] seconds. Prior to reactor 

criticality, after 

each removal of 

the reactor head 
CEA Alignment (Digital) 

3.1.4 

CEOG STS 3.1.4-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.4 Control Element Assembly (CEA) Alignment (Digital) 

LCO 3.1.4 All full length CEAs shall be OPERABLE. 

 AND

 All full and part length CEAs shall be aligned to within [7 inches] 

(indicated position) of their respective groups. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more CEAs 

misaligned from its 

group by > [7 inches] 

and ≤ [19 inches]. 

 OR

 One CEA misaligned 

from its group by 

> [19 inches]. 

A.1 Reduce THERMAL 

POWER in accordance with 

Figure 3.1.4-1. 

AND

A.2 Restore CEA Alignment. 

1 hour 

2 hours 

B. Required Action and 

associated Completion 

Time not met. 

 OR

 One or more full length 

CEAs inoperable. 

 OR

 Two or more CEAs 

misaligned by 

> [19 inches]. 

B.1 Be in MODE 3. 6 hours 
CEA Alignment (Digital) 

3.1.4 

CEOG STS 3.1.4-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.4.1 Verify the indicated position of each full and part 

length CEA is within [7 inches] of all other CEAs in 

its group. 

12 hours 

SR 3.1.4.2 Verify that, for each CEA, its OPERABLE CEA 

position indicator channels indicate within [5 inches] 

of each other. 

12 hours 

SR 3.1.4.3 Verify full length CEA freedom of movement 

(trippability) by moving each individual full length 

CEA that is not fully inserted in the core at least 

[5 inches]. 

92 days 

SR 3.1.4.4 Perform a CHANNEL FUNCTIONAL TEST of each 

reed switch position transmitter channel. 

[18] months 

SR 3.1.4.5 Verify each full length CEA drop time 

≤ [3.5] seconds and the arithmetic average of all full 

length CEA drop times ≤ [3.2] seconds. 

Prior to reactor 

criticality, after 

each removal of 

the reactor head 
CEA Alignment (Digital) 

3.1.4 

CEOG STS 3.1.4-3 Rev. 3.0, 03/31/04 

------------------------------------------------------------NOTE----------------------------------------------------------- 

When core power is reduced to 60% RTP per this limit curve, further reduction is not required by 

this Specification. 

-------------------------------------------------------------------------------------------------------------------------------

 [ NOT TO BE USED FOR OPERATION. 

 FOR ILLUSTRATION PURPOSES ONLY. ] 

Figure 3.1.4-1 (page 1 of 1) 

Required Power Reduction After CEA Deviation 
Shutdown CEA Insertion Limits (Analog) 

3.1.5 

CEOG STS 3.1.5-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.5 Shutdown Control Element Assembly (CEA) Insertion Limits (Analog) 

LCO 3.1.5 All shutdown CEAs shall be withdrawn to ≥ [129] inches. 

APPLICABILITY: MODE 1, 

 MODE 2 with any regulating CEA not fully inserted. 

 ---------------------------------------------NOTE-------------------------------------------- 

 This LCO is not applicable while performing SR 3.1.4.4. 

-------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more shutdown 

CEAs not within limit. 

A.1 Restore shutdown CEA(s) 

to within limit. 

2 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.5.1 Verify each shutdown CEA is withdrawn 

≥ [129] inches. 

12 hours 
Shutdown CEA Insertion Limits (Digital) 

3.1.5 

CEOG STS 3.1.5-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.5 Shutdown Control Element Assembly (CEA) Insertion Limits (Digital) 

LCO 3.1.5 All shutdown CEAs shall be withdrawn to ≥ [145] inches. 

APPLICABILITY: MODE 1, 

 MODE 2 with any regulating CEA not fully inserted. 

 ---------------------------------------------NOTE-------------------------------------------- 

 This LCO is not applicable while performing SR 3.1.4.3. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more shutdown 

CEAs not within limit. 

A.1 Restore shutdown CEA(s) 

to within limit. 

2 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.5.1 Verify each shutdown CEA is withdrawn 

≥ [145] inches. 

12 hours 
Regulating CEA Insertion Limits (Analog) 

3.1.6 

CEOG STS 3.1.6-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (Analog) 

LCO 3.1.6 The power dependent insertion limit (PDIL) alarm circuit shall be 

OPERABLE, and the regulating CEA groups shall be limited to the 

withdrawal sequence and to the insertion limits specified in the COLR. 

APPLICABILITY: MODES 1 and 2. 

 ---------------------------------------------NOTE-------------------------------------------- 

 This LCO is not applicable while performing SR 3.1.4.4 [or during reactor 

power cutback operation]. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Regulating CEA groups 

inserted beyond the 

transient insertion limit. 

A.1 Restore regulating CEA 

groups to within limits. 

OR

A.2 Reduce THERMAL 

POWER to less than or 

equal to the fraction of RTP 

allowed by the CEA group 

position and insertion limits 

specified in the COLR. 

2 hours 

2 hours 

B. Regulating CEA groups 

inserted between the 

long term steady state 

insertion limit and the 

transient insertion limit 

for > 4 hours per 24 hour 

interval. 

B.1 Verify short term steady 

state insertion limits are not 

exceeded. 

OR

B.2 Restrict increases in 

THERMAL POWER to 

≤ 5% RTP per hour. 

15 minutes 

15 minutes 
Regulating CEA Insertion Limits (Analog) 

3.1.6 

CEOG STS 3.1.6-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. Regulating CEA groups 

inserted between the 

long term steady state 

insertion limit and the 

transient insertion limit 

for intervals > 5 effective 

full power days (EFPD) 

per 30 EFPD interval or 

> 14 EFPD per 

365 EFPD. 

C.1 Restore regulating CEA 

groups to within limits. 

2 hours 

D. PDIL alarm circuit 

inoperable. 

D.1 Perform SR 3.1.6.1. 1 hour 

AND

Once per 4 hours 

thereafter 

E. Required Action and 

associated Completion 

Time not met. 

E.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.6.1 -------------------------------NOTE------------------------------ 

 Not required to be performed until 12 hours after 

entry into MODE 2. 

 --------------------------------------------------------------------- 

 Verify each regulating CEA group position is within 

its insertion limits. 

12 hours 
Regulating CEA Insertion Limits (Analog) 

3.1.6 

CEOG STS 3.1.6-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.1.6.2 Verify the accumulated times during which the 

regulating CEA groups are inserted beyond the 

steady state insertion limits but within the transient 

insertion limits. 

24 hours 

SR 3.1.6.3 Verify PDIL alarm circuit is OPERABLE. 31 days 
Regulating CEA Insertion Limits (Digital) 

3.1.6 

CEOG STS 3.1.6-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (Digital) 

LCO 3.1.6 The power dependent insertion limit (PDIL) alarm circuit shall be 

OPERABLE and 

 a. With the Core Operating Limit Supervisory System (COLSS) in 

service, the regulating CEA groups shall be limited to the withdrawal 

sequence, insertion limits, and associated time restraints specified 

in the COLR. 

 b. With COLSS out of service, the regulating CEA groups shall be 

limited to the short term steady state insertion limit and associated 

time restraints specified in the COLR. 

APPLICABILITY: MODES 1 and 2. 

 ---------------------------------------------NOTE-------------------------------------------- 

 This LCO is not applicable while conducting SR 3.1.4.3 [or during reactor 

power cutback operation]. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Regulating CEA groups 

inserted beyond the 

transient insertion limit 

with COLSS in service. 

A.1 Restore regulating CEA 

groups to within limits. 

OR

A.2 Reduce THERMAL 

POWER to less than or 

equal to the fraction of RTP 

allowed by the CEA group 

position and insertion limits 

specified in the COLR. 

2 hours 

2 hours 
Regulating CEA Insertion Limits (Digital) 

3.1.6 

CEOG STS 3.1.6-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. Regulating CEA groups 

inserted between the 

long term steady state 

insertion limit and the 

transient insertion limit 

for > 4 hours per 24 hour 

interval with COLSS in 

service. 

B.1 Verify short term steady 

state insertion limits are not 

exceeded. 

OR

B.2 Restrict increases in 

THERMAL POWER to 

≤ 5% RTP per hour. 

15 minutes 

15 minutes 

C. Regulating CEA groups 

inserted between the 

long term steady state 

insertion limit and the 

transient insertion limit 

for intervals > 5 effective 

full power days (EFPD) 

per 30 EFPD interval or 

> 14 EFPD per 

365 EFPD interval with 

COLSS in service. 

C.1 Restore regulating CEA 

groups to within limits. 

2 hours 

D. Regulating CEA groups 

inserted beyond the 

short term steady state 

insertion limit with 

COLSS out of service. 

D.1 Restore regulating CEA 

groups to within limits. 

OR

D.2 Reduce THERMAL 

POWER to less than or 

equal to the fraction of RTP 

allowed by CEA group 

position and short term 

steady state insertion limit 

specified in the COLR. 

2 hours 

2 hours 

E. PDIL alarm circuit 

inoperable. 

E.1 Perform SR 3.1.6.1. 1 hour 

AND

Once per 4 hours 

thereafter 
Regulating CEA Insertion Limits (Digital) 

3.1.6 

CEOG STS 3.1.6-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

F. Required Actions and 

associated Completion 

Times not met. 

F.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.6.1 -------------------------------NOTE------------------------------ 

 Not required to be performed until 12 hours after 

entry into MODE 2. 

 --------------------------------------------------------------------- 

 Verify each regulating CEA group position is within 

its insertion limits. 

12 hours 

SR 3.1.6.2 Verify the accumulated times during which the 

regulating CEA groups are inserted beyond the 

steady state insertion limits but within the transient 

insertion limits. 

24 hours 

SR 3.1.6.3 Verify PDIL alarm circuit is OPERABLE. 31 days 
STE - SDM (Analog) 

3.1.7 

CEOG STS 3.1.7-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.7 Special Test Exceptions (STE) - SHUTDOWN MARGIN (SDM) (Analog) 

LCO 3.1.7 During performance of PHYSICS TESTS, the requirements of: 

 LCO 3.1.1, "SHUTDOWN MARGIN," 

 LCO 3.1.5, "Shutdown Control Element Assembly Insertion Limits," and 

 LCO 3.1.6, "Regulating Control Element Assembly Insertion Limits," 

 may be suspended for measurement of Control Element Assembly (CEA) 

worth, provided shutdown reactivity equivalent to at least the highest 

estimated CEA worth (of those CEAs actually withdrawn) is available for 

trip insertion. 

APPLICABILITY: MODES 2 and 3 during PHYSICS TESTS. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Operation in MODE 3 shall be limited to 6 consecutive hours. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Any CEA not fully 

inserted and less than 

the above shutdown 

reactivity equivalent 

available for trip 

insertion. 

 OR

 All CEAs inserted and 

the reactor subcritical by 

less than the above 

shutdown reactivity 

equivalent. 

A.1 Initiate boration to restore 

required shutdown 

reactivity. 

15 minutes 
STE - SDM (Analog) 

3.1.7 

CEOG STS 3.1.7-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.7.1 Verify that the position of each CEA not fully 

inserted is within the acceptance criteria for 

available negative reactivity addition. 

2 hours 

SR 3.1.7.2 -------------------------------NOTE------------------------------ 

 Not required to be performed during initial power 

escalation following a refueling outage if SR 3.1.4.6 

has been met. 

 --------------------------------------------------------------------- 

 Verify that each CEA not fully inserted is capable of 

full insertion when tripped from at least the 50% 

withdrawn position. 

Once within 

[7 days] prior to 

reducing SDM to 

less than the 

limits of 

LCO 3.1.1 
Part Length CEA Insertion Limits (Digital) 

3.1.7 

CEOG STS 3.1.7-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.7 Part Length Control Element Assembly (CEA) Insertion Limits (Digital) 

LCO 3.1.7 The part length CEA groups shall be limited to the insertion limits 

specified in the COLR. 

APPLICABILITY: MODE 1 > 20% RTP. 

 ---------------------------------------------NOTE-------------------------------------------- 

 This LCO not applicable while exercising part length CEAs. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Part length CEA groups 

inserted beyond the 

transient insertion limit. 

A.1 Restore part length CEA 

groups to within the limit. 

OR

A.2 Reduce THERMAL 

POWER to less than or 

equal to that fraction of 

RTP specified in the COLR. 

2 hours 

2 hours 

B. Part length CEA groups 

inserted between the 

long term steady state 

insertion limit and the 

transient insertion limit 

for intervals ≥ 7 effective 

full power days (EFPD) 

per 30 EFPD or 

≥ 14 EFPD per 

365 EFPD interval. 

B.1 Restore part length CEA 

groups to within the long 

term steady state insertion 

limit. 

2 hours 
Part Length CEA Insertion Limits (Digital) 

3.1.7 

CEOG STS 3.1.7-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. Required Action and 

associated Completion 

Time of Condition B not 

met. 

C.1 Reduce THERMAL 

POWER to ≤ 20% RTP. 

4 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.7.1 Verify part length CEA group position. 12 hours 
STE - MODES 1 and 2 (Analog) 

3.1.8 

CEOG STS 3.1.8-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.8 Special Test Exceptions (STE) - MODES 1 and 2 (Analog) 

LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of: 

 LCO 3.1.3, "Moderator Temperature Coefficient (MTC)," 

 LCO 3.1.4, "Control Element Assembly (CEA) Alignment," 

 LCO 3.1.5, "Shutdown Control Element Assembly (CEA) Insertion 

Limits," 

 LCO 3.1.6, "Regulating Control Element Assembly (CEA) Insertion 

Limits," 

 LCO 3.2.2, "Total Planar Radial Peaking Factor ( T FXY )," 

 LCO 3.2.3, "Total Integrated Radial Peaking Factor ( T Fr )," and 

 LCO 3.2.4, "AZIMUTHAL POWER TILT (Tq)," 

 may be suspended, provided THERMAL POWER is restricted to the test 

power plateau, which shall not exceed 85% RTP. 

APPLICABILITY: MODES 1 and 2 during PHYSICS TESTS. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Test power plateau 

exceeded. 

A.1 Reduce THERMAL 

POWER to less than or 

equal to test power plateau. 

15 minutes 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Suspend PHYSICS TESTS. 1 hour 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.8.1 Verify THERMAL POWER is equal to or less than 

the test power plateau. 

1 hour 
STE - SDM (Digital) 

3.1.8 

CEOG STS 3.1.8-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.8 Special Test Exceptions (STE) - SHUTDOWN MARGIN (SDM) (Digital) 

LCO 3.1.8 During performance of PHYSICS TESTS, the requirements of: 

 LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," 

 LCO 3.1.5, "Shutdown Control Element Assembly (CEA) Insertion 

Limits," and 

 LCO 3.1.6, "Regulating Control Element Assembly (CEA) Insertion 

Limits," 

 may be suspended for measurement of CEA worth, provided shutdown 

reactivity equivalent to at least the highest estimated CEA worth (of those 

CEAs actually withdrawn) is available for trip insertion. 

APPLICABILITY: MODES 2 and 3 during PHYSICS TESTS. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Operation in MODE 3 shall be limited to 6 consecutive hours. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Any full length CEA not 

fully inserted and less 

than the required 

shutdown reactivity 

available for trip 

insertion. 

 OR

 All full length CEAs 

inserted and the reactor 

subcritical by less than 

the above required 

shutdown reactivity 

equivalent. 

A.1 Initiate boration to restore 

required shutdown 

reactivity. 

15 minutes 
STE - SDM (Digital) 

3.1.8 

CEOG STS 3.1.8-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.8.1 Verify that the position of each CEA not fully 

inserted is within the acceptance criteria for 

available negative reactivity addition. 

2 hours 

SR 3.1.8.2 -------------------------------NOTE------------------------------ 

 Not required to be performed during initial power 

escalation following a refueling outage if SR 3.1.4.5 

has been met. 

 --------------------------------------------------------------------- 

 Verify each full length CEA not fully inserted is 

capable of full insertion when tripped from at least 

the 50% withdrawn position. 

Once within 

[7 days] prior to 

reducing SDM to 

less than the 

limits of 

LCO 3.1.1 
STE - MODES 1 and 2 (Digital) 

3.1.9 

CEOG STS 3.1.9-1 Rev. 3.0, 03/31/04 

3.1 REACTIVITY CONTROL SYSTEMS 

3.1.9 Special Test Exceptions (STE) - MODES 1 and 2 (Digital) 

LCO 3.1.9 During performance of PHYSICS TESTS, the requirements of: 

 LCO 3.1.3, "Moderator Temperature Coefficient (MTC)," 

 LCO 3.1.4, "Control Element Assembly (CEA) Alignment," 

 LCO 3.1.5, "Shutdown Control Element Assembly (CEA) Insertion 

Limits," 

 LCO 3.1.6, "Regulating Control Element Assembly (CEA) Insertion 

Limits," 

 LCO 3.1.7, "Part Length Control Element Assembly (CEA) Insertion 

Limits," 

 LCO 3.2.2, "Planar Radial Peaking Factors (FXY)," and 

 LCO 3.2.3, "AZIMUTHAL POWER TILT (Tq)," 

 may be suspended, provided THERMAL POWER is restricted to the test 

power plateau, which shall not exceed 85% RTP. 

APPLICABILITY: MODES 1 and 2 during PHYSICS TESTS. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Test power plateau 

exceeded. 

A.1 Reduce THERMAL 

POWER to less than or 

equal to the test power 

plateau. 

15 minutes 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Suspend PHYSICS TESTS. 1 hour 
STE - MODES 1 and 2 (Digital) 

3.1.9 

CEOG STS 3.1.9-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.1.9.1 Verify THERMAL POWER equal to or less than the 

test power plateau. 

1 hour 
LHR (Analog) 

3.2.1 

CEOG STS 3.2.1-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.1 Linear Heat Rate (LHR) (Analog) 

LCO 3.2.1 LHR shall not exceed the limits specified in the COLR. 

APPLICABILITY: MODE 1. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. LHR, as determined by 

the Incore Detector 

Monitoring System, 

exceeds the limits 

specified in the COLR, 

as indicated by four or 

more coincident incore 

channels. 

 OR

 LHR, as determined by 

the Excore Detector 

Monitoring System, 

exceeds the limits as 

indicated by the ASI 

outside the power 

dependent control limits 

specified in the COLR. 

A.1 Restore LHR to within 

limits. 

1 hour 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 2. 6 hours 
LHR (Analog) 

3.2.1 

CEOG STS 3.2.1-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Either the Excore Detector Monitoring System or the Incore Detector Monitoring System shall be 

used to determine LHR. 

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY 

SR 3.2.1.1 -------------------------------NOTE------------------------------ 

 Only required to be met when the Excore Detector 

Monitoring System is being used to determine LHR. 

 --------------------------------------------------------------------- 

 Verify ASI alarm setpoints are within the limits 

specified in the COLR. 

31 days 

SR 3.2.1.2 ------------------------------NOTES----------------------------- 

 1. Only required to be met when the Incore 

Detector Monitoring System is being used to 

determine LHR. 

 2. Not required to be performed below 20% RTP. 

 --------------------------------------------------------------------- 

 Verify incore detector local power density alarms 

satisfy the requirements of the core power 

distribution map, which shall be updated at least 

once per 31 days of accumulated operation in 

MODE 1. 

31 days 

SR 3.2.1.3 ------------------------------NOTES----------------------------- 

 1. Only required to be met when the Incore 

Detector Monitoring System is being used to 

determine LHR. 

 2. Not required to be performed below 20% RTP. 

 --------------------------------------------------------------------- 

 Verify incore detector local power density alarm 

setpoints are less than or equal to the limits 

specified in the COLR. 

31 days 
LHR (Digital) 

3.2.1 

CEOG STS 3.2.1-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.1 Linear Heat Rate (LHR) (Digital) 

LCO 3.2.1 LHR shall not exceed the limits specified in the COLR. 

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Core Operating Limit 

Supervisory System 

(COLSS) calculated core 

power exceeds the 

COLSS calculated core 

power operating limit 

based on LHR. 

A.1 Restore LHR to within 

limits. 

1 hour 

B. LHR not within region of 

acceptable operation 

when the COLSS is out 

of service. 

B.1 Determine trend in LHR. 

AND

B.2.1 With an adverse trend, 

restore LHR to within limit. 

 OR

B.2.2 With no adverse trend, 

restore LHR to within limits. 

Once per 15 minutes 

1 hour 

4 hours 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Reduce THERMAL 

POWER to ≤ 20% RTP. 

6 hours 
LHR (Digital) 

3.2.1 

CEOG STS 3.2.1-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.1.1 -------------------------------NOTE------------------------------ 

 Only required to be met when COLSS is out of 

service. With COLSS in service, LHR is 

continuously monitored. 

 --------------------------------------------------------------------- 

 Verify LHR, as indicated on each OPERABLE local 

power density channel, is within its limit. 

2 hours 

SR 3.2.1.2 Verify the COLSS margin alarm actuates at a 

THERMAL POWER equal to or less than the core 

power operating limit based on LHR. 

31 days 
T Fxy (Analog) 

3.2.2 

CEOG STS 3.2.2-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.2 Total Planar Radial Peaking Factor ( T Fxy ) (Analog) 

LCO 3.2.2 The calculated value of T Fxy shall not exceed the limits specified in the 

COLR. 

APPLICABILITY: MODE 1. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. ------------NOTE------------ 

 Required Actions shall 

be completed if this 

Condition is entered. 

 --------------------------------- 

T Fxy not within limits. 

A.1 Reduce THERMAL 

POWER to bring the 

combination of THERMAL 

POWER and T Fxy to within 

the limits specified in the 

COLR. 

AND

 A.2 Withdraw the control 

element assemblies (CEAs) 

to or beyond the long term 

steady state insertion limits 

of LCO 3.1.6, "Regulating 

CEAs," as specified in the 

COLR. 

6 hours 

6 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 2. 6 hours 
T Fxy (Analog) 

3.2.2 

CEOG STS 3.2.2-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.2.1 -------------------------------NOTE------------------------------ 

 SR 3.2.2.2 and SR 3.2.2.3 shall be completed each 

time SR 3.2.2.1 is required. T Fxy shall be determined 

by using the incore detectors to obtain a power 

distribution map with all full length CEAs at or above 

the long term steady state insertion limit, as 

specified in the COLR. 

 --------------------------------------------------------------------- 

 Verify the value of T Fxy

Once prior to 

operation above 

70% RTP after 

each fuel loading 

AND

Each 31 days of 

accumulated 

operation in 

MODE 1 

SR 3.2.2.2 Verify the value of Fxy. In accordance 

with the 

Frequency 

requirements of 

SR 3.2.2.1 

SR 3.2.2.3 Verify the value of Tq. In accordance 

with the 

Frequency 

requirements of 

SR 3.2.2.1 
Fxy (Digital) 

3.2.2 

CEOG STS 3.2.2-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.2 Planar Radial Peaking Factors (Fxy) (Digital) 

LCO 3.2.2 The measured Planar Radial Peaking Factors ( M F ) shall be equal to or xy

less than the Planar Radial Peaking Factors ( C Fxy ). (These factors are 

used in the Core Operating Limit Supervisory System (COLSS) and in the 

Core Protection Calculators (CPCs)). 

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. M Fxy > C Fxy . A.1.1 Adjust addressable CPC 

constants to increase the 

multiplier applied to planar 

radial peaking by a factor 

≥ M Fxy / C Fxy . 

 AND

A.1.2 Maintain a margin to the 

COLSS operating limits of 

[( M Fxy / C Fxy )-1.0] x 100% 

OR

A.2 Adjust the affected C Fxy

used in the COLSS and 

CPCs to a value greater 

than or equal to the 

measured M Fxy . 

OR

A.3 Reduce THERMAL 

POWER to ≤ 20% RTP. 

6 hours 

6 hours 

6 hours 

6 hours 
Fxy (Digital) 

3.2.2 

CEOG STS 3.2.2-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.2.1 Verify measured M Fxy obtained using the Incore 

Detector System is equal to or less than the value of 

C Fxy used in the COLSS and CPCs. 

Once after each 

fuel loading with 

THERMAL 

POWER 

> 40% RTP but 

prior to operations 

above 70% RTP 

AND

31 EFPD 

thereafter 
T Fr (Analog) 

3.2.3 

CEOG STS 3.2.3-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.3 Total Integrated Radial Peaking Factor ( T Fr ) (Analog) 

LCO 3.2.3 The calculated value of T Fr shall be within the limits specified in the 

COLR. 

APPLICABILITY: MODE 1. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. ------------NOTE------------ 

 Required Actions shall 

be completed if this 

Condition is entered. 

 --------------------------------- 

T Fr not within limit. 

A.1 Reduce THERMAL 

POWER to bring the 

combination of THERMAL 

POWER and T Fr to within 

limits specified in the 

COLR. 

AND

A.2 Withdraw the control 

element assemblies (CEAs) 

to or beyond the long term 

steady state insertion limits 

of LCO 3.1.6, "Regulating 

Control Element Assembly 

(CEA) Insertion Limits," as 

specified in the COLR. 

AND

A.3 Establish a revised upper 

THERMAL POWER limit as 

specified in the COLR. 

6 hours 

6 hours 

6 hours 

B. Required Actions and 

associated Completion 

Times not met. 

B.1 Be in MODE 2. 6 hours 
T Fr (Analog) 

3.2.3 

CEOG STS 3.2.3-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.3.1 -------------------------------NOTE------------------------------ 

 SR 3.2.3.2 and SR 3.2.3.3 shall be completed each 

time SR 3.2.3.1 is required. T Fr shall be determined 

by using the incore detectors to obtain a power 

distribution map with all full length CEAs at or above 

the long term steady state insertion limit as specified 

in the COLR. 

 --------------------------------------------------------------------- 

 Verify the value of T Fr . Prior to operation 

> 70% RTP after 

each fuel loading 

AND

Each 31 days of 

accumulated 

operation in 

MODE 1 

SR 3.2.3.2 Verify the value of Fr. In accordance 

with the 

Frequency 

requirements of 

SR 3.2.3.1 

SR 3.2.3.3 Verify the value of Tq. In accordance 

with the 

Frequency 

requirements of 

SR 3.2.3.1 
Tq (Digital) 

3.2.3 

CEOG STS 3.2.3-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.3 AZIMUTHAL POWER TILT (Tq) (Digital) 

LCO 3.2.3 The measured Tq shall be less than or equal to the Tq allowance used in 

the core protection calculators (CPCs). 

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Measured Tq greater 

than the allowance used 

in the CPCs and 

≤ [0.10]. 

A.1 Restore measured Tq. 

OR

A.2 Adjust the Tq allowance in 

the CPCs to greater than or 

equal to the measured 

value. 

2 hours 

2 hours 

B. Measured Tq > [0.10]. --------------------NOTE------------------- 

All subsequent Required Actions 

must be completed if power 

reduction commences prior to 

restoring Tq to ≤ [0.10]. 

------------------------------------------------ 

B.1 Reduce THERMAL 

POWER to ≤ 50% RTP. 

AND

B.2 Reduce Linear Power Level 

- High trip setpoints to 

≤ 55% RTP. 

AND

4 hours 

16 hours 
Tq (Digital) 

3.2.3 

CEOG STS 3.2.3-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.3 Restore the measured Tq to 

less than the Tq allowance 

used in the CPCs. 

Prior to increasing 

THERMAL POWER 

-----------NOTE---------- 

Correct the cause of 

the out of limit 

condition prior to 

increasing THERMAL 

POWER. 

Subsequent power 

operation > 50% RTP 

may proceed 

provided that the 

measured Tq is 

verified ≤ [0.10] at 

least once per hour 

for 12 hours, or until 

verified at ≥ 95% RTP 

----------------------------- 

C. Required Actions and 

associated Completion 

Times not met. 

C.1 Reduce THERMAL 

POWER to ≤ 20%. 

6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.3.1 -------------------------------NOTE------------------------------ 

 Only required to be met when COLSS is out of 

service. With COLSS in service, this parameter is 

continuously monitored. 

 --------------------------------------------------------------------- 

 Calculate Tq and verify it is within the limit. 12 hours 

SR 3.2.3.2 Verify COLSS azimuthal tilt alarm is actuated at a Tq

value less than the Tq value used in the CPCs. 

31 days 
Tq (Digital) 

3.2.3 

CEOG STS 3.2.3-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.2.3.3 Independently confirm the validity of the COLSS 

calculated Tq by use of the incore detectors. 

31 EFPD 
Tq (Analog) 

 3.2.4 

CEOG STS 3.2.4-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.4 AZIMUTHAL POWER TILT (Tq) (Analog) 

LCO 3.2.4 Tq shall be ≤ [0.03]. 

APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Indicated Tq > [0.03] and 

≤ 0.10. 

A.1 Restore Tq to ≤ [0.03]. 

OR

A.2 Verify T F and xy

T Fr are 

within the limits of 

LCO 3.2.2, "Total Planar 

Radial Peaking Factor 

( T Fxy )," and LCO 3.2.3, 

"Total Integrated Radial 

Peaking Factor ( T Fr )," 

respectively. 

2 hours 

2 hours 

AND

Once per 8 hours 

thereafter 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Reduce THERMAL 

POWER to ≤ 50% RTP. 

4 hours 
Tq (Analog) 

 3.2.4 

CEOG STS 3.2.4-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. Indicated Tq > 0.10. -------------------NOTE-------------------- 

All subsequent Required Actions 

must be completed if power 

reduction commences prior to 

restoring Tq ≤ 0.10. 

------------------------------------------------ 

C.1 Verify T Fxy and T Fr are 

within the limits of 

LCO 3.2.2 and LCO 3.2.3, 

respectively. 

AND

C.2 Reduce THERMAL 

POWER to < 50% RTP. 

AND

C.3 Restore Tq to ≤ [0.03]. 

1 hour 

2 hours 

Correct the cause of 

the out of limit 

condition prior to 

increasing THERMAL 

POWER. 

Subsequent power 

operation above 

50% RTP may 

proceed provided that 

the measured Tq is 

verified ≤ [0.03] at 

least once per hour 

for 12 hours, or until 

verified at 95% RTP 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.4.1 Verify Tq is within limits. 12 hours 
DNBR (Digital) 

3.2.4 

CEOG STS 3.2.4-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.4 Departure From Nucleate Boiling Ratio (DNBR) (Digital) 

LCO 3.2.4 The DNBR shall be maintained by one of the following methods: 

 a. Maintaining Core Operating Limit Supervisory System (COLSS) 

calculated core power less than or equal to COLSS calculated core 

power operating limit based on DNBR (when COLSS is in service, 

and either one or both control element assembly calculators 

(CEACs) are OPERABLE), 

 b. Maintaining COLSS calculated core power less than or equal to 

COLSS calculated core power operating limit based on DNBR 

decreased by the allowance specified in the COLR (when COLSS is 

in service and neither CEAC is OPERABLE), 

 c. Operating within the region of acceptable operation of 

Figure 3.2.4-1 specified in the COLR using any operable core 

protection calculator (CPC) channel (when COLSS is out of service 

and either one or both CEACs are OPERABLE), or 

 d. Operating within the region of acceptable operation of 

Figure 3.2.4-2 specified in the COLR using any operable CPC 

channel (when COLSS is out of service and neither CEAC is 

OPERABLE). 

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. COLSS calculated core 

power not within limit. 

A.1 Restore the DNBR to within 

limit. 

1 hour 

B. DNBR outside the region 

of acceptable operation 

when COLSS is out of 

service. 

B.1 [ Determine trend in DNBR. 

AND

Once per 15 

minutes ] 
DNBR (Digital) 

3.2.4 

CEOG STS 3.2.4-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

 

B.2.1 With an adverse trend, 

restore DNBR to within 

limit. 

 OR

B.2.2 With no adverse trend, 

restore DNBR to within 

limit. 

1 hour 

4 hours 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Reduce THERMAL 

POWER to ≤ 20% RTP. 

6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.4.1 -------------------------------NOTE------------------------------ 

 Only required to be met when COLSS is out of 

service. With COLSS in service, this parameter is 

continuously monitored. 

 --------------------------------------------------------------------- 

 Verify DNBR, as indicated on all OPERABLE DNBR 

channels, is within the limit of Figure 3.2.4-1 or 

3.2.4-2 of the COLR, as applicable. 

2 hours 

SR 3.2.4.2 Verify COLSS margin alarm actuates at a 

THERMAL POWER level equal to or less than the 

core power operating limit based on DNBR. 

31 days 
ASI (Analog) 

3.2.5 

CEOG STS 3.2.5-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.5 AXIAL SHAPE INDEX (ASI) (Analog) 

LCO 3.2.5 The ASI shall be maintained within the limits specified in the COLR. 

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. ASI not within limits. A.1 Restore ASI to within limits. 2 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Reduce THERMAL 

POWER to ≤ 20% RTP. 

4 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.5.1 Verify ASI is within limits specified in the COLR. 12 hours 
ASI (Digital) 

3.2.5 

CEOG STS 3.2.5-1 Rev. 3.0, 03/31/04 

3.2 POWER DISTRIBUTION LIMITS 

3.2.5 AXIAL SHAPE INDEX (ASI) (Digital) 

LCO 3.2.5 ASI shall be within the limits specified in the COLR. 

APPLICABILITY: MODE 1 with THERMAL POWER > 20% RTP. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Core average ASI not 

within limits. 

A.1 Restore ASI to within limits. 2 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Reduce THERMAL 

POWER to ≤ 20% RTP. 

4 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.2.5.1 Verify ASI is within limits. 12 hours 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.1 Reactor Protective System (RPS) Instrumentation - Operating (Analog) 

LCO 3.3.1 Four RPS trip units and associated instrument and bypass removal 

channels for each Function in Table 3.3.1-1 shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.1-1. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each RPS Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one RPS trip unit or 

associated instrument 

channel inoperable 

except for Condition C 

(excore channel not 

calibrated with incore 

detectors). 

A.1 Place affected trip unit in 

bypass or trip. 

AND

A.2.1 Restore channel to 

OPERABLE status. 

 OR

A.2.2 [ Place affected trip unit in 

trip. 

1 hour 

[48] hours 

48 hours ] 

B. One or more Functions 

with two RPS trip units 

or associated instrument 

channels inoperable 

except for Condition C 

(excore channel not 

calibrated with incore 

detectors). 

B.1 Place one trip unit in 

bypass and place the other 

trip unit in trip. 

AND

B.2 Restore one trip unit to 

OPERABLE status. 

1 hour 

[48] hours 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. One or more Functions 

with one or more power 

range excore channels 

not calibrated with the 

incore detectors. 

C.1 Perform SR 3.3.1.3. 

OR

C.2 Restrict THERMAL 

POWER to ≤ 90% RTP. 

24 hours 

24 hours 

D. One or more Functions 

with one automatic 

bypass removal channel 

inoperable. 

D.1 Disable bypass channel. 

OR

D.2.1 Place affected trip units in 

bypass or trip. 

 AND

D.2.2.1 Restore bypass removal 

channel and affected trip 

units to OPERABLE status. 

 OR

D.2.2.2 [ Place affected trip units in 

trip. 

1 hour 

1 hour 

[48] hours 

48 hours ] 

E. One or more Functions 

with two automatic 

bypass removal 

channels inoperable. 

E.1 Disable bypass channels. 

OR

1 hour 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

 

E.2.1 [ Place one affected trip unit 

in bypass and place the 

other in trip for each 

affected trip Function. 

 AND

E.2.2 Restore one automatic 

bypass removal channel 

and the associated trip unit 

to OPERABLE status for 

each affected trip Function. 

1 hour 

[48] hours ] 

F. Required Action and 

associated Completion 

Time not met for Axial 

Power Distribution and 

Loss of Load Trip 

Functions. 

F.1 Reduce THERMAL 

POWER to < 15% RTP. 

6 hours 

G. Required Action and 

associated Completion 

Time not met except for 

Axial Power Distribution 

or Loss of Load Trip 

Functions. 

G.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Refer to Table 3.3.1-1 to determine which SR shall be performed for each RPS Function. 

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY 

SR 3.3.1.1 Perform a CHANNEL CHECK of each RPS 

instrument channel except Loss of Load. 

12 hours 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.1.2 ------------------------------NOTES----------------------------- 

 1. Not required to be performed until 12 hours 

after THERMAL POWER is ≥ [20]% RTP. 

 2. The daily calibration may be suspended during 

PHYSICS TESTS, provided the calibration is 

performed upon reaching each major test power 

plateau and prior to proceeding to the next 

major test power plateau. 

 --------------------------------------------------------------------- 

 Perform calibration (heat balance only) and adjust 

the excore power range and ∆T power channels to 

agree with calorimetric calculation if the absolute 

difference is ≥ [1.5]%. 

24 hours 

SR 3.3.1.3 -------------------------------NOTE------------------------------ 

 Not required to be performed until 12 hours after 

THERMAL POWER is ≥ [20]% RTP. 

 --------------------------------------------------------------------- 

 Calibrate the power range excore channels using 

the incore detectors. 

31 days 

SR 3.3.1.4 Perform a CHANNEL FUNCTIONAL TEST of each 

RPS channel except Loss of Load and Power Rate 

of Change. 

[92] days 

SR 3.3.1.5 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL CALIBRATION on excore 

power range channels. 

92 days 

SR 3.3.1.6 Perform a CHANNEL FUNCTIONAL TEST of each 

Power Rate of Change channel and each Loss of 

Load functional unit. 

Once within 

7 days prior to 

each reactor 

startup 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-5 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.1.7 Perform a CHANNEL FUNCTIONAL TEST on each 

automatic bypass removal function. 

Once within 

92 days prior to 

each reactor 

startup 

SR 3.3.1.8 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL CALIBRATION of each RPS 

instrument channel, including bypass removal 

functions. 

[18] months 

SR 3.3.1.9 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded. 

 --------------------------------------------------------------------- 

 Verify RPS RESPONSE TIME is within limits. [18] months on a 

STAGGERED 

TEST BASIS 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-6 Rev. 3.0, 03/31/04 

Table 3.3.1-1 (page 1 of 2) 

Reactor Protective System Instrumentation 

FUNCTION 

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS 

SURVEILLANCE 

REQUIREMENTS ALLOWABLE VALUE 

 1. Variable High 

Power Trip 

1, 2 SR 3.3.1.1 

SR 3.3.1.2 

SR 3.3.1.3 

SR 3.3.1.4 

SR 3.3.1.5 

SR 3.3.1.8 

SR 3.3.1.9 

≤ [10]% RTP above current 

THERMAL POWER but not 

< [30]% RTP nor > [107]% RTP

 2. Power Rate of 

Change - High(a)

1, 2 SR 3.3.1.1 

SR 3.3.1.6 

SR 3.3.1.7 

SR 3.3.1.8 

≤ [2.6] dpm 

 3. Reactor Coolant 

Flow - Low(b)

1, 2 SR 3.3.1.1 

SR 3.3.1.4 

SR 3.3.1.7 

SR 3.3.1.8 

SR 3.3.1.9 

≥ [95]% 

 4. Pressurizer 

Pressure - High 

1, 2 SR 3.3.1.1 

SR 3.3.1.4 

SR 3.3.1.8 

SR 3.3.1.9 

≤ [2400] psia 

 5. Containment 

Pressure - High 

1, 2 [SR 3.3.1.1] 

SR 3.3.1.4 

SR 3.3.1.8 

SR 3.3.1.9 

≤ [4.0] psig 

 6. Steam Generator 

Pressure - Low(c)

1, 2 SR 3.3.1.1 

SR 3.3.1.4 

SR 3.3.1.7 

SR 3.3.1.8 

SR 3.3.1.9 

≥ [685] psia 

(a) Trip may be bypassed when THERMAL POWER is < [1E-4]% RTP or > [13]% RTP. Bypass shall be 

automatically removed when THERMAL POWER is ≥ [1E-4]% RTP and ≤ [13]% RTP. 

(b) Trips may be bypassed when THERMAL POWER is < [1E-4]%. Bypass shall be automatically removed when 

THERMAL POWER is ≥ [1E-4]% RTP. During testing pursuant to LCO 3.4.17, RCS Loops - Test Exceptions, 

trips may be bypassed below 5% RTP. Bypass shall be automatically removed when THERMAL POWER is 

≥ 5% RTP. 

(c) Trip may be bypassed when steam generator pressure is < [785] psig. Bypass shall be automatically removed 

when steam generator pressure is ≥ [785] psig.
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-7 Rev. 3.0, 03/31/04 

Table 3.3.1-1 (page 2 of 2) 

Reactor Protective System Instrumentation 

FUNCTION 

APPLICABLE MODES OR 

OTHER SPECIFIED 

CONDITIONS 

SURVEILLANCE 

REQUIREMENTS ALLOWABLE VALUE 

 7a. Steam Generator A 

Level - Low 

1, 2 SR 3.3.1.1 

SR 3.3.1.4 

SR 3.3.1.8 

SR 3.3.1.9 

≥ [24.7]% 

 7b. Steam Generator B 

Level - Low 

1, 2 SR 3.3.1.1 

SR 3.3.1.4 

SR 3.3.1.8 

SR 3.3.1.9 

≥ [24.7]% 

[8. Axial Power 

Distribution - High 

1(d) (e) SR 3.3.1.1 

SR 3.3.1.2 

SR 3.3.1.3 

SR 3.3.1.4 

SR 3.3.1.5 

SR 3.3.1.7 

SR 3.3.1.8 

SR 3.3.1.9 

Figure 3.3.1-3 ] 

 9a. Thermal 

Margin/Low 

Pressure (TM/LP)(b)

1, 2 SR 3.3.1.1 

SR 3.3.1.2 

SR 3.3.1.3 

SR 3.3.1.4 

SR 3.3.1.5 

SR 3.3.1.7 

[SR 3.3.1.8] 

SR 3.3.1.9 

Figures 3.3.1-1 and 3.3.1-2 

[9b. Steam Generator 

Pressure 

Difference(b)

1, 2 SR 3.3.1.1 

SR 3.3.1.4 

SR 3.3.1.8 

SR 3.3.1.9 

≤ [135] psid ] 

 10. Loss of Load 

(turbine stop valve 

control oil pressure)

1(d) (e) SR 3.3.1.6 

SR 3.3.1.7 

SR 3.3.1.8 

≥ [800] psig 

(b) Trips may be bypassed when THERMAL POWER is < [1E-4]%. Bypass shall be automatically removed when 

THERMAL POWER is ≥ [1E-4]% RTP. During testing pursuant to LCO 3.4.17, trips may be bypassed 

below 5% RTP. Bypass shall be automatically removed when THERMAL POWER is ≥ 5% RTP. 

(d) Trip is not applicable and may be bypassed when THERMAL POWER is < [15]% RTP. Bypass shall be 

automatically removed when THERMAL POWER is ≥ [15]% RTP. 

(e) Trip is only applicable in MODE 1 ≥ [15]% RTP. 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-8 Rev. 3.0, 03/31/04 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-9 Rev. 3.0, 03/31/04 
RPS Instrumentation - Operating (Analog) 

3.3.1 

CEOG STS 3.3.1-10 Rev. 3.0, 03/31/04 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.1 Reactor Protective System (RPS) Instrumentation - Operating (Digital) 

LCO 3.3.1 Four RPS trip and bypass removal channels for each Function in 

Table 3.3.1-1 shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.1-1. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each RPS Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one automatic RPS 

trip channel inoperable. 

A.1 Place channel in bypass or 

trip. 

AND

A.2 Restore channel to 

OPERABLE status. 

1 hour 

Prior to entering 

MODE 2 following 

next MODE 5 entry 

B. One or more Functions 

with two automatic RPS 

trip channels inoperable. 

B.1 Place one channel in 

bypass and the other in trip. 

1 hour 

C. One or more Functions 

with one automatic 

bypass removal channel 

inoperable. 

C.1 Disable bypass channel. 

OR

1 hour 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C.2.1 Place affected automatic 

trip channel in bypass or 

trip. 

 AND

C.2.2 Restore bypass removal 

channel and associated 

automatic trip channel to 

OPERABLE status. 

1 hour 

Prior to entering 

MODE 2 following 

next MODE 5 entry 

D. One or more Functions 

with two automatic 

bypass removal 

channels inoperable. 

D.1 Disable bypass channels. 

OR

D.2 Place one affected 

automatic trip channel in 

bypass and place the other 

in trip. 

1 hour 

1 hour 

E. One or more core 

protection calculator 

(CPC) channels with a 

cabinet high temperature 

alarm. 

E.1 Perform CHANNEL 

FUNCTIONAL TEST on 

affected CPC. 

12 hours 

F. One or more CPC 

channels with three or 

more autorestarts during 

a 12 hour period. 

F.1 Perform CHANNEL 

FUNCTIONAL TEST on 

affected CPC. 

24 hours 

G. Required Action and 

associated Completion 

Time not met. 

G.1 Be in MODE 3. 6 hours 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Refer to Table 3.3.1-1 to determine which SR shall be performed for each RPS Function. 

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY 

SR 3.3.1.1 Perform a CHANNEL CHECK of each RPS 

instrument channel except Loss of Load. 

12 hours 

SR 3.3.1.2 -------------------------------NOTE------------------------------ 

 Not required to be performed until 12 hours after 

THERMAL POWER ≥ 70% RTP. 

 --------------------------------------------------------------------- 

 Verify total Reactor Coolant System (RCS) flow rate 

as indicated by each CPC is less than or equal to 

the RCS total flow rate. 

 If necessary, adjust the CPC addressable constant 

flow coefficients such that each CPC indicated flow 

is less than or equal to the RCS flow rate. 

12 hours 

SR 3.3.1.3 Check the CPC auto restart count. 12 hours 

SR 3.3.1.4 ------------------------------NOTES----------------------------- 

 1. Not required to be performed until 12 hours 

after THERMAL POWER ≥ 20% RTP. 

 2. The daily calibration may be suspended during 

PHYSICS TESTS, provided the calibration is 

performed upon reaching each major test power 

plateau and prior to proceeding to the next 

major test power plateau. 

 --------------------------------------------------------------------- 

 Perform calibration (heat balance only) and adjust 

the linear power level signals and the CPC 

addressable constant multipliers to make the CPC 

∆T power and CPC nuclear power calculations 

agree with the calorimetric, if the absolute difference 

is ≥ [2]%. 

24 hours 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.1.5 -------------------------------NOTE------------------------------ 

 Not required to be performed until 12 hours after 

THERMAL POWER ≥ 70% RTP. 

 --------------------------------------------------------------------- 

 Verify total RCS flow rate indicated by each CPC is 

less than or equal to the RCS flow determined by 

calorimetric calculations. 

31 days 

SR 3.3.1.6 -------------------------------NOTE------------------------------ 

 Not required to be performed until 12 hours after 

THERMAL POWER ≥ 15% RTP. 

 --------------------------------------------------------------------- 

 Verify linear power subchannel gains of the excore 

detectors are consistent with the values used to 

establish the shape annealing matrix elements in 

the CPCs. 

31 days 

SR 3.3.1.7 ------------------------------NOTES----------------------------- 

 1. The CPC CHANNEL FUNCTIONAL TEST shall 

include verification that the correct values of 

addressable constants are installed in each 

OPERABLE CPC. 

 2. Not required to be performed for logarithmic 

power level channels until 2 hours after 

reducing logarithmic power below 1E-4% and 

only if reactor trip circuit breakers (RTCBs) are 

closed. 

 --------------------------------------------------------------------- 

 Perform CHANNEL FUNCTIONAL TEST on each 

channel except Loss of Load and power range 

neutron flux. 

92 days 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-5 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.1.8 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from the CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION of the power 

range neutron flux channels. 

92 days 

SR 3.3.1.9 -------------------------------NOTE------------------------------ 

 [ Not required to be performed until 2 hours after 

THERMAL POWER ≥ 55% RTP. 

 --------------------------------------------------------------------- 

 Perform CHANNEL FUNCTIONAL TEST for Loss of 

Load Function. 

92 days ] 

SR 3.3.1.10 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION on each 

channel, including bypass removal functions. 

[18] months 

SR 3.3.1.11 Perform a CHANNEL FUNCTIONAL TEST on each 

CPC channel. 

[18] months 

SR 3.3.1.12 Using the incore detectors, verify the shape 

annealing matrix elements to be used by the CPCs. 

Once after each 

refueling prior to 

exceeding 

70% RTP 

SR 3.3.1.13 Perform a CHANNEL FUNCTIONAL TEST on each 

automatic bypass removal function. 

Once within 

92 days prior to 

each reactor 

startup 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-6 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.1.14 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded. 

 --------------------------------------------------------------------- 

 Verify RPS RESPONSE TIME is within limits. [18] months on a 

STAGGERED 

TEST BASIS 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-7 Rev. 3.0, 03/31/04 

Table 3.3.1-1 (page 1 of 3) 

Reactor Protective System Instrumentation 

FUNCTION 

APPLICABLE MODES 

OR OTHER SPECIFIED 

CONDITIONS 

SURVEILLANCE 

REQUIREMENTS ALLOWABLE VALUE 

 1. Linear Power Level - High 1,2 SR 3.3.1.1 

SR 3.3.1.4 

SR 3.3.1.6 

SR 3.3.1.7 

SR 3.3.1.8 

 SR 3.3.1.10 

 SR 3.3.1.14 

≤ [111.3]% RTP 

 2. Logarithmic Power Level - High(a) 2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.13 

 SR 3.3.1.14 

≤ [.96]% 

 3. Pressurizer Pressure - High 1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.14 

≤ [2389] psia 

 4. Pressurizer Pressure - Low(c) 1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.13 

 SR 3.3.1.14 

≥ [1763] psig 

 5. Containment Pressure - High 1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.14 

≤ [3.14] psig 

 6. Steam Generator #1 Pressure - 

Low 

1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.14 

≥ [711] psia 

(a) Bypass may be enabled when logarithmic power is > [1E-4]% and shall be capable of automatic removal 

whenever logarithmic power is > [1E-4]%. Bypass shall be removed prior to reducing logarithmic power to a 

value ≤ [1E-4]%. Trip may be manually bypassed during physics testing pursuant to LCO 3.4.17, "RCS Loops 

- Test Exceptions." 

(b) Not used. 

(c) The setpoint may be decreased to a minimum value of [300] psia, as pressurizer pressure is reduced, 

provided the margin between pressurizer pressure and the setpoint is maintained ≤ [400] psi. Bypass may be 

enabled when pressurizer pressure is < [500] psia and shall be capable of automatic removal whenever 

pressurizer pressure is < [500] psia. Bypass shall be removed prior to raising pressurizer pressure to a value 

≥ [500] psia. The setpoint shall be automatically increased to the normal setpoint as pressurizer pressure is 

increased. 
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-8 Rev. 3.0, 03/31/04 

Table 3.3.1-1 (page 2 of 3) 

Reactor Protective System Instrumentation 

FUNCTION 

APPLICABLE MODES 

OR OTHER SPECIFIED 

CONDITIONS 

SURVEILLANCE 

REQUIREMENTS ALLOWABLE VALUE 

 7. Steam Generator #2 Pressure - 

Low 

1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.14 

≥ [711] psia 

 8. Steam Generator #1 Level - Low 1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.14 

≥ [24.23]% 

 9. Steam Generator #2 Level - Low 1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.14 

≥ [24.23]% 

[ 10. Reactor Coolant Flow, Steam 

Generator #1 - Low(d)

1,2 SR 3.3.1.1 

SR 3.3.1.7 

 SR 3.3.1.10 

 [SR 3.3.1.13] 

 SR 3.3.1.14 

Ramp: ≤ [0.231] 

psid/sec. 

Floor: ≥ [12.1] psid 

Step: ≤ [7.231] psid ] 

[ 11. Reactor Coolant Flow, Steam 

Generator #2 - Low(d)

1,2 SR 3.3.1.1 

SR 3.3.1.7 

SR 3.3.1.10 

[SR 3.3.1.13] 

SR 3.3.1.14 

Ramp: ≤ [0.231] 

psid/sec. 

Floor: ≥ [12.1] psid 

Step: ≤ [7.231] psid ] 

[ 12. Loss of Load (turbine stop valve 

control oil pressure)(e)

1 SR 3.3.1.9 

 SR 3.3.1.10 

 [SR 3.3.1.13] 

≥ [100] psig ] 

(d) Bypass may be enabled when logarithmic power is < [1E-04]% and shall be capable of automatic removal 

whenever logarithmic power is < [1E-4]%. Bypass shall be removed prior to raising logarithmic power to a 

value ≥ [1E-4]%. During testing pursuant to LCO 3.4.17, bypass may be enabled when THERMAL POWER is 

< [5]% RTP and shall be capable of automatic removal whenever THERMAL POWER is < [5]% RTP. Bypass 

shall be removed above 5% RTP. 

(e) Bypass may be enabled when THERMAL POWER is < [55]% RTP and shall be capable of automatic removal 

whenever THERMAL POWER is < [55]% RTP. Bypass shall be removed prior to raising THERMAL POWER 

to a value ≥ [55]% RTP.
RPS Instrumentation - Operating (Digital) 

3.3.1 

CEOG STS 3.3.1-9 Rev. 3.0, 03/31/04 

Table 3.3.1-1 (page 3 of 3) 

Reactor Protective System Instrumentation 

FUNCTION 

APPLICABLE MODES 

OR OTHER SPECIFIED 

CONDITIONS 

SURVEILLANCE 

REQUIREMENTS ALLOWABLE VALUE 

 13. Local Power Density - High(d) 1,2 SR 3.3.1.1 

SR 3.3.1.2 

SR 3.3.1.3 

SR 3.3.1.4 

SR 3.3.1.5 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.11 

 SR 3.3.1.12 

 SR 3.3.1.13 

 SR 3.3.1.14 

≤ [21.0] kW/ft 

 14. Departure From Nucleate Boiling 

Ratio (DNBR) - Low(d)

1,2 SR 3.3.1.1 

SR 3.3.1.2 

SR 3.3.1.3 

SR 3.3.1.4 

SR 3.3.1.5 

SR 3.3.1.7 

 SR 3.3.1.10 

 SR 3.3.1.11 

 SR 3.3.1.12 

 SR 3.3.1.13 

 SR 3.3.1.14 

≥ [1.31] 

(d) Bypass may be enabled when logarithmic power is < [1E-04]% and shall be capable of automatic removal 

whenever logarithmic power is < [1E-4]%. Bypass shall be removed prior to raising logarithmic power to a 

value ≥ [1E-4]%. During testing pursuant to LCO 3.4.17, bypass may be enabled when THERMAL POWER is 

< [5]% RTP and shall be capable of automatic removal whenever THERMAL POWER is < [5]% RTP. Bypass 

shall be removed above 5% RTP. 
RPS Instrumentation - Shutdown (Analog) 

3.3.2 

CEOG STS 3.3.2-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.2 Reactor Protective System (RPS) Instrumentation - Shutdown (Analog) 

LCO 3.3.2 Four Power Rate of Change - High RPS trip units and associated 

instrument and bypass removal channels shall be OPERABLE. 

APPLICABILITY: MODES 3, 4, and 5, with any reactor trip circuit breakers (RTCBs) closed 

and any control element assembly capable of being withdrawn. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Trip may be bypassed when THERMAL POWER is < [1E-4]% RTP. 

Bypass shall be automatically removed when THERMAL POWER is 

≥ [1E-4]% RTP. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One Power Rate of 

Change - High trip unit 

or associated instrument 

channel inoperable. 

A.1 Place affected trip unit in 

bypass or trip. 

AND

A.2.1 Restore channel to 

OPERABLE status. 

 OR

A.2.2 [ Place affected trip unit in 

trip. 

1 hour 

[48] hours 

48 hours ] 
RPS Instrumentation - Shutdown (Analog) 

3.3.2 

CEOG STS 3.3.2-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. Two Power Rate of 

Change - High trip units 

or associated instrument 

channel inoperable. 

B.1 Place one trip unit in 

bypass and place the other 

trip unit in trip. 

AND

B.2 [ Restore one trip unit to 

OPERABLE status. 

1 hour 

48 hours ] 

C. One automatic bypass 

removal channel 

inoperable. 

C.1 Disable bypass channel. 

OR

C.2.1 Place affected trip unit in 

bypass or trip. 

 AND

C.2.2.1 Restore bypass removal 

channel and affected trip 

unit to OPERABLE status. 

 OR

C.2.2.2 [ Place affected trip units in 

trip. 

1 hour 

1 hour 

[48] hours 

48 hours ] 

D. Two automatic bypass 

removal channels 

inoperable. 

D.1 Disable bypass channels. 

OR

D.2.1 Place one affected trip unit 

in bypass and place the 

other in trip. 

 AND

1 hour 

1 hour 
RPS Instrumentation - Shutdown (Analog) 

3.3.2 

CEOG STS 3.3.2-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

 

D.2.2 Restore one bypass 

channel and the associated 

trip unit to OPERABLE 

status. 

[48] hours 

E. Required Action and 

associated Completion 

Time not met. 

E.1 Open all RTCBs. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.2.1 Perform a CHANNEL CHECK of each wide range 

power channel. 

12 hours 

SR 3.3.2.2 Perform a CHANNEL FUNCTIONAL TEST on the 

Power Rate of Change trip function. 

92 days 

SR 3.3.2.3 Perform a CHANNEL FUNCTIONAL TEST on each 

automatic bypass removal function. 

92 days 

SR 3.3.2.4 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL CALIBRATION, including 

bypass removal functions with Allowable Value 

≤ [2.6] dpm. 

[18] months 
RPS Instrumentation - Shutdown (Digital) 

3.3.2 

CEOG STS 3.3.2-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.2 Reactor Protective System (RPS) Instrumentation - Shutdown (Digital) 

LCO 3.3.2 Four RPS Logarithmic Power Level - High trip channels and associated 

instrument and bypass removal channels shall be OPERABLE. 

APPLICABILITY: MODES 3, 4, and 5, with any reactor trip circuit breakers (RTCBs) closed 

and any control element assembly capable of being withdrawn. 

 --------------------------------------------NOTE--------------------------------------------- 

 Bypass may be enabled when logarithmic power is > [1E-4]% and shall 

be capable of automatic removal whenever logarithmic power is 

> [1E-4]%. Bypass shall be removed prior to reducing logarithmic power 

to a value ≤ [1E-4]%. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One RPS logarithmic 

power level trip channel 

inoperable. 

A.1 Place channel in bypass or 

trip. 

AND

A.2 Restore channel to 

OPERABLE status. 

1 hour 

Prior to entering 

MODE 2 following 

next MODE 5 entry 

B. Two RPS logarithmic 

power level trip channels 

inoperable. 

B.1 Place one channel in 

bypass and place the other 

in trip. 

1 hour 
RPS Instrumentation - Shutdown (Digital) 

3.3.2 

CEOG STS 3.3.2-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION 

C. One automatic bypass 

removal channel 

inoperable. 

C.1 Disable bypass channel. 

OR

C.2.1 Place affected automatic 

trip channel in bypass or 

trip. 

 AND

C.2.2 Restore bypass removal 

channel and associated 

automatic trip channel to 

OPERABLE status. 

1 hour 

1 hour 

Prior to entering 

MODE 2 following 

next MODE 5 entry 

D. Two automatic bypass 

removal channels 

inoperable. 

D.1 Disable bypass channels. 

OR

D.2 Place one affected 

automatic trip channel in 

bypass and place the other 

in trip. 

1 hour 

1 hour 

E. Required Action and 

associated Completion 

Time not met. 

E.1 Open all RTCBs. 1 hour 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.2.1 Perform a CHANNEL CHECK of each logarithmic 

power channel. 

12 hours 
RPS Instrumentation - Shutdown (Digital) 

3.3.2 

CEOG STS 3.3.2-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.2.2 Perform a CHANNEL FUNCTIONAL TEST on each 

logarithmic power channel. 

92 days 

SR 3.3.2.3 Perform a CHANNEL FUNCTIONAL TEST on each 

automatic bypass removal function. 

Once within 

92 days prior to 

each reactor 

startup 

SR 3.3.2.4 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL CALIBRATION on each 

logarithmic power channel, including bypass 

removal function with Allowable Value for trip 

channels ≤ [.93]%. 

[18] months 

SR 3.3.2.5 Verify RPS RESPONSE TIME is within limits. [18] months on a 

STAGGERED 

TEST BASIS 
RPS Logic and Trip Initiation (Analog) 

3.3.3 

CEOG STS 3.3.3-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.3 Reactor Protective System (RPS) Logic and Trip Initiation (Analog) 

LCO 3.3.3 Six channels of RPS Matrix Logic, four channels of RPS Initiation Logic, 

[four] channels of reactor trip circuit breakers (RTCBs), and [four] 

channels of Manual Trip shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2, 

 MODES 3, 4, and 5, with any RTCBs closed and any control element 

assemblies capable of being withdrawn. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One Matrix Logic 

channel inoperable. 

 OR

 Three Matrix Logic 

channels inoperable due 

to a common power 

source failure deenergizing three matrix 

power supplies. 

A.1 Restore channel(s) to 

OPERABLE status. 

48 hours 

B. One channel of Manual 

Trip, RTCBs, or Initiation 

Logic inoperable in 

MODE 1 or 2. 

B.1 Open the affected RTCBs. 1 hour 

C. One channel of Manual 

Trip, RTCBs, or Initiation 

Logic inoperable in 

MODE 3, 4, or 5. 

C.1 Open the affected RTCBs. 48 hours 
RPS Logic and Trip Initiation (Analog) 

3.3.3 

CEOG STS 3.3.3-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. Two channels of Manual 

Trip, RTCBs, or Initiation 

Logic affecting the same 

trip leg inoperable. 

D.1 Open the affected RTCBs. Immediately 

E. Required Action and 

associated Completion 

Time of Condition A, B, 

or D not met. 

 OR

 One or more Functions 

with two or more Manual 

Trip, Matrix Logic, 

Initiation Logic, or RTCB 

channels inoperable for 

reasons other than 

Condition A or D. 

E.1 Be in MODE 3. 

AND

E.2 Open all RTCBs. 

6 hours 

6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.3.1 Perform a CHANNEL FUNCTIONAL TEST on each 

RTCB channel. 

[31] days 

SR 3.3.3.2 Perform a CHANNEL FUNCTIONAL TEST on each 

RPS Logic channel. 

[92] days 

SR 3.3.3.3 Perform a CHANNEL FUNCTIONAL TEST on each 

RPS Manual Trip channel. 

Once within 

7 days prior to 

each reactor 

startup 
RPS Logic and Trip Initiation (Analog) 

3.3.3 

CEOG STS 3.3.3-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.3.4 [ Perform a CHANNEL FUNCTIONAL TEST, 

including separate verification of the undervoltage 

and shunt trips, on each RTCB channel. 

[18] months ] 
CEACs (Digital) 

3.3.3 

CEOG STS 3.3.3-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.3 Control Element Assembly Calculators (CEACs) (Digital) 

LCO 3.3.3 Two CEACs shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One CEAC inoperable. A.1 Perform SR 3.1.4.1. 

AND

A.2 Restore CEAC to 

OPERABLE status. 

Once per 4 hours 

7 days 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

 OR

 Both CEACs inoperable. 

B.1 Verify the departure from 

nucleate boiling ratio 

requirement of LCO 3.2.4, 

"Departure from Nucleate 

Boiling Ratio (DNBR)," is 

met [and the Reactor 

Power Cutback System is 

disabled]. 

AND

4 hours 
CEACs (Digital) 

3.3.3 

CEOG STS 3.3.3-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.2 Verify all full length and part 

length control element 

assembly (CEA) groups are 

fully withdrawn and 

maintained fully withdrawn, 

except during Surveillance 

testing pursuant to 

SR 3.1.4.3 [or for control, 

when CEA group #6 may 

be inserted to a maximum 

of 127.5 inches]. 

AND

B.3 Verify the "RSPT/CEAC 

Inoperable" addressable 

constant in each core 

protection calculator (CPC) 

is set to indicate that both 

CEACs are inoperable. 

AND

B.4 Verify the Control Element 

Drive Mechanism Control 

System is placed in "OFF" 

and maintained in "OFF," 

except during CEA motion 

permitted by Required 

Action B.2. 

AND

B.5 Perform SR 3.1.4.1. 

4 hours 

4 hours 

4 hours 

Once per 4 hours 

C. Receipt of a CPC 

channel B or C cabinet 

high temperature alarm. 

C.1 Perform CHANNEL 

FUNCTIONAL TEST on 

affected CEAC(s). 

12 hours 
CEACs (Digital) 

3.3.3 

CEOG STS 3.3.3-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. One or two CEACs with 

three or more auto 

restarts during a 12 hour 

period. 

D.1 Perform CHANNEL 

FUNCTIONAL TEST on 

affected CEAC. 

24 hours 

E. Required Action and 

associated Completion 

Time of Condition B, C, 

or D not met. 

E.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.3.1 Perform a CHANNEL CHECK. 12 hours 

SR 3.3.3.2 Check the CEAC auto restart count. 12 hours 

SR 3.3.3.3 Perform a CHANNEL FUNCTIONAL TEST. 92 days 

SR 3.3.3.4 Perform a CHANNEL CALIBRATION. [18] months 

SR 3.3.3.5 Perform a CHANNEL FUNCTIONAL TEST. [18] months 

SR 3.3.3.6 Verify the isolation characteristics of each CEAC 

isolation amplifier and each optical isolator for 

CEAC to CPC data transfer. 

[18] months 
ESFAS Instrumentation (Analog) 

3.3.4 

CEOG STS 3.3.4-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.4 Engineered Safety Features Actuation System (ESFAS) Instrumentation (Analog) 

LCO 3.3.4 Four ESFAS trip units and associated instrument and bypass removal 

channels for each Function in Table 3.3.4-1 shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each ESFAS Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. [ One Containment 

Spray Actuation Signal 

(CSAS) trip unit or 

associated instrument 

inoperable. 

A.1 Place affected trip unit in 

bypass. 

1 hour ] 

B. One or more Functions 

with one ESFAS trip unit 

or associated instrument 

channel (except CSAS) 

inoperable. 

B.1 Place affected trip unit in 

bypass or trip. 

AND

B.2.1 Restore channel to 

OPERABLE status. 

 OR

B.2.2 [ Place affected trip unit in 

trip. 

1 hour 

[48] hours 

48 hours ] 
ESFAS Instrumentation (Analog) 

3.3.4 

CEOG STS 3.3.4-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. One or more Functions 

with two ESFAS trip 

units or associated 

instrument channels 

(except CSAS) 

inoperable. 

C.1 Place one trip unit in 

bypass and place the other 

trip unit in trip. 

AND

C.2 Restore one trip unit to 

OPERABLE status. 

1 hour 

[48] hours 

D. One or more Functions 

with one automatic 

bypass removal channel 

inoperable. 

D.1 Disable bypass channel. 

OR

D.2.1 Place affected trip units in 

bypass or trip. 

 AND

D.2.2.1 Restore bypass removal 

channel and affected trip 

units to OPERABLE status. 

 OR

D.2.2.2 [ Place affected trip units in 

trip. 

1 hour 

1 hour 

[48] hours 

48 hours ] 

E. One or more Functions 

with two automatic 

bypass removal 

channels inoperable. 

E.1 Disable bypass channels. 

OR

E.2.1 Place one affected trip unit 

in bypass and place the 

other in trip for each 

affected ESFAS Function. 

 AND

1 hour 

1 hour 
ESFAS Instrumentation (Analog) 

3.3.4 

CEOG STS 3.3.4-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

 

E.2.2 [ Restore one bypass 

channel and the associated 

trip unit to OPERABLE 

status for each affected trip 

Function. 

48 hours ] 

F. Required Action and 

associated Completion 

Time not met. 

F.1 Be in MODE 3. 

AND

F.2 Be in MODE 4. 

6 hours 

[12] hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.4.1 Perform a CHANNEL CHECK of each ESFAS 

instrument channel. 

12 hours 

SR 3.3.4.2 Perform a CHANNEL FUNCTIONAL TEST of each 

ESFAS instrument channel. 

[92] days 

SR 3.3.4.3 Perform a CHANNEL FUNCTIONAL TEST on each 

automatic bypass removal function. 

Once within 

92 days prior to 

each reactor 

startup 

SR 3.3.4.4 Perform a CHANNEL CALIBRATION of each 

ESFAS instrument channel, including bypass 

removal functions. 

[18] months 

SR 3.3.4.5 Verify ESF RESPONSE TIME is within limits. [18] months on a 

STAGGERED 

TEST BASIS 
ESFAS Instrumentation (Analog) 

3.3.4 

CEOG STS 3.3.4-4 Rev. 3.0, 03/31/04 

Table 3.3.4-1 (page 1 of 2) 

Engineered Safety Features Actuation System Instrumentation 

FUNCTION MODES 

SURVEILLANCE 

REQUIREMENTS 

ALLOWABLE 

VALUE 

 1. Safety Injection Actuation Signal (SIAS) 

 a. Containment Pressure - High 1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

≤ [19.0] psia 

 b. Pressurizer Pressure - Low(a) 1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.3 

SR 3.3.4.4 

SR 3.3.4.5 

≥ [1687] psia 

 2. Containment Spray Actuation Signal(b)

 a. Containment Pressure - High 1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

≤ [19.0] psia 

 3. Containment Isolation Actuation Signal 

 

 a. Containment Pressure - High 1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

≤ [19.0] psia 

 [ b. Containment Radiation - High 1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

≤ [2x Background] ] 

(a) Pressurizer Pressure - Low may be manually bypassed when pressurizer pressure is < [1800] psia. The bypass 

shall be automatically removed whenever pressurizer pressure is ≥ [1800] psia. 

[ (b) SIAS is also required as a permissive to initiate containment spray. ]
ESFAS Instrumentation (Analog) 

3.3.4 

CEOG STS 3.3.4-5 Rev. 3.0, 03/31/04 

Table 3.3.4-1 (page 2 of 2) 

Engineered Safety Features Actuation System Instrumentation 

FUNCTION MODES 

SURVEILLANCE 

REQUIREMENTS 

ALLOWABLE 

VALUE 

 4. Main Steam Isolation Signal 

 

 a. Steam Generator Pressure - Low(c) 1,2(d),3(d) SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.3 

SR 3.3.4.4 

SR 3.3.4.5 

≥ [495] psig 

 5. Recirculation Actuation Signal 

 a. Refueling Water Tank Level - Low 1,2,3 [SR 3.3.4.1] 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

[≥ 24 inches and 

≤ 30] inches above 

tank bottom 

 6. Auxiliary Feedwater Actuation Signal 

(AFAS) 

 a. Steam Generator A Level - Low 1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

≥ [45.7] % 

 b. Steam Generator B Level - Low 1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

≥ [45.7] % 

 c. Steam Generator Pressure Difference - 

High (A > B) or (B > A) 

1,2,3 SR 3.3.4.1 

SR 3.3.4.2 

SR 3.3.4.4 

SR 3.3.4.5 

≤ [48.3] psid 

(c) Steam Generator Pressure - Low may be manually bypassed when steam generator pressure is < [785] psia. 

The bypass shall be automatically removed whenever steam generator pressure is ≥ [785] psia. 

(d) Only the Main Steam Isolation Signal (MSIS) Function and the Steam Generator Pressure - Low and 

Containment Pressure - High signals are not required to be OPERABLE when all associated valves isolated by 

the MSIS Function are closed and [de-activated].
RPS Logic and Trip Initiation (Digital) 

3.3.4 

CEOG STS 3.3.4-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.4 Reactor Protective System (RPS) Logic and Trip Initiation (Digital) 

LCO 3.3.4 Six channels of RPS Matrix Logic, four channels of RPS Initiation Logic, 

[four channels of reactor trip circuit breakers (RTCBs),] and four channels 

of Manual Trip shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2, 

 MODES 3, 4, and 5, with any RTCBs closed and any control element 

assemblies capable of being withdrawn. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One Matrix Logic 

channel inoperable. 

 OR

 Three Matrix Logic 

channels inoperable due 

to a common power 

source failure deenergizing three matrix 

power supplies. 

A.1 Restore channel(s) to 

OPERABLE status. 

48 hours 

B. One channel of Manual 

Trip, RTCBs, or Initiation 

Logic inoperable in 

MODE 1 or 2. 

B.1 Open the affected RTCBs. 1 hour 

C. One channel of Manual 

Trip, RTCBs, or Initiation 

Logic inoperable in 

MODE 3, 4, or 5. 

C.1 Open the affected RTCBs. 48 hours 

D. Two channels of Manual 

Trip, RTCBs, or Initiation 

Logic affecting the same 

trip leg inoperable. 

D.1 Open the affected RTCBs. Immediately 
RPS Logic and Trip Initiation (Digital) 

3.3.4 

CEOG STS 3.3.4-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

E. Required Action and 

associated Completion 

Time of Condition A, B, 

or D not met. 

 OR

 One or more Functions 

with more than one 

Manual Trip, Matrix 

Logic, Initiation Logic, or 

RTCB channel 

inoperable for reasons 

other than Condition A 

or D. 

E.1 Be in MODE 3. 

AND

E.2 Open all RTCBs. 

6 hours 

6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.4.1 Perform a CHANNEL FUNCTIONAL TEST on each 

RTCB channel. 

[31] days 

SR 3.3.4.2 Perform a CHANNEL FUNCTIONAL TEST on each 

RPS Logic channel. 

[92] days 

SR 3.3.4.3 Perform a CHANNEL FUNCTIONAL TEST, 

including separate verification of the undervoltage 

and shunt trips, on each RTCB. 

[18] months 

SR 3.3.4.4 Perform a CHANNEL FUNCTIONAL TEST on each 

RPS Manual Trip channel. 

Once within 

7 days prior to 

each reactor 

startup 
ESFAS Logic and Manual Trip (Analog) 

3.3.5 

CEOG STS 3.3.5-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.5 Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip 

(Analog) 

LCO 3.3.5 Two ESFAS Manual Trip and two ESFAS Actuation Logic channels shall 

be OPERABLE for each ESFAS Function specified in Table 3.3.5-1. 

APPLICABILITY: According to Table 3.3.5-1. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one Auxiliary 

Feedwater Actuation 

Signal (AFAS) Manual 

Trip or Actuation Logic 

channel inoperable. 

A.1 Restore channel to 

OPERABLE status. 

48 hours 

B. Two AFAS Manual Trip 

or Actuation Logic 

channels inoperable. 

 OR

 Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4. 

6 hours 

[12] hours 

C. One or more Functions 

with one Manual Trip or 

Actuation Logic channel 

inoperable except AFAS. 

C.1 Restore channel to 

OPERABLE status. 

48 hours 
ESFAS Logic and Manual Trip (Analog) 

3.3.5 

CEOG STS 3.3.5-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. One or more Functions 

with two Manual Trip or 

Actuation Logic channel 

inoperable except AFAS. 

 OR

 Required Action and 

associated Completion 

Time of Condition C not 

met. 

D.1 Be in MODE 3. 

AND

D.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.5.1 ------------------------------NOTES----------------------------- 

 1. Testing of Actuation Logic shall include 

verification of the proper operation of each 

initiation relay. 

 2. Relays associated with plant equipment that 

cannot be operated during plant operation are 

only required to be tested during each MODE 5 

entry exceeding 24 hours unless tested during 

the previous 6 months. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on each 

ESFAS logic channel. 

[92] days 

SR 3.3.5.2 Perform a CHANNEL FUNCTIONAL TEST on each 

ESFAS Manual Trip channel. 

[18] months 
ESFAS Logic and Manual Trip (Analog) 

3.3.5 

CEOG STS 3.3.5-3 Rev. 3.0, 03/31/04 

Table 3.3.5-1 (page 1 of 1) 

Engineered Safety Features Actuation System Actuation Logic and 

Manual Channel Applicability 

FUNCTION APPLICABLE MODES 

 1. Safety Injection Actuation Signal 1,2,3,[4] 

 2. Containment Spray Actuation Signal 1,2,3,[4] 

 3. Containment Isolation Actuation Signal 1,2,3,4 

 4. Main Steam Isolation Signal 1,2,3,4 

 5. Recirculation Actuation Signal 1,2,3,4 

 6. Auxiliary Feedwater Actuation Signal 1,2,3 
ESFAS Instrumentation (Digital) 

3.3.5 

CEOG STS 3.3.5-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.5 Engineered Safety Features Actuation System (ESFAS) Instrumentation (Digital) 

LCO 3.3.5 Four ESFAS trip and bypass removal channels for each Function in 

Table 3.3.5-1 shall be OPERABLE. 

APPLICABILITY: According to Table 3.3.5-1. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each ESFAS Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one automatic 

ESFAS trip channel 

inoperable. 

A.1 Place channel in bypass or 

trip. 

AND

A.2 Restore channel to 

OPERABLE status. 

1 hour 

Prior to entering 

MODE 2 following 

next MODE 5 entry 

B. One or more Functions 

with two automatic 

ESFAS trip channels 

inoperable. 

B.1 Place one channel in 

bypass and the other in trip. 

1 hour 

C. One or more Functions 

with one automatic 

bypass removal channel 

inoperable. 

C.1 Disable bypass channel. 

OR

1 hour 
ESFAS Instrumentation (Digital) 

3.3.5 

CEOG STS 3.3.5-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C.2.1 Place affected automatic 

trip channel in bypass or 

trip. 

 AND

C.2.2 Restore bypass removal 

channel and associated 

automatic trip channel to 

OPERABLE status. 

1 hour 

Prior to entering 

MODE 2 following 

next MODE 5 entry 

D. One or more Functions 

with two automatic 

bypass removal 

channels inoperable. 

D.1 Disable bypass channels. 

OR

D.2 Place one affected 

automatic trip channel in 

bypass and place the other 

in trip. 

1 hour 

1 hour 

E. Required Action and 

associated Completion 

Time not met. 

E.1 Be in MODE 3. 

AND

E.2 Be in MODE 4. 

6 hours 

[12] hours 
ESFAS Instrumentation (Digital) 

3.3.5 

CEOG STS 3.3.5-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.5.1 Perform a CHANNEL CHECK of each ESFAS 

channel. 

12 hours 

SR 3.3.5.2 Perform a CHANNEL FUNCTIONAL TEST of each 

ESFAS channel. 

92 days 

SR 3.3.5.3 Perform a CHANNEL CALIBRATION of each 

ESFAS channel, including bypass removal 

functions. 

[18] months 

SR 3.3.5.4 Verify ESF RESPONSE TIME is within limits. [18] months on a 

STAGGERED 

TEST BASIS 

SR 3.3.5.5 Perform a CHANNEL FUNCTIONAL TEST on each 

automatic bypass removal channel. 

Once within 

92 days prior to 

each reactor 

startup 
ESFAS Instrumentation (Digital) 

3.3.5 

CEOG STS 3.3.5-4 Rev. 3.0, 03/31/04 

Table 3.3.5-1 (page 1 of 2) 

Engineered Safety Features Actuation System Instrumentation 

FUNCTION 

APPLICABLE MODES 

OR OTHER 

SPECIFIED 

CONDITIONS ALLOWABLE VALUE 

 1. Safety Injection Actuation Signal(a)

 a. Containment Pressure - High 1,2,3 ≤ [3.14] psig 

 b. Pressurizer Pressure - Low(b) 1,2,3 ≥ [1763] psia 

 2. Containment Spray Actuation Signal 

 

 a. Containment Pressure - High High 1,2,3 ≤ [16.83] psia 

 b. Automatic SIAS 1,2,3 NA 

 3. Containment Isolation Actuation Signal 

 

 a. Containment Pressure - High 1,2,3 ≤ [3.14] psig 

 b. Pressurizer Pressure - Low(b) 1,2,3 ≥ [1763] psia 

 4. Main Steam Isolation Signal 

 

 a. Steam Generator Pressure - Low(c) 1,2(d),3(d) ≥ [711] psig 

 b. Containment Pressure - High 1,2(d),3(d) ≤ [3.14] psig 

 5. Recirculation Actuation Signal 

 

a. Refueling Water Storage Tank Level – 

Low 

1,2,3 [≥ 17.73 and ≤ 19.27]% 

(a) Automatic SIAS also initiates a Containment Cooling Actuation Signal (CCAS). 

(b) The setpoint may be decreased to a minimum value of [300] psia, as pressurizer pressure is reduced, 

provided the margin between pressurizer pressure and the setpoint is maintained ≤ [400] psia. Trips may be 

bypassed when pressurizer pressure is < [400] psia. Bypass shall be automatically removed when pressurizer 

pressure is ≥ [500] psia. The setpoint shall be automatically increased to the normal setpoint as pressurizer 

pressure is increased. 

(c) The setpoint may be decreased as steam pressure is reduced, provided the margin between steam pressure 

and the setpoint is maintained ≤ [200] psig. The setpoint shall be automatically increased to the normal 

setpoint as steam pressure is increased. 

(d) The Main Steam Isolation Signal (MSIS) Function (Steam Generator Pressure - Low and Containment 

Pressure - High signals) is not required to be OPERABLE when all associated valves isolated by the MSIS 

Function are closed and [de-activated]. 
ESFAS Instrumentation (Digital) 

3.3.5 

CEOG STS 3.3.5-5 Rev. 3.0, 03/31/04 

Table 3.3.5-1 (page 2 of 2) 

Engineered Safety Features Actuation System Instrumentation 

FUNCTION 

APPLICABLE MODES 

OR OTHER SPECIFIED 

CONDITIONS ALLOWABLE VALUE 

 6. Emergency Feedwater Actuation Signal SG #1 (EFAS-1) 

 a. Steam Generator Level - Low 1,2,3 ≥ [24.23]% 

 b. SG Pressure Difference - High 1,2,3 ≤ [66.25] psid 

 [ c. Steam Generator Pressure - Low 1,2,3 ≥ [711] psig ] 

 7. Emergency Feedwater Actuation Signal SG #2 (EFAS-2) 

 a. Steam Generator Level - Low 1,2,3 ≥ [24.23]% 

 b. SG Pressure Difference - High 1,2,3 ≤ [66.25] psid 

 [ c. Steam Generator Pressure – Low 1,2,3 ≥ [711] psig ] 
DG - LOVS (Analog) 

3.3.6 

CEOG STS 3.3.6-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.6 Diesel Generator (DG) - Loss of Voltage Start (LOVS) (Analog) 

LCO 3.3.6 [Four] channels of Loss of Voltage Function and [four] channels of 

Degraded Voltage Function auto-initiation instrumentation per DG shall 

be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4, 

 When associated DG is required to be OPERABLE by LCO 3.8.2, "AC 

Sources - Shutdown." 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one channel per DG 

inoperable. 

A.1 Place channel in bypass or 

trip. 

AND

A.2.1 Restore channel to 

OPERABLE status. 

 OR

A.2.2 [ Place the channel in trip. 

1 hour 

[48] hours 

48 hours ] 

B. One or more Functions 

with two channels per 

DG inoperable. 

B.1 Enter applicable Conditions 

and Required Actions for 

the associated DG made 

inoperable by DG - LOVS 

instrumentation. 

OR

1 hour 
DG - LOVS (Analog) 

3.3.6 

CEOG STS 3.3.6-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.2.1 Place one channel in 

bypass and the other 

channel in trip. 

 AND

B.2.2 Restore one channel to 

OPERABLE status. 

1 hour 

[48] hours 

C. One or more Functions 

with more than two 

channels inoperable. 

C.1 Restore all but two 

channels to OPERABLE 

status. 

1 hour 

D. Required Action and 

associated Completion 

Time not met. 

D.1 Enter applicable Conditions 

and Required Actions for 

the associated DG made 

inoperable by DG - LOVS 

instrumentation. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.6.1 [ Perform CHANNEL CHECK. 12 hours ] 

SR 3.3.6.2 Perform CHANNEL FUNCTIONAL TEST. [92] days 
DG - LOVS (Analog) 

3.3.6 

CEOG STS 3.3.6-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.6.3 Perform CHANNEL CALIBRATION with setpoint 

Allowable Values as follows: 

 a. Degraded Voltage Function ≥ [3180] V and 

≤ [3220] V 

 Time delay: ≥ [ ] seconds and ≤ [ ] seconds at 

[ ] V and 

 b. Loss of Voltage Function ≥ [3180] V and 

≤ [3220] V 

 Time delay: ≥ [ ] seconds and ≤ [ ] seconds at 

[ ] V. 

[18] months 
ESFAS Logic and Manual Trip (Digital) 

3.3.6 

CEOG STS 3.3.6-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.6 Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip 

(Digital) 

LCO 3.3.6 Six channels of ESFAS Matrix Logic, four channels of ESFAS Initiation 

Logic, two channels of Actuation Logic, and two channels of Manual Trip 

shall be OPERABLE for each Function in Table 3.3.6-1. 

APPLICABILITY: According to Table 3.3.6-1. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. ------------NOTE------------ 

 This action also applies 

when three Matrix Logic 

channels are inoperable 

due to a common power 

source failure deenergizing three matrix 

power supplies. 

 --------------------------------- 

 One or more Functions 

with one Matrix Logic 

channel inoperable. 

A.1 Restore channel to 

OPERABLE status. 

48 hours 

B. One or more Functions 

with one Manual Trip or 

Initiation Logic channel 

inoperable. 

B.1 Restore channel to 

OPERABLE status. 

48 hours 
ESFAS Logic and Manual Trip (Digital) 

3.3.6 

CEOG STS 3.3.6-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. One or more Functions 

with two Initiation Logic 

channels affecting the 

same trip leg inoperable. 

C.1 Open at least one contact 

in the affected trip leg of 

both ESFAS Actuation 

Logics. 

AND

C.2 Restore channels to 

OPERABLE status. 

Immediately 

48 hours 

D. One or more Functions 

with one Actuation Logic 

channel inoperable. 

D.1 ---------------NOTE-------------- 

 One channel of Actuation 

Logic may be bypassed for 

up to 1 hour for 

Surveillances, provided the 

other channel is 

OPERABLE. 

 ------------------------------------- 

 Restore inoperable channel 

to OPERABLE status. 

48 hours 

E. Two Actuation Logic 

channels inoperable. 

 OR

 Required Action and 

associated Completion 

Time of Conditions, for 

Containment Spray 

Actuation Signal, Main 

Steam Isolation Signal, 

or Emergency 

Feedwater Actuation 

Signal not met. 

E.1 Be in MODE 3. 

AND

E.2 Be in MODE 4. 

6 hours 

[12] hours 
ESFAS Logic and Manual Trip (Digital) 

3.3.6 

CEOG STS 3.3.6-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

F. Two Actuation Logic 

channels inoperable. 

 OR

 Required Action and 

associated Completion 

Time of Conditions, for 

Safety Injection 

Actuation Signal, 

Containment Isolation 

Actuation Signal, 

Recirculation Actuation 

Signal, or Containment 

Cooling Actuation Signal 

not met. 

F.1 Be in MODE 3. 

AND

F.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.6.1 -------------------------------NOTE------------------------------ 

 Testing of Actuation Logic shall include the 

verification of the proper operation of each initiation 

relay. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on each 

ESFAS logic channel. 

[92] days 
ESFAS Logic and Manual Trip (Digital) 

3.3.6 

CEOG STS 3.3.6-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.6.2 -------------------------------NOTE------------------------------ 

 Relays exempt from testing during operation shall 

be tested during each MODE 5 entry exceeding 

24 hours unless tested during the previous 

6 months. 

 --------------------------------------------------------------------- 

 Perform a subgroup relay test of each Actuation 

Logic channel, which includes the de-energization of 

each subgroup relay and verification of the 

OPERABILITY of each subgroup relay. 

[184] days 

SR 3.3.6.3 Perform a CHANNEL FUNCTIONAL TEST on each 

ESFAS Manual Trip channel. 

[18] months 
ESFAS Logic and Manual Trip (Digital) 

3.3.6 

CEOG STS 3.3.6-5 Rev. 3.0, 03/31/04 

Table 3.3.6-1 (page 1 of 2) 

Engineered Safety Features Actuation System Logic and Manual Trip Applicability 

FUNCTION APPLICABLE MODES 

 1. Safety Injection Actuation Signal 

 a. Matrix Logic 1,2,3 

 b. Initiation Logic 1,2,3,4 

 c. Actuation Logic 1,2,3,4 

 d. Manual Trip 1,2,3,4 

 2. Containment Isolation Actuation Signal 

 a. Matrix Logic 1,2,3 

 b. Initiation Logic 1,2,3,4 

 c. Actuation Logic 1,2,3,4 

 d. Manual Trip 1,2,3,4 

 3. Containment Cooling Actuation Signal(a)

 a. Initiation Logic 1,2,3,4 

 b. Actuation Logic 1,2,3,4 

 c. Manual Trip 1,2,3,4 

 4. Recirculation Actuation Signal 

 a. Matrix Logic 1,2,3 

 b. Initiation Logic 1,2,3,4 

 c. Actuation Logic 1,2,3,4 

 d. Manual Trip 1,2,3,4 

 5. Containment Spray Actuation Signal(b)

 a. Matrix Logic 1,2,3 

 b. Initiation Logic 1,2,3 

c. Actuation Logic 1,2,3 

(a) Automatic SIAS also initiates CCAS. 

(b) Automatic SIAS also required for automatic CSAS initiation. 
ESFAS Logic and Manual Trip (Digital) 

3.3.6 

CEOG STS 3.3.6-6 Rev. 3.0, 03/31/04 

Table 3.3.6-1 (page 2 of 2) 

Engineered Safety Features Actuation System Logic and Manual Trip Applicability 

FUNCTION APPLICABLE MODES 

 5. Containment Spray Actuation Signal(b) (continued) 

 d. Manual Trip 1,2,3 

 6. Main Steam Isolation Signal 

 a. Matrix Logic 1,2,3 

 b. Initiation Logic 1,2,3 

 c. Actuation Logic 1,2,3 

 d. Manual Trip 1,2,3 

 7. Emergency Feedwater Actuation Signal SG #1 (EFAS-1) 

 a. Matrix Logic 1,2,3 

 b. Initiation Logic 1,2,3 

 c. Actuation Logic 1,2,3 

 d. Manual Trip 1,2,3 

 8. Emergency Feedwater Actuation Signal SG #2 (EFAS-2) 

 a. Matrix Logic 1,2,3 

 b. Initiation Logic 1,2,3 

 c. Actuation Logic 1,2,3 

 d. Manual Trip 1,2,3 

(b) Automatic SIAS also required for automatic CSAS initiation.
CPIS (Analog) 

3.3.7 

CEOG STS 3.3.7-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.7 Containment Purge Isolation Signal (CPIS) (Analog) 

LCO 3.3.7 [Four] CPIS containment radiation monitor channels and one CPIS 

automatic Actuation Logic and one Manual Trip train shall be 

OPERABLE. 

APPLICABILITY: During movement of [recently] irradiated fuel assemblies within 

containment. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One radiation monitor 

channel inoperable. 

A.1 Place the affected channel 

in trip. 

OR

A.2 Suspend movement of 

[recently] irradiated fuel 

assemblies within 

containment. 

4 hours 

Immediately 

B. One required Manual 

Trip or automatic 

Actuation Logic train 

inoperable. 

 OR

 More than one radiation 

monitor channel 

inoperable. 

 OR

 Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Place and maintain 

containment purge and 

exhaust valves in closed 

position. 

OR

B.2 Enter applicable Conditions 

and Required Actions for 

affected valves of 

LCO 3.9.3, "Containment 

Penetrations," made 

inoperable by isolation 

instrumentation. 

Immediately 

Immediately 
CPIS (Analog) 

3.3.7 

CEOG STS 3.3.7-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.7.1 Perform a CHANNEL CHECK on each containment 

radiation monitor channel. 

12 hours 

SR 3.3.7.2 Perform a CHANNEL FUNCTIONAL TEST on each 

containment radiation monitor channel. 

 Verify CPIS high radiation setpoint is less than or 

equal to the Allowable Value of [220 mR/hr]. 

[92] days 

SR 3.3.7.3 -------------------------------NOTE------------------------------ 

 Testing of Actuation Logic shall include verification 

of the proper operation of each initiation relay. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on each 

CPIS Actuation Logic channel. 

[31] days 

SR 3.3.7.4 Perform a CHANNEL CALIBRATION on each 

containment radiation monitor channel. 

[18] months 

SR 3.3.7.5 Perform a CHANNEL FUNCTIONAL TEST on each 

CPIS Manual Trip channel. 

[18] months 

SR 3.3.7.6 Verify CPIS response time of each containment 

radiation channel is within limits. 

[18] months on a 

STAGGERED 

TEST BASIS 
DG - LOVS (Digital) 

3.3.7 

CEOG STS 3.3.7-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.7 Diesel Generator (DG) - Loss of Voltage Start (LOVS) (Digital) 

LCO 3.3.7 [Four] channels of Loss of Voltage Function and [four] channels of 

Degraded Voltage Function auto-initiation instrumentation per DG shall 

be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4, 

 When associated DG is required to be OPERABLE by LCO 3.8.2, 

"AC Sources - Shutdown." 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one channel per DG 

inoperable. 

A.1 Place channel in bypass or 

trip 

AND

A.2 Restore channel to 

OPERABLE status. 

1 hour 

Prior to entering 

MODE 2 following 

next MODE 5 entry 

B. One or more Functions 

with two channels per 

DG inoperable. 

B.1 Enter applicable Conditions 

and Required Actions for 

the associated DG made 

inoperable by DG - LOVS 

instrumentation. 

OR

1 hour 
DG - LOVS (Digital) 

3.3.7 

CEOG STS 3.3.7-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.2 Place one channel in 

bypass and the other 

channel in trip. 

1 hour 

C. One or more Functions 

with more than two 

channels inoperable. 

C.1 Restore all but two 

channels to OPERABLE 

status. 

1 hour 

D. Required Action and 

associated Completion 

Time not met. 

D.1 Enter applicable Conditions 

and Required Actions for 

the associated DG made 

inoperable by DG - LOVS 

instrumentation. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.7.1 [ Perform CHANNEL CHECK. 12 hours ] 

SR 3.3.7.2 Perform CHANNEL FUNCTIONAL TEST. [92] days 
DG - LOVS (Digital) 

3.3.7 

CEOG STS 3.3.7-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.7.3 Perform CHANNEL CALIBRATION with setpoint 

Allowable Values as follows: 

 a. Degraded Voltage Function ≥ [3180] V and 

≤ [3220] V 

 Time delay: ≥ [ ] seconds and ≤ [ ] seconds at 

[ ] V and 

 b. Loss of Voltage Function ≥ [3180] V and 

≤ [3220] V 

 Time delay: ≥ [ ] seconds and ≤ [ ] seconds at 

[ ] V. 

[18] months 
CRIS (Analog) 

3.3.8 

CEOG STS 3.3.8-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.8 Control Room Isolation Signal (CRIS) (Analog) 

LCO 3.3.8 One CRIS channel shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6], 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. CRIS Manual Trip, 

Actuation Logic, or [one 

or more required 

channels of 

particulate/iodine or 

gaseous] radiation 

monitors inoperable in 

MODE 1, 2, 3, or 4. 

A.1 --------------NOTE-------------- 

 Place Control Room 

Emergency Air Cleanup 

System (CREACS) in toxic 

gas protection mode if 

automatic transfer to toxic 

gas protection mode 

inoperable. 

 ------------------------------------- 

 Place one CREACS train in 

emergency radiation 

protection mode. 

1 hour 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 
CRIS (Analog) 

3.3.8 

CEOG STS 3.3.8-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. CRIS Manual Trip, 

Actuation Logic, or [one 

or more required 

channels of 

particulate/iodine or 

gaseous] radiation 

monitors inoperable [in 

MODE 5 or 6], during 

movement of [recently] 

irradiated fuel 

assemblies. 

C.1 --------------NOTE-------------- 

 Place CREACS in toxic gas 

protection mode if 

automatic transfer to toxic 

gas protection mode 

inoperable. 

 ------------------------------------- 

 Place one CREACS train in 

emergency radiation 

protection mode. 

OR

C.2.1 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

 AND

C.2.2 --------------NOTE-------------- 

 Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM. 

 ------------------------------------- 

 Suspend positive reactivity 

additions. 

Immediately 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.8.1 Perform a CHANNEL CHECK on the required 

control room radiation monitor channel. 

12 hours 
CRIS (Analog) 

3.3.8 

CEOG STS 3.3.8-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.8.2 Perform a CHANNEL FUNCTIONAL TEST on the 

required CRIS radiation monitor channel. 

 Verify CRIS high radiation setpoint is less than or 

equal to the Allowable Value of [6E4] cpm above 

normal background. 

[92] days 

SR 3.3.8.3 ------------------------------NOTES----------------------------- 

 1. Surveillance of Actuation Logic shall include 

verification of the proper operation of each 

initiation relay. 

 2. Relays associated with plant equipment that 

cannot be operated during plant operation are 

only required to be tested during each MODE 5 

entry exceeding 24 hours unless tested within 

the previous 6 months. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on the 

required CRIS Actuation Logic channel. 

[31] days 

SR 3.3.8.4 Perform a CHANNEL CALIBRATION on the 

required CRIS radiation monitor channel. 

[18] months 

SR 3.3.8.5 Perform a CHANNEL FUNCTIONAL TEST on the 

required CRIS Manual Trip channel. 

[18] months 

SR 3.3.8.6 [ Verify response time of required CRIS channel is 

within limits. 

[18] months ] 
CPIS (Digital) 

3.3.8 

CEOG STS 3.3.8-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.8 Containment Purge Isolation Signal (CPIS) (Digital) 

LCO 3.3.8 One CPIS channel shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4, 

 During movement of [recently] irradiated fuel assemblies within 

containment. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Only required when the penetration is not isolated by at least one closed 

and de-activated automatic valve, closed manual valve, or blind flange. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. CPIS Manual Trip, 

Actuation Logic, or one 

or more required 

channels of radiation 

monitors inoperable in 

MODES 1, 2, 3, and 4. 

A.1 Enter applicable Conditions 

and Required Actions for 

affected valves of 

LCO 3.6.3, "Containment 

Isolation Valves," made 

inoperable by CPIS 

instrumentation. 

Immediately 

B. Required Action and 

associated Completion 

Time not met in 

MODE 1, 2, 3, or 4. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 
CPIS (Digital) 

3.3.8 

CEOG STS 3.3.8-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. CPIS Manual Trip, 

Actuation Logic, or one 

or more required 

channels of radiation 

monitors inoperable 

during movement of 

[recently] irradiated fuel 

assemblies within 

containment. 

C.1 Place and maintain 

containment purge and 

exhaust valves in closed 

position. 

OR

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies in containment. 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.8.1 Perform a CHANNEL CHECK on required 

containment area and gaseous radiation monitor 

channel. 

12 hours 

SR 3.3.8.2 Perform a CHANNEL CHECK on required 

containment particulate and iodine radiation monitor 

channel. 

7 days 

SR 3.3.8.3 -------------------------------NOTE------------------------------ 

 Only required to be met in MODES 1, 2, 3, and 4. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on each 

required containment radiation monitor channel. 

Verify setpoint [Allowable Value] is in accordance 

with the following: 

 Containment Gaseous 

 Monitor: ≤ [2X background] 

 Containment Particulate 

 Monitor: ≤ [2X background] 

 Containment Area Gamma 

 Monitor: ≤ [325 mR/hr] 

92 days 
CPIS (Digital) 

3.3.8 

CEOG STS 3.3.8-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.8.4 -------------------------------NOTE------------------------------ 

 Only required to be met during CORE 

ALTERATIONS or during movement of irradiated 

fuel assemblies within containment. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on 

required containment radiation monitor channel. 

Verify setpoint [Allowable Value] is in accordance 

with the following: 

 Containment Gaseous 

 Monitor: ≤ [2X background] 

 Containment Particulate 

 Monitor: ≤ [2X background] 

 Containment Iodine 

 Monitor: ≤ [2X background] 

 Containment Area Gamma 

 Monitor: ≤ [2X background] 

92 days 

SR 3.3.8.5 -------------------------------NOTE------------------------------ 

 Surveillance of Actuation Logic shall include the 

actuation of each initiation relay and verification of 

the proper operation of each initiation relay. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on 

required CPIS Actuation Logic channel. 

[18] months 

SR 3.3.8.6 Perform a CHANNEL CALIBRATION on required 

containment radiation monitor channel. 

[18] months 

SR 3.3.8.7 Verify that response time of required CPIS channel 

is within limits. 

[18] months 

SR 3.3.8.8 Perform CHANNEL FUNCTIONAL TEST on 

required CPIS Manual Trip channel. 

[18] months 
CVCS Isolation Signal (Analog) 

3.3.9 

CEOG STS 3.3.9-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.9 Chemical and Volume Control System (CVCS) Isolation Signal (Analog) 

LCO 3.3.9 Four channels of West Penetration Room/Letdown Heat Exchanger 

Room pressure sensing and two Actuation Logic channels shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One Actuation Logic 

channel inoperable. 

A.1 Restore the channel to 

OPERABLE status. 

48 hours 

B. One CVCS isolation 

instrument channel 

inoperable. 

B.1 Place the channel in 

bypass or trip. 

AND

B.2.1 Restore the channel to 

OPERABLE status. 

 OR

B.2.2 Place the channel in trip. 

1 hour 

48 hours 

48 hours 

C. Two CVCS isolation 

instrument channels 

inoperable. 

C.1 Place one channel in 

bypass and place the other 

channel in trip. 

AND

C.2 Restore one channel to 

OPERABLE status. 

1 hour 

48 hours 
CVCS Isolation Signal (Analog) 

3.3.9 

CEOG STS 3.3.9-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. Two Actuation Logic 

channels inoperable. 

 OR

 Required Action and 

associated Completion 

Time not met. 

D.1 Be in MODE 3. 

AND

D.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.9.1 Perform a CHANNEL CHECK. 12 hours 

SR 3.3.9.2 ------------------------------NOTES----------------------------- 

 1. Testing of Actuation Logic shall include the 

verification of the proper operation of each 

initiation relay. 

 2. Relays associated with plant equipment that 

cannot be operated during plant operation are 

only required to be tested during each MODE 5 

entry exceeding 24 hours unless tested within 

the previous 6 months. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on each 

CVCS isolation channel with setpoints in 

accordance with the following Allowable Values: 

 West Penetration Room 

 Pressure - High ≤ .5 psig 

 Letdown Heat Exchanger 

 Room Pressure - High ≤ .5 psig 

31 days 
CVCS Isolation Signal (Analog) 

3.3.9 

CEOG STS 3.3.9-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.9.3 Perform a CHANNEL CALIBRATION on each 

CVCS isolation pressure indicating channel. 

18 months 
CRIS (Digital) 

3.3.9 

CEOG STS 3.3.9-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.9 Control Room Isolation Signal (CRIS) (Digital) 

LCO 3.3.9 One CRIS channel shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6], 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. CRIS Manual Trip, 

Actuation Logic, or [one 

or more required 

channels of 

particulate/iodine or 

gaseous] radiation 

monitors inoperable in 

MODE 1, 2, 3, or 4. 

A.1 ---------------NOTE-------------- 

 Place Control Room 

Emergency Air Cleanup 

System (CREACS) in toxic 

gas protection mode if 

automatic transfer to toxic 

gas protection mode 

inoperable. 

 ------------------------------------- 

 Place one CREACS train in 

emergency radiation 

protection mode. 

1 hour 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 
CRIS (Digital) 

3.3.9 

CEOG STS 3.3.9-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. CRIS Manual Trip, 

Actuation Logic, or 

required 

particulate/iodine or 

gaseous radiation 

monitors inoperable [in 

MODE 5 or 6], or during 

movement of [recently] 

irradiated fuel 

assemblies. 

C.1 ---------------NOTE-------------- 

 Place CREACS in toxic gas 

protection mode if 

automatic transfer to toxic 

gas protection mode 

inoperable. 

 ------------------------------------- 

 Place one CREACS train in 

emergency radiation 

protection mode. 

OR

C.2.1 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

 AND

C.2.2 ---------------NOTE-------------- 

 Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM. 

 ------------------------------------- 

 Suspend positive reactivity 

additions. 

Immediately 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.9.1 Perform a CHANNEL CHECK on the required 

control room radiation monitor channel. 

12 hours 
CRIS (Digital) 

3.3.9 

CEOG STS 3.3.9-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.9.2 Perform a CHANNEL FUNCTIONAL TEST on 

required CRIS radiation monitor channel. 

 Verify CRIS high radiation setpoint [Allowable Value] 

is ≤ [6E4] cpm above normal background. 

[92] days 

SR 3.3.9.3 ------------------------------NOTES----------------------------- 

 1. Surveillance of Actuation Logic shall include the 

verification of the proper operation of each 

initiation relay. 

 2. Relays associated with plant equipment that 

cannot be operated during plant operation are 

required to be tested during each MODE 5 entry 

exceeding 24 hours unless tested within the 

previous 6 months. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on 

required CRIS Actuation Logic channel. 

[18] months 

SR 3.3.9.4 Perform a CHANNEL CALIBRATION on required 

CRIS radiation monitor channel. 

[18] months 

SR 3.3.9.5 Perform a CHANNEL FUNCTIONAL TEST on 

required CRIS Manual Trip channel. 

[18] months 

SR 3.3.9.6 [ Verify that response time of required CRIS channel 

is within limits. 

[18] months ] 
SBFAS (Analog) 

3.3.10 

CEOG STS 3.3.10-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.10 Shield Building Filtration Actuation Signal (SBFAS) (Analog) 

LCO 3.3.10 Two channels of SBFAS automatic and two channels of Manual Trip shall 

be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One Manual Trip or 

Actuation Logic channel 

inoperable. 

A.1 Restore the channel to 

OPERABLE status. 

48 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.10.1 Perform a CHANNEL FUNCTIONAL TEST on each 

SBFAS automatic actuation channel. 

[92] days 

SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST on each 

SBFAS Manual Trip channel. 

[18] months 
FHIS (Digital) 

3.3.10 

CEOG STS 3.3.10-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.10 Fuel Handling Isolation Signal (FHIS) (Digital) 

LCO 3.3.10 One FHIS channel shall be OPERABLE. 

APPLICABILITY: [MODES 1, 2, 3, and 4,] 

 During movement of [recently] irradiated fuel in the fuel building. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. [ Actuation Logic, 

Manual Trip, or [one or 

more required channels 

of particulate/iodine and 

gaseous] radiation 

monitors inoperable in 

MODE 1, 2, 3, or 4. 

A.1 Place one OPERABLE Fuel 

Building Air Cleanup 

System (FBACS) train in 

operation. 

1 hour ] 

B. [ Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours ] 

C. Actuation Logic, Manual 

Trip, or [one or more 

required channels of 

particulate/iodine and 

gaseous] radiation 

monitors inoperable 

during movement of 

[recently] irradiated fuel 

assemblies. 

C.1 Place one OPERABLE 

FBACS train in operation. 

OR

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building. 

Immediately 

Immediately 
FHIS (Digital) 

3.3.10 

CEOG STS 3.3.10-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.10.1 Perform a CHANNEL CHECK on required FHIS 

radiation monitor channel. 

12 hours 

SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST on 

required FHIS radiation monitor channel. Verify 

radiation monitor setpoint [Allowable Values]: 

 [ Airborne Particulate/ Iodine: ≤ [6E4] cpm 

 above background ]

Airborne Gaseous: ≤ [6E4] cpm 

 above background 

92 days 

SR 3.3.10.3 -------------------------------NOTE------------------------------ 

 Testing of Actuation Logic shall include the 

actuation of each initiation relay and verification of 

the proper operation of each ignition relay. 

 --------------------------------------------------------------------- 

 Perform a CHANNEL FUNCTIONAL TEST on 

required FHIS Actuation Logic channel. 

[18] months 

SR 3.3.10.4 Perform a CHANNEL FUNCTIONAL TEST on 

required FHIS Manual Trip logic. 

[18] months 

SR 3.3.10.5 Perform a CHANNEL CALIBRATION on required 

FHIS radiation monitor channel. 

[18] months 

SR 3.3.10.6 [ Verify response time of required FHIS channel is 

within limits. 

[18] months ] 
PAM Instrumentation (Analog) 

3.3.11 

CEOG STS 3.3.11-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.11 Post Accident Monitoring (PAM) Instrumentation (Analog) 

LCO 3.3.11 The PAM instrumentation for each Function in Table 3.3.11-1 shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

-----------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one required 

channel inoperable. 

A.1 Restore required channel to 

OPERABLE status. 

30 days 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Initiate action in accordance 

with Specification 5.6.7. 

Immediately 

C. One or more Functions 

with two required 

channels inoperable. 

C.1 Restore one channel to 

OPERABLE status. 

7 days 

D. Required Action and 

associated Completion 

Time of Condition C not 

met. 

D.1 Enter the Condition 

referenced in 

Table 3.3.11-1 for the 

channel. 

Immediately 
PAM Instrumentation (Analog) 

3.3.11 

CEOG STS 3.3.11-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

E. As required by Required 

Action D.1 and 

referenced in 

Table 3.3.11-1. 

E.1 Be in MODE 3. 

AND

E.2 Be in MODE 4. 

6 hours 

12 hours 

F. [ As required by 

Required Action D.1 and 

referenced in 

Table 3.3.11-1. 

F.1 Initiate action in accordance 

with Specification 5.6.7. 

Immediately ] 

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

These SRs apply to each PAM instrumentation Function in Table 3.3.11-1. 

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY 

SR 3.3.11.1 Perform CHANNEL CHECK for each required 

instrumentation channel that is normally energized. 

31 days 

SR 3.3.11.2 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION. [18] months 
PAM Instrumentation (Analog) 

3.3.11 

CEOG STS 3.3.11-3 Rev. 3.0, 03/31/04 

Table 3.3.11-1 (page 1 of 1) 

Post Accident Monitoring Instrumentation 

FUNCTION REQUIRED CHANNELS 

CONDITIONS 

REFERENCED FROM 

REQUIRED 

ACTION D.1 

 1. [Logarithmic] Neutron Flux 2 E 

 2. Reactor Coolant System Hot Leg Temperature 2 per loop E 

 3. Reactor Coolant System Cold Leg Temperature 2 per loop E 

 4. Reactor Coolant System Pressure (wide range) 2 E 

 5. Reactor Vessel Water Level 2 [F] 

 6. Containment Sump Water Level (wide range) 2 E 

 7. Containment Pressure (wide range) 2 E 

 8. Penetration Flow Path Containment Isolation 

Valve Position 

2 per penetration flow 

path(a)(b)

E 

 9. Containment Area Radiation (high range) 2 [F] 

 10. Pressurize Level 2 E 

 11. Steam Generator Water Level (wide range) 2 per steam generator E 

 12. Condensate Storage Tank Level 2 E 

 13. Core Exit Temperature - Quadrant [1] 2(c) E 

 14. Core Exit Temperature - Quadrant [2] 2(c) E 

 15. Core Exit Temperature - Quadrant [3] 2(c) E 

 16. Core Exit Temperature - Quadrant [4] 2(c) E 

 17. Auxiliary Feedwater Flow 2 E 

(a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated 

automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured. 

(b) Only one position indication channel is required for penetration flow paths with only one installed control room 

indication channel. 

(c) A channel consists of two or more core exit thermocouples. 

-------------------------------------------------------------------REVIEWER'S NOTE------------------------------------------------------------- 

Table 3.3.11-1 shall be amended for each unit as necessary to list: 

1. All Regulatory Guide 1.97, Type A instruments and 

2. All Regulatory Guide 1.97, Category I, non-Type A instruments specified in the unit's Regulatory Guide 1.97, 

Safety Evaluation Report. 

------------------------------------------------------------------------------------------------------------------------------------------------------------
PAM Instrumentation (Digital) 

3.3.11 

CEOG STS 3.3.11-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.11 Post Accident Monitoring (PAM) Instrumentation (Digital) 

LCO 3.3.11 The PAM instrumentation for each Function in Table 3.3.11-1 shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more Functions 

with one required 

channel inoperable. 

A.1 Restore required channel to 

OPERABLE status. 

30 days 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Initiate action in accordance 

with Specification 5.6.7. 

Immediately 

C. One or more Functions 

with two required 

channels inoperable. 

C.1 Restore one channel to 

OPERABLE status. 

7 days 

D. Required Action and 

associated Completion 

Time of Condition C not 

met. 

D.1 Enter the Condition 

referenced in 

Table 3.3.11-1 for the 

channel. 

Immediately 
PAM Instrumentation (Digital) 

3.3.11 

CEOG STS 3.3.11-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

E. As required by Required 

Action D.1 and 

referenced in 

Table 3.3.11-1. 

E.1 Be in MODE 3. 

AND

E.2 Be in MODE 4. 

6 hours 

12 hours 

F. [ As required by 

Required Action D.1 and 

referenced in 

Table 3.3.11-1. 

F.1 Initiate action in accordance 

with Specification 5.6.7. 

Immediately ] 

SURVEILLANCE REQUIREMENTS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

These SRs apply to each PAM instrumentation Function in Table 3.3.11-1. 

-------------------------------------------------------------------------------------------------------------------------------

SURVEILLANCE FREQUENCY 

SR 3.3.11.1 Perform CHANNEL CHECK for each required 

instrumentation channel that is normally energized. 

31 days 

SR 3.3.11.2 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from the CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION. [18] months 
PAM Instrumentation (Digital) 

3.3.11 

CEOG STS 3.3.11-3 Rev. 3.0, 03/31/04 

Table 3.3.11-1 (page 1 of 1) 

Post Accident Monitoring Instrumentation 

FUNCTION REQUIRED CHANNELS 

CONDITIONS 

REFERENCED FROM 

REQUIRED ACTION D.1 

 1. [Wide Range] Neutron Flux 2 E 

 2. Reactor Coolant System Hot Leg Temperature 2 per loop E 

 3. Reactor Coolant System Cold Leg Temperature 2 per loop E 

 4. Reactor Coolant System Pressure (wide range) 2 E 

 5. Reactor Vessel Water Level 2 [F] 

 6. Containment Sump Water Level (wide range) 2 E 

 7. Containment Pressure (wide range) 2 E 

 8. Penetration Flow Path Containment Isolation Valve 

Position 

2 per penetration flow 

path(a)(b)

E 

 9. Containment Area Radiation (high range) 2 [F] 

 10. Pressurizer Level 2 E 

 11. Steam Generator Water Level (wide range) 2 per steam generator E 

 12. Condensate Storage Tank Level 2 E 

 13. Core Exit Temperature - Quadrant [1] 2(c) E 

 14. Core Exit Temperature - Quadrant [2] 2(c) E 

 15. Core Exit Temperature - Quadrant [3] 2(c) E 

 16. Core Exit Temperature - Quadrant [4] 2(c) E 

 17. Emergency Feedwater Flow 2 E 

(a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve 

secured. 

(b) Only one position indication channel is required for penetration flow paths with only one installed control room 

indication channel. 

(c) A channel consists of two or more core exit thermocouples. 

-----------------------------------------------------------------REVIEWER'S NOTE--------------------------------------------------------------- 

Table 3.3.11-1 shall be amended for each unit as necessary to list: 

1. All Regulatory Guide 1.97, Type A instruments and 

2. All Regulatory Guide 1.97, Category I, non-Type A instruments specified in the unit's Regulatory Guide 1.97, 

Safety Evaluation Report. 

------------------------------------------------------------------------------------------------------------------------------------------------------------------------------- 
Remote Shutdown System (Analog) 

3.3.12 

CEOG STS 3.3.12-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.12 Remote Shutdown System (Analog) 

LCO 3.3.12 The Remote Shutdown System Functions shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

-----------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more required 

Functions inoperable. 

A.1 Restore required Functions 

to OPERABLE status. 

30 days 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4. 

6 hours 

[12] hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.12.1 [ Perform CHANNEL CHECK for each required 

instrumentation channel that is normally energized. 

31 days ] 

SR 3.3.12.2 Verify each required control circuit and transfer 

switch is capable of performing the intended 

function. 

[18] months 
Remote Shutdown System (Analog) 

3.3.12 

CEOG STS 3.3.12-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.12.3 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from the CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION for each 

required instrumentation channel. 

[18] months 

SR 3.3.12.4 [ Perform CHANNEL FUNCTIONAL TEST of the 

reactor trip circuit breaker open/closed indication. 

18 months ] 
Remote Shutdown System (Digital) 

3.3.12 

CEOG STS 3.3.12-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.12 Remote Shutdown System (Digital) 

LCO 3.3.12 The Remote Shutdown System Functions shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

-----------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each Function. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more required 

Functions inoperable. 

A.1 Restore required Functions 

to OPERABLE status. 

30 days 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4. 

6 hours 

[12] hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.12.1 [ Perform CHANNEL CHECK for each required 

instrumentation channel that is normally energized. 

31 days ] 

SR 3.3.12.2 Verify each required control circuit and transfer 

switch is capable of performing the intended 

function. 

[18] months 
Remote Shutdown System (Digital) 

3.3.12 

CEOG STS 3.3.12-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.3.12.3 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from the CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION for each 

required instrumentation channel. 

[18] months 

SR 3.3.12.4 [ Perform CHANNEL FUNCTIONAL TEST of the 

reactor trip circuit breaker open/closed indication. 

18 months ] 
[Logarithmic] Power Monitoring Channels (Analog) 

3.3.13 

CEOG STS 3.3.13-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.13 [Logarithmic] Power Monitoring Channels (Analog) 

LCO 3.3.13 Two channels of [logarithmic] power level monitoring instrumentation shall 

be OPERABLE. 

APPLICABILITY: MODES 3, 4, and 5, with the reactor trip circuit breakers open or Control 

Element Assembly (CEA) Drive System not capable of CEA 

withdrawal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more required 

channel(s) inoperable. 

A.1 ---------------NOTE-------------- 

 Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM. 

 ------------------------------------- 

 Suspend all operations 

involving positive reactivity 

additions. 

AND

A.2 Perform SDM verification in 

accordance with 

SR 3.1.1.1. 

Immediately 

4 hours 

AND

Once per 12 hours 

thereafter 
[Logarithmic] Power Monitoring Channels (Analog) 

3.3.13 

CEOG STS 3.3.13-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.13.1 Perform CHANNEL CHECK. 12 hours 

SR 3.3.13.2 Perform CHANNEL FUNCTIONAL TEST. [92] days 

SR 3.3.13.3 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION. [18] months 
 [Logarithmic] Power Monitoring Channels (Digital) 

3.3.13 

CEOG STS 3.3.13-1 Rev. 3.0, 03/31/04 

3.3 INSTRUMENTATION 

3.3.13 [Logarithmic] Power Monitoring Channels (Digital) 

LCO 3.3.13 Two channels of [logarithmic] power level monitoring instrumentation shall 

be OPERABLE. 

APPLICABILITY: MODES 3, 4, and 5, with the reactor trip circuit breakers open or Control 

Element Assembly (CEA) Drive System not capable of CEA 

withdrawal. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more required 

channels inoperable. 

A.1 ---------------NOTE-------------- 

 Limited plant cooldown or 

boron dilution is allowed 

provided the change is 

accounted for in the 

calculated SDM. 

 ------------------------------------- 

 Suspend all operations 

involving positive reactivity 

additions. 

AND

A.2 Perform SDM verification in 

accordance with 

SR 3.1.1.1. 

Immediately 

4 hours 

AND

Once per 12 hours 

thereafter 
 [Logarithmic] Power Monitoring Channels (Digital) 

3.3.13 

CEOG STS 3.3.13-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.3.13.1 Perform CHANNEL CHECK. 12 hours 

SR 3.3.13.2 Perform CHANNEL FUNCTIONAL TEST. [92] days 

SR 3.3.13.3 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from 

CHANNEL CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION. [18] months 
RCS Pressure, Temperature, and Flow [DNB] Limits 

3.4.1 

CEOG STS 3.4.1-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.1 RCS Pressure, Temperature, and Flow [Departure from Nucleate Boiling (DNB)] 

Limits 

LCO 3.4.1 RCS DNB parameters for pressurizer pressure, cold leg temperature, and 

RCS total flow rate shall be within the limits specified below: 

 a. Pressurizer pressure ≥ [2025] psia and ≤ [2275] psia, 

 b. RCS cold leg temperature (Tc) ≥ [535]°F and ≤ [558]°F for 

< [70]% RTP or ≥ [544]°F and ≤ [588]°F for ≥ [70]% RTP, and 

 c. RCS total flow rate ≥ [148 E6] lb/hour. 

APPLICABILITY: MODE 1. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Pressurizer pressure limit does not apply during: 

 a. THERMAL POWER ramp > 5% RTP per minute or 

 b. THERMAL POWER step > 10% RTP. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Pressurizer pressure or 

RCS flow rate not within 

limits. 

A.1 Restore parameter(s) to 

within limit. 

2 hours 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 2. 6 hours 
RCS Pressure, Temperature, and Flow [DNB] Limits 

3.4.1 

CEOG STS 3.4.1-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. RCS cold leg 

temperature not within 

limits. 

C.1 Restore cold leg 

temperature to within limits. 

2 hours 

D. Required Action and 

associated Completion 

Time of Condition C not 

met. 

D.1 Reduce THERMAL 

POWER to ≤ [30]% RTP. 

6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.1.1 Verify pressurizer pressure ≥ [2025] psia and 

≤ [2275] psia. 

12 hours 

SR 3.4.1.2 Verify RCS cold leg temperature ≥ [535]°F and 

≤ [558]°F for < [70]% RTP or ≥ [544]°F and 

≤ [558]°F for ≥ [70]% RTP. 

12 hours 

SR 3.4.1.3 -------------------------------NOTE------------------------------ 

 Only required to be met in MODE 1. 

 --------------------------------------------------------------------- 

 Verify RCS total flow rate ≥ [148 E6] lb/hour. 12 hours 

SR 3.4.1.4 -------------------------------NOTE------------------------------ 

 Not required to be performed until [24] hours after 

≥ [90]% RTP. 

 --------------------------------------------------------------------- 

 Verify by precision heat balance that RCS total flow 

rate within limits specified in the COLR. 

[18] months 
RCS Minimum Temperature for Criticality 

3.4.2 

CEOG STS 3.4.2-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.2 RCS Minimum Temperature for Criticality 

LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be ≥ [520]°F. 

APPLICABILITY: MODE 1 with Tavg in one or more RCS loops < [535]°F, 

 MODE 2 with Tavg in one or more RCS loops < [535]°F and Keff ≥ 1.0. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Tavg in one or more RCS 

loops not within limit. 

A.1 Be in MODE 2 with Keff

< 1.0. 

30 minutes 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.2.1 Verify RCS Tavg in each loop ≥ [520]°F. 12 hours 
RCS P/T Limits 

3.4.3 

CEOG STS 3.4.3-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.3 RCS Pressure and Temperature (P/T) Limits 

LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates 

shall be maintained within the limits specified in the PTLR. 

APPLICABILITY: At all times. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. ------------NOTE------------ 

 Required Action A.2 

shall be completed 

whenever this Condition 

is entered. 

 --------------------------------- 

 Requirements of 

LCO not met in 

MODE 1, 2, 3, or 4. 

A.1 Restore parameter(s) to 

within limits. 

AND

A.2 Determine RCS is 

acceptable for continued 

operation. 

30 minutes 

72 hours 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5 with 

RCS pressure < [500] psig. 

6 hours 

36 hours 

C. ------------NOTE------------ 

 Required Action C.2 

shall be completed 

whenever this Condition 

is entered. 

 --------------------------------- 

 Requirements of 

LCO not met any time in 

other than MODE 1, 2, 

3, or 4. 

C.1 Initiate action to restore 

parameter(s) to within 

limits. 

AND

C.2 Determine RCS is 

acceptable for continued 

operation. 

Immediately 

Prior to entering 

MODE 4 
RCS P/T Limits 

3.4.3 

CEOG STS 3.4.3-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.3.1 -------------------------------NOTE------------------------------ 

 Only required to be performed during RCS heatup 

and cooldown operations and RCS inservice leak 

and hydrostatic testing. 

 --------------------------------------------------------------------- 

 Verify RCS pressure, RCS temperature, and RCS 

heatup and cooldown rates within limits specified in 

the PTLR. 

30 minutes 
RCS Loops - MODES 1 and 2 

3.4.4 

CEOG STS 3.4.4-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.4 RCS Loops - MODES 1 and 2 

LCO 3.4.4 Two RCS loops shall be OPERABLE and in operation. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Requirements of 

LCO not met. 

A.1 Be in MODE 3. 6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.4.1 Verify each RCS loop is in operation. 12 hours 
RCS Loops - MODE 3 

3.4.5 

CEOG STS 3.4.5-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.5 RCS Loops - MODE 3 

LCO 3.4.5 [Two] RCS loops shall be OPERABLE and one RCS loop shall be in 

operation. 

 ---------------------------------------------NOTE-------------------------------------------- 

 All reactor coolant pumps may be removed from operation for ≤ 1 hour 

per 8 hour period, provided: 

 a. No operations are permitted that would cause introduction of coolant 

into the RCS with boron concentration less than required to meet 

the SDM of LCO 3.1.1 and 

 b. Core outlet temperature is maintained at least 10°F below saturation 

temperature. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 3. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One RCS loop 

inoperable. 

A.1 Restore RCS loop to 

OPERABLE status. 

72 hours 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 4. 12 hours 

C. Two RCS loops 

inoperable. 

 OR

 Required RCS loop not 

in operation. 

C.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1. 

AND

Immediately 
RCS Loops - MODE 3 

3.4.5 

CEOG STS 3.4.5-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C.2 Initiate action to restore 

one RCS loop to 

OPERABLE status and 

operation. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.5.1 Verify one RCS loop is in operation. 12 hours 

SR 3.4.5.2 Verify secondary side water level in each steam 

generator ≥ [25]%. 

12 hours 

SR 3.4.5.3 -------------------------------NOTE------------------------------ 

 Not required to be performed until 24 hours after a 

required pump is not in operation. 

 --------------------------------------------------------------------- 

 Verify correct breaker alignment and indicated 

power available to each required pump. 

7 days 
RCS Loops - MODE 4 

3.4.6 

CEOG STS 3.4.6-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.6 RCS Loops - MODE 4 

LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and 

shutdown cooling (SDC) trains shall be OPERABLE and one loop or train 

shall be in operation. 

 --------------------------------------------NOTES------------------------------------------- 

 1. All reactor coolant pumps (RCPs) and SDC pumps may be removed 

from operation for ≤ 1 hour per 8 hour period, provided: 

 a. No operations are permitted that would cause introduction of 

coolant into the RCS with boron concentration less than 

required to meet the SDM of LCO 3.1.1 and 

 b. Core outlet temperature is maintained at least 10°F below 

saturation temperature. 

 2. No RCP shall be started with any RCS cold leg temperature less 

than or equal to the LTOP enable temperature specified in the PTLR 

unless: 

 a. Pressurizer water level is < [60]% or 

 b. Secondary side water temperature in each steam generator 

(SG) is < [100]°F above each of the RCS cold leg 

temperatures. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One required loop 

inoperable. 

A.1 Initiate action to restore a 

second loop or train to 

OPERABLE status. 

AND

Immediately 
RCS Loops - MODE 4 

3.4.6 

CEOG STS 3.4.6-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.2 ---------------NOTE-------------- 

 Only required to be met if 

SDC train is OPERABLE. 

 ------------------------------------- 

 Be in MODE 5. 24 hours 

B. Two required loops or 

trains inoperable. 

 OR

 Required loop or train 

not in operation. 

B.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1. 

AND

B.2 Initiate action to restore one 

loop or train to OPERABLE 

status and operation. 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.6.1 Verify required RCS loop or SDC train is in 

operation. 

12 hours 

SR 3.4.6.2 Verify secondary side water level in required SG(s) 

is ≥ [25]%. 

12 hours 

SR 3.4.6.3 -------------------------------NOTE------------------------------ 

 Not required to be performed until 24 hours after a 

required pump is not in operation. 

 --------------------------------------------------------------------- 

 Verify correct breaker alignment and indicated 

power available to each required pump. 

7 days 
RCS Loops - MODE 5, Loops Filled 

3.4.7 

CEOG STS 3.4.7-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.7 RCS Loops - MODE 5, Loops Filled 

LCO 3.4.7 One shutdown cooling (SDC) train shall be OPERABLE and in operation 

and either: 

 a. One additional SDC train shall be OPERABLE or 

 b. The secondary side water level of each steam generator (SG) shall 

be ≥ [25%]. 

 --------------------------------------------NOTES------------------------------------------- 

 1. The SDC pump of the train in operation may be removed from 

operation for ≤ 1 hour per 8 hour period provided: 

 a. No operations are permitted that would cause introduction of 

coolant into the RCS with boron concentration less than 

required to meet the SDM of LCO 3.1.1 and 

 b. Core outlet temperature is maintained at ≥ 10°F below 

saturation temperature. 

 2. One SDC train may be inoperable for up to 2 hours for surveillance 

testing provided that the other SDC train is OPERABLE and in 

operation. 

 3. No reactor coolant pump (RCP) shall be started with any RCS cold 

leg temperature less than or equal to the LTOP enable temperature 

specified in the PTLR unless: 

 a. The pressurizer water level is < [60]% or 

 b. The secondary side water temperature in each SG is < [100]°F 

above each of the RCS cold leg temperatures. 

 4. All SDC trains may not be in operation during planned heatup to 

MODE 4 when at least one RCS loop is in operation. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 5 with RCS loops filled. 
RCS Loops - MODE 5, Loops Filled 

3.4.7 

CEOG STS 3.4.7-2 Rev. 3.0, 03/31/04 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One required SDC train 

inoperable. 

 AND

 One SDC train 

OPERABLE. 

A.1 Initiate action to restore a 

second SDC train to 

OPERABLE status. 

OR

A.2 Initiate action to restore 

required SGs secondary 

side water level to within 

limit. 

Immediately 

Immediately 

B. One or more required 

SGs with secondary side 

water level not within 

limit. 

 AND

 One SDC train 

OPERABLE. 

B.1 Initiate action to restore a 

second SDC train to 

OPERABLE status. 

OR

B.2 Initiate action to restore 

required SGs secondary 

side water level to within 

limit. 

Immediately 

Immediately 

C. No required SDC trains 

OPERABLE. 

 OR

 Required SDC train not 

in operation. 

C.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1. 

AND

C.2 Initiate action to restore one 

SDC train to OPERABLE 

status and operation. 

Immediately 

Immediately 
RCS Loops - MODE 5, Loops Filled 

3.4.7 

CEOG STS 3.4.7-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.7.1 Verify required SDC train is in operation. 12 hours 

SR 3.4.7.2 Verify required SG secondary side water level is 

≥ [25]%. 

12 hours 

SR 3.4.7.3 -------------------------------NOTE------------------------------ 

 Not required to be performed until 24 hours after a 

required pump is not in operation. 

 --------------------------------------------------------------------- 

 Verify correct breaker alignment and indicated 

power available to each required SDC pump. 

7 days 
RCS Loops - MODE 5, Loops Not Filled 

3.4.8 

CEOG STS 3.4.8-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.8 RCS Loops - MODE 5, Loops Not Filled 

LCO 3.4.8 Two shutdown cooling (SDC) trains shall be OPERABLE and one SDC 

train shall be in operation. 

 --------------------------------------------NOTES------------------------------------------- 

 1. All SDC pumps may be removed from operation for ≤ 15 minutes 

when switching from one train to another provided: 

 [ a. The core outlet temperature is maintained > 10°F below 

saturation temperature, ]

 b. No operations are permitted that would cause introduction of 

coolant into the RCS with boron concentration less than 

required to meet the SDM of LCO 3.1.1 and 

 c. No draining operations to further reduce the RCS water 

volume are permitted. 

 2. One SDC train may be inoperable for ≤ 2 hours for surveillance 

testing provided the other SDC train is OPERABLE and in 

operation. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 5 with RCS loops not filled. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One required SDC train 

inoperable. 

A.1 Initiate action to restore 

SDC train to OPERABLE 

status. 

Immediately 
RCS Loops - MODE 5, Loops Not Filled 

3.4.8 

CEOG STS 3.4.8-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. No required SDC train 

OPERABLE. 

 OR

 Required SDC train not 

in operation. 

B.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet SDM 

of LCO 3.1.1. 

AND

B.2 Initiate action to restore 

one SDC train to 

OPERABLE status and 

operation. 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.8.1 Verify required SDC train is in operation. 12 hours 

SR 3.4.8.2 -------------------------------NOTE------------------------------ 

 Not required to be performed until 24 hours after a 

required pump is not in operation. 

 --------------------------------------------------------------------- 

 Verify correct breaker alignment and indicated 

power available to each required SDC pump. 

7 days 
Pressurizer 

3.4.9 

CEOG STS 3.4.9-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.9 Pressurizer 

LCO 3.4.9 The pressurizer shall be OPERABLE with: 

 a. Pressurizer water level < [60]% and 

 b. [Two groups of] pressurizer heaters OPERABLE with the capacity 

[of each group] ≥ [150] kW [and capable of being powered from an 

emergency power supply]. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Pressurizer water level 

not within limit. 

A.1 Be in MODE 3 with reactor 

trip breakers open. 

AND

A.2 Be in MODE 4. 

6 hours 

[12] hours 

B. One [required] group of 

pressurizer heaters 

inoperable. 

B.1 Restore [required] group of 

pressurizer heaters to 

OPERABLE status. 

72 hours 

C. Required Action and 

associated Completion 

Time of Condition B not 

met. 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 4. 

6 hours 

[12] hours 
Pressurizer 

3.4.9 

CEOG STS 3.4.9-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.9.1 Verify pressurizer water level is < [60]%. 12 hours 

----------------------------------REVIEWER’S NOTE--------------------------------- 

The frequency for performing pressurizer heater capacity testing shall 

be either 18 months or 92 days, depending on whether or not the plant 

has dedicated safety-related heaters. For dedicated safety-related 

heaters, which do not normally operate, 92 days is applied. For nondedicated safety-related heaters, which normally operate, 18 months is 

applied. 

----------------------------------------------------------------------------------------------- 

SR 3.4.9.2 Verify capacity of each required group of pressurizer 

heaters ≥ [150] kW. 

[18] months 

SR 3.4.9.3 [ Verify required pressurizer heaters are capable of 

being powered from an emergency power supply. 

[18] months ] 
Pressurizer Safety Valves 

3.4.10 

CEOG STS 3.4.10-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.10 Pressurizer Safety Valves 

LCO 3.4.10 [Two] pressurizer safety valves shall be OPERABLE with lift settings 

≥ [2475] psia and ≤ [2525] psia. 

APPLICABILITY: MODES 1, 2, and 3, 

 MODE 4 with all RCS cold leg temperatures greater than the LTOP 

enable temperature specified in the PTLR. 

 ---------------------------------------------NOTE-------------------------------------------- 

 The lift settings are not required to be within LCO limits during MODES 3 

and 4 for the purpose of setting the pressurizer safety valves under 

ambient (hot) conditions. This exception is allowed for [36] hours 

following entry into MODE 3 provided a preliminary cold setting was made 

prior to heatup. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One pressurizer safety 

valve inoperable. 

A.1 Restore valve to 

OPERABLE status. 

15 minutes 

B. Required Action and 

associated Completion 

Time not met. 

 OR

 Two [or more] 

pressurizer safety valves 

inoperable. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4 with any 

RCS cold leg temperature 

less than or equal to the 

LTOP enable temperature 

specified in the PTLR. 

6 hours 

[24] hours 
Pressurizer Safety Valves 

3.4.10 

CEOG STS 3.4.10-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE 

in accordance with the Inservice Testing Program. 

Following testing, lift settings shall be within ± 1%. 

In accordance 

with the Inservice 

Testing Program 
Pressurizer PORVs 

3.4.11 

CEOG STS 3.4.11-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.11 Pressurizer Power Operated Relief Valves (PORVs) 

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

-----------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each PORV and each block. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more PORVs 

inoperable and capable 

of being manually 

cycled. 

A.1 Close and maintain power 

to associated block valve. 

1 hour 

B. One PORV inoperable 

and not capable of being 

manually cycled. 

B.1 Close associated block 

valve. 

AND

B.2 Remove power from 

associated block valve. 

AND

B.3 Restore PORV to 

OPERABLE status. 

1 hour 

1 hour 

72 hours 

C. One block valve 

inoperable. 

C.1 Place associated PORV in 

manual control. 

AND

1 hour 
Pressurizer PORVs 

3.4.11 

CEOG STS 3.4.11-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C.2 Restore block valve to 

OPERABLE status. 

72 hours 

D. Required Action and 

associated Completion 

Time of Condition A, B, 

or C not met. 

D.1 Be in MODE 3. 

AND

D.2 Be in MODE 4. 

6 hours 

[12] hours 

E. Two PORVs inoperable 

and not capable of being 

manually cycled. 

E.1 Close associated block 

valves. 

AND

E.2 Remove power from 

associated block valves. 

AND

E.3 Be in MODE 3. 

AND

E.4 Be in MODE 4. 

1 hour 

1 hour 

6 hours 

[12] hours 

F. Two block valves 

inoperable. 

F.1 Restore at least one block 

valve to OPERABLE status. 

2 hours 

G. Required Action and 

associated Completion 

Time of Condition F not 

met. 

G.1 Be in MODE 3. 

AND

G.2 Be in MODE 4. 

6 hours 

[12] hours 
Pressurizer PORVs 

3.4.11 

CEOG STS 3.4.11-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.11.1 ------------------------------NOTES----------------------------- 

 1. Not required to be performed with block valve 

closed in accordance with the Required Actions 

of this LCO. 

 2. Only required to be performed in MODES 1 

and 2. 

 --------------------------------------------------------------------- 

 Perform a complete cycle of each block valve. [92] days 

SR 3.4.11.2 -------------------------------NOTE------------------------------ 

 Only required to be performed in MODES 1 and 2. 

 --------------------------------------------------------------------- 

 Perform a complete cycle of each PORV. [18] months 

SR 3.4.11.3 [ Perform a complete cycle of each solenoid air 

control valve and check valve on the air 

accumulators in PORV control systems. 

[18] months ] 

SR 3.4.11.4 [ Verify PORVs and block valve(s) are capable of 

being powered from an emergency power supply. 

[18] months ] 
LTOP System 

3.4.12 

CEOG STS 3.4.12-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.12 Low Temperature Overpressure Protection (LTOP) System 

LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum of one high 

pressure safety injection (HPSI) pump and one charging pump capable of 

injecting into the RCS and the safety injection tanks (SITs) isolated, and: 

 --------------------------------------------NOTES------------------------------------------- 

 1. [Two charging pumps] may be made capable of injecting for 

≤ 1 hour for pump swap operations. 

 2. SIT may be unisolated when SIT pressure is less than the maximum 

RCS pressure for the existing RCS cold leg temperature allowed by 

the P/T limit curves provided in the PTLR. 

 -------------------------------------------------------------------------------------------------- 

 a. Two OPERABLE power operated relief valves (PORVs) with lift 

settings within the limits specified in the PTLR or 

 b. The RCS depressurized and an RCS vent of ≥ [1.3] square inches. 

APPLICABILITY: MODE 4 when any RCS cold leg temperature is less than or equal to the 

LTOP enable temperature specified in the PTLR, 

 MODE 5, 

 MODE 6 when the reactor vessel head is on. 

ACTIONS 

-----------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.4.b is not applicable to PORVs when entering MODE 4. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Two or more HPSI 

pumps capable of 

injecting into the RCS. 

A.1 Initiate action to verify a 

maximum of one HPSI 

pump capable of injecting 

into the RCS. 

Immediately 
LTOP System 

3.4.12 

CEOG STS 3.4.12-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. Two or more charging 

pumps capable of 

injecting into the RCS. 

B.1 Initiate action to verify a 

maximum of one charging 

pump capable of injecting 

into the RCS. 

Immediately 

C. A SIT not isolated when 

SIT pressure is greater 

than or equal to the 

maximum RCS pressure 

for existing cold leg 

temperature allowed in 

the PTLR. 

C.1 Isolate affected SIT. 1 hour 

D. Required Action and 

associated Completion 

Time of Condition C not 

met. 

D.1 Increase RCS cold leg 

temperature to > [175]°F. 

OR

D.2 Depressurize affected SIT 

to less than the maximum 

RCS pressure for existing 

cold leg temperature 

allowed in the PTLR. 

12 hours 

12 hours 

E. One required PORV 

inoperable in MODE 4. 

E.1 Restore required PORV to 

OPERABLE status. 

7 days 

F. One required PORV 

inoperable in MODE 5 

or 6. 

F.1 Restore required PORV to 

OPERABLE status. 

24 hours 
LTOP System 

3.4.12 

CEOG STS 3.4.12-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

G. Two required PORVs 

inoperable. 

 OR

 Required Action and 

associated Completion 

Time of Condition A, [B], 

D, E, or F not met. 

 OR

 LTOP System 

inoperable for any 

reason other than 

Condition A, [B], C, D, E, 

or F. 

G.1 Depressurize RCS and 

establish RCS vent of 

≥ [1.3] square inches. 

12 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.12.1 Verify a maximum of one HPSI pump is capable of 

injecting into the RCS. 

12 hours 

SR 3.4.12.2 Verify a maximum of one charging pump is capable 

of injecting into the RCS. 

12 hours 

SR 3.4.12.3 Verify each SIT is isolated. 12 hours 

SR 3.4.12.4 Verify required RCS vent ≥ [1.3] square inches is 

open. 

12 hours for 

unlocked open 

vent valve(s) 

AND

31 days for other 

vent path(s) 
LTOP System 

3.4.12 

CEOG STS 3.4.12-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.4.12.5 Verify PORV block valve is open for each required 

PORV. 

72 hours 

SR 3.4.12.6 -------------------------------NOTE------------------------------ 

 Not required to be performed until [12] hours after 

decreasing RCS cold leg temperature to less than or 

equal to the LTOP enable temperature specified in 

the PTLR. 

 --------------------------------------------------------------------- 

 Perform CHANNEL FUNCTIONAL TEST on each 

required PORV, excluding actuation. 

31 days 

SR 3.4.12.7 Perform CHANNEL CALIBRATION on each 

required PORV actuation channel. 

[18] months 
RCS Operational LEAKAGE 

3.4.13 

CEOG STS 3.4.13-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.13 RCS Operational LEAKAGE 

LCO 3.4.13 RCS operational LEAKAGE shall be limited to: 

 a. No pressure boundary LEAKAGE, 

 b. 1 gpm unidentified LEAKAGE, 

 c. 10 gpm identified LEAKAGE, 

 d. 1 gpm total primary to secondary LEAKAGE through all steam 

generators (SGs), and 

 e. [720] gallons per day primary to secondary LEAKAGE through any 

one SG. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. RCS LEAKAGE not 

within limits for reasons 

other than pressure 

boundary LEAKAGE. 

A.1 Reduce LEAKAGE to within 

limits. 

4 hours 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

 OR

 Pressure boundary 

LEAKAGE exists. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 
RCS Operational LEAKAGE 

3.4.13 

CEOG STS 3.4.13-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.13.1 -------------------------------NOTE------------------------------ 

 Not required to be performed until 12 hours after 

establishment of steady state operation. 

 --------------------------------------------------------------------- 

 Verify RCS operational LEAKAGE is within limits by 

performance of RCS water inventory balance. 

72 hours 

SR 3.4.13.2 Verify SG tube integrity is in accordance with the 

Steam Generator Tube Surveillance Program. 

In accordance 

with the Steam 

Generator Tube 

Surveillance 

Program 
RCS PIV Leakage 

3.4.14 

CEOG STS 3.4.14-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.14 RCS Pressure Isolation Valve (PIV) Leakage 

LCO 3.4.14 Leakage from each RCS PIV shall be within limits. 

APPLICABILITY: MODES 1, 2, and 3, 

 MODE 4, except valves in the shutdown cooling (SDC) flow path when in, 

or during the transition to or from, the SDC mode of operation. 

ACTIONS 

-----------------------------------------------------------NOTES---------------------------------------------------------- 

1. Separate Condition entry is allowed for each flow path. 

2. Enter applicable Conditions and Required Actions for systems made inoperable by an 

inoperable PIV. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more flow paths 

with leakage from one or 

more RCS PIVs not 

within limit. 

--------------------NOTE------------------- 

Each valve used to satisfy Required 

Action A.1 and Required Action A.2 

must have been verified to meet 

SR 3.4.14.1 and be on the RCS 

pressure boundary [or the high 

pressure portion of the system]. 

------------------------------------------------ 

A.1 Isolate the high pressure 

portion of the affected 

system from the low 

pressure portion by use of 

one closed manual, 

deactivated automatic, or 

check valve. 

AND

4 hours 
RCS PIV Leakage 

3.4.14 

CEOG STS 3.4.14-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.2 [ Isolate the high pressure 

portion of the affected 

system from the low 

pressure portion by use of a 

second closed manual, 

deactivated automatic, or 

check valve. 

 [or] 

 Restore RCS PIV to within 

limits. 

72 hours ] 

B. Required Action and 

associated Completion 

Time for Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

C. [ Shutdown Cooling 

(SDC) System 

autoclosure interlock 

function inoperable. 

C.1 Isolate the affected 

penetration by use of one 

closed manual or 

deactivated automatic 

valve. 

4 hours ] 
RCS PIV Leakage 

3.4.14 

CEOG STS 3.4.14-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.14.1 ------------------------------NOTES----------------------------- 

 1. Not required to be performed in MODES 3 

and 4. 

 2. Not required to be performed on the RCS PIVs 

located in the SDC flow path when in the 

shutdown cooling mode of operation. 

 3. RCS PIVs actuated during the performance of 

this Surveillance are not required to be tested 

more than once if a repetitive testing loop 

cannot be avoided. 

 --------------------------------------------------------------------- 

 Verify leakage from each RCS PIV is equivalent to 

≤ 0.5 gpm per nominal inch of valve size up to a 

maximum of 5 gpm at an RCS pressure 

≥ [2215] psia and ≤ [2255] psia. 

In accordance 

with the Inservice 

Testing Program, 

and [18] months 

AND

Prior to entering 

MODE 2 

determine the unit 

has been in 

MODE 5 for 

7 days or more, if 

leakage testing 

has not been 

performed in the 

previous 9 months 

AND

Within 24 hours 

following valve 

actuation due to 

automatic or 

manual action or 

flow through the 

valve 
RCS PIV Leakage 

3.4.14 

CEOG STS 3.4.14-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.4.14.2 -------------------------------NOTE------------------------------ 

 [ Not required to be met when the SDC System 

autoclosure interlock is disabled in accordance with 

SR 3.4.12.7. 

--------------------------------------------------------------------- 

 Verify SDC System autoclosure interlock prevents 

the valves from being opened with a simulated or 

actual RCS pressure signal ≥ [425] psig. 

[18] months ] 

SR 3.4.14.3 -------------------------------NOTE------------------------------ 

 [ Not required to be met when the SDC System 

autoclosure interlock is disabled in accordance with 

SR 3.4.12.7. 

 --------------------------------------------------------------------- 

 Verify SDC System autoclosure interlock causes the 

valves to close automatically with a simulated or 

actual RCS pressure signal ≥ [600] psig. 

[18] months ] 
RCS Leakage Detection Instrumentation 

3.4.15 

CEOG STS 3.4.15-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.15 RCS Leakage Detection Instrumentation 

LCO 3.4.15 [Two of] the following RCS leakage detection instrumentation shall be 

OPERABLE: 

 a. One containment sump monitor, 

 b. One containment atmosphere radioactivity monitor (gaseous or 

particulate), and 

 [ c. One containment air cooler condensate flow rate monitor. ] 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Required containment 

sump monitor 

inoperable. 

A.1 ---------------NOTE-------------- 

 Not required until 12 hours 

after establishment of 

steady state operation. 

 ------------------------------------- 

 Perform SR 3.4.13.1. 

AND

A.2 Restore containment sump 

monitor to OPERABLE 

status. 

Once per 24 hours 

30 days 
RCS Leakage Detection Instrumentation 

3.4.15 

CEOG STS 3.4.15-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. Required containment 

atmosphere radioactivity 

monitor inoperable. 

B.1.1 Analyze grab samples of 

the containment 

atmosphere. 

 OR

B.1.2 ---------------NOTE-------------- 

 Not required until 12 hours 

after establishment of 

steady state operation. 

 ------------------------------------- 

 Perform SR 3.4.13.1. 

AND

B.2.1 Restore required 

containment atmosphere 

radioactivity monitor to 

OPERABLE status. 

 OR

B.2.2 [ Verify containment air 

cooler condensate flow rate 

monitor is OPERABLE. 

Once per 24 hours 

Once per 24 hours 

30 days 

30 days ] 

C. [ Required containment 

air cooler condensate 

flow rate monitor 

inoperable. 

C.1 ---------------NOTE-------------- 

 Not required until 12 hours 

after establishment of 

steady state operation. 

 ------------------------------------- 

 Perform SR 3.4.15.1. 

OR

C.2 Perform SR 3.4.13.1. 

Once per 8 hours 

Once per 24 hours ]
RCS Leakage Detection Instrumentation 

3.4.15 

CEOG STS 3.4.15-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. [ Required containment 

atmosphere radioactivity 

monitor inoperable. 

 AND

 Required containment 

air cooler condensate 

flow rate monitor 

inoperable. 

D.1 Restore required 

containment atmosphere 

radioactivity monitor to 

OPERABLE status. 

OR

D.2 Restore required 

containment air cooler 

condensate flow rate 

monitor to OPERABLE 

status. 

30 days 

30 days ] 

E. Required Action and 

associated Completion 

Time not met. 

E.1 Be in MODE 3. 

AND

E.2 Be in MODE 5. 

6 hours 

36 hours 

F. All required monitors 

inoperable. 

F.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.15.1 Perform CHANNEL CHECK of the required 

containment atmosphere radioactivity monitor. 

[12] hours 

SR 3.4.15.2 Perform CHANNEL FUNCTIONAL TEST of the 

required containment atmosphere radioactivity 

monitor. 

92 days 

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 

containment sump monitor. 

[18] months 
RCS Leakage Detection Instrumentation 

3.4.15 

CEOG STS 3.4.15-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required 

containment atmosphere radioactivity monitor. 

[18] months 

SR 3.4.15.5 [ Perform CHANNEL CALIBRATION of the required 

containment air cooler condensate flow rate monitor. 

[18] months ] 
RCS Specific Activity 

3.4.16 

CEOG STS 3.4.16-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.16 RCS Specific Activity 

LCO 3.4.16 The specific activity of the reactor coolant shall be within limits. 

APPLICABILITY: MODES 1 and 2, 

 MODE 3 with RCS average temperature (Tavg) ≥ 500°F. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. DOSE 

EQUIVALENT I-131 

> 1.0 μCi/gm. 

--------------------NOTE------------------- 

LCO 3.0.4.c is not applicable. 

------------------------------------------------ 

A.1 Verify DOSE 

EQUIVALENT I-131 within 

the acceptable region of 

Figure 3.4.16-1. 

AND

A.2 Restore DOSE 

EQUIVALENT I-131 to 

within limit. 

Once per 4 hours 

48 hours 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

 OR

 DOSE 

EQUIVALENT I-131 in 

the unacceptable region 

of Figure 3.4.16-1. 

B.1 Be in MODE 3 with 

Tavg < 500°F. 

6 hours 
RCS Specific Activity 

3.4.16 

CEOG STS 3.4.16-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. Gross specific activity of 

the reactor coolant not 

within limit. 

C.1 Be in MODE 3 with 

Tavg < 500°F. 

6 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.16.1 Verify reactor coolant gross specific activity 

≤ 100/Ē μCi/gm. 

7 days 

SR 3.4.16.2 -------------------------------NOTE------------------------------ 

 Only required to be performed in MODE 1. 

 --------------------------------------------------------------------- 

 Verify reactor coolant DOSE EQUIVALENT I-131 

specific activity ≤ 1.0 μCi/gm. 

14 days 

AND

Between 2 and 

6 hours after 

THERMAL 

POWER change 

of ≥ 15% RTP 

within a 1 hour 

period 

SR 3.4.16.3 -------------------------------NOTE------------------------------ 

 Not required to be performed until 31 days after a 

minimum of 2 EFPD and 20 days of MODE 1 

operation have elapsed since the reactor was last 

subcritical for ≥ 48 hours. 

 --------------------------------------------------------------------- 

 Determine Ē from a sample taken in MODE 1 after a 

minimum of 2 EFPD and 20 days of MODE 1 

operation have elapsed since the reactor was last 

subcritical for ≥ 48 hours. 

184 days 
RCS Specific Activity 

3.4.16 

CEOG STS 3.4.16-3 Rev. 3.0, 03/31/04 
STE-RCS Loops 

3.4.17 

CEOG STS 3.4.17-1 Rev. 3.0, 03/31/04 

3.4 REACTOR COOLANT SYSTEM (RCS) 

3.4.17 Special Test Exception (STE)-RCS Loops 

LCO 3.4.17 The requirements of LCO 3.4.4, "RCS Loops - MODES 1 and 2," and the 

listed requirements of LCO 3.3.1, "Reactor Protective System (RPS) 

Instrumentation - Operating," for the [(Analog) RC flow low, thermal 

margin or low pressure, and asymmetric steam generator transient 

protective trip functions] [(Digital) high log power, high local power 

density, low departure from nucleate boiling ratio protective trip functions] 

may be suspended provided: 

 a. THERMAL POWER ≤ 5% RTP and 

 b. The reactor trip setpoints of the OPERABLE power level channels 

are set ≤ 20% RTP. 

APPLICABILITY: MODE 2, during startup and PHYSICS TESTS. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. THERMAL POWER not 

within limit. 

A.1 Open reactor trip breakers. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.4.17.1 Verify THERMAL POWER ≤ 5% RTP. 1 hour 

SR 3.4.17.2 Perform a CHANNEL FUNCTIONAL TEST on each 

logarithmic power level and linear power level 

neutron flux monitoring channel. 

12 hours prior to 

initiating startup or 

PHYSICS TESTS 
SITs 

3.5.1 

CEOG STS 3.5.1-1 Rev. 3.0, 03/31/04 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.1 Safety Injection Tanks (SITs) 

LCO 3.5.1 [Four] SITs shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2, 

 MODE 3 with pressurizer pressure ≥ [700] psia. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One SIT inoperable due 

to boron concentration 

not within limits. 

 OR

 One SIT inoperable due 

to the inability to verify 

level or pressure. 

A.1 Restore SIT to OPERABLE 

status. 

72 hours 

B. One SIT inoperable for 

reasons other than 

Condition A. 

B.1 Restore SIT to OPERABLE 

status. 

24 hours 

C. Required Action and 

associated Completion 

Time of Condition A or B 

not met. 

C.1 Be in MODE 3. 

AND

C.2 Reduce pressurizer 

pressure to < [700] psia. 

6 hours 

2 hours 

D. Two or more SITs 

inoperable. 

D.1 Enter LCO 3.0.3. Immediately 
SITs 

3.5.1 

CEOG STS 3.5.1-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.5.1.1 Verify each SIT isolation valve is fully open. 12 hours 

SR 3.5.1.2 Verify borated water volume in each SIT is 

≥ [28% narrow range (1802 cubic feet) and 

≤ 72% narrow range (1914 cubic feet)]. 

12 hours 

SR 3.5.1.3 Verify nitrogen cover pressure in each SIT is 

≥ [615] psig and ≤ [655] psig. 

12 hours 

SR 3.5.1.4 Verify boron concentration in each SIT is 

≥ [1500] ppm and ≤ [2800] ppm. 

31 days 

AND

--------NOTE-------- 

Only required to 

be performed for 

affected SIT 

------------------------ 

Once within 

6 hours after each 

solution volume 

increase of ≥ [1]% 

of tank volume 

that is not the 

result of addition 

from the refueling 

water tank 

SR 3.5.1.5 Verify power is removed from each SIT isolation 

valve operator when pressurizer pressure is 

≥ [2000] psia. 

31 days 
ECCS - Operating 

3.5.2 

CEOG STS 3.5.2-1 Rev. 3.0, 03/31/04 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.2 ECCS - Operating 

LCO 3.5.2 Two ECCS trains shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2, 

 MODE 3 with pressurizer pressure ≥ [1700] psia. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

-----REVIEWER’S NOTE----- 

The adoption of this 

Condition is contingent upon 

implementation of a program 

to perform a 

contemporaneous 

assessment of the overall 

impact on safety of 

proposed plant 

configurations prior to 

performing and during 

performance of maintenance 

activities that remove 

equipment from service. 

-------------------------------------- 

A. One LPSI subsystem 

inoperable. 

A.1 Restore subsystem to 

OPERABLE status. 

7 days 

B. One or more trains 

inoperable for reasons 

other than Condition A. 

B.1 Restore train(s) to 

OPERABLE status. 

72 hours 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Be in MODE 3. 

AND

C.2 Reduce pressurizer 

pressure to < [1700] psia. 

6 hours 

12 hours 
ECCS - Operating 

3.5.2 

CEOG STS 3.5.2-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. Less than 100% of the 

ECCS flow equivalent to 

a single OPERABLE 

train available. 

D.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.5.2.1 [ Verify the following valves are in the listed position 

with power to the valve operator removed [and key 

locked in position]. 

 Valve Number Position Function

 [ ] [ ] [ ] 

 [ ] [ ] [ ] 

 [ ] [ ] [ ] 

12 hours ] 

SR 3.5.2.2 Verify each ECCS manual, power operated, and 

automatic valve in the flow path, that is not locked, 

sealed, or otherwise secured in position, is in the 

correct position. 

31 days 

SR 3.5.2.3 [ Verify ECCS piping is full of water. 31 days ] 

SR 3.5.2.4 Verify each ECCS pump's developed head at the 

test flow point is greater than or equal to the 

required developed head. 

In accordance 

with the Inservice 

Testing Program 

SR 3.5.2.5 [ Verify each charging pump develops a flow of 

≥ [36] gpm at a discharge pressure of ≥ [2200] psig. 

In accordance 

with the Inservice 

Testing Program ]
ECCS - Operating 

3.5.2 

CEOG STS 3.5.2-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.5.2.6 Verify each ECCS automatic valve that is not 

locked, sealed, or otherwise secured in position, in 

the flow path actuates to the correct position on an 

actual or simulated actuation signal. 

[18] months 

SR 3.5.2.7 Verify each ECCS pump starts automatically on an 

actual or simulated actuation signal. 

[18] months 

SR 3.5.2.8 Verify each LPSI pump stops on an actual or 

simulated actuation signal. 

[18] months 

SR 3.5.2.9 [ Verify, for each ECCS throttle valve listed below, 

each position stop is in the correct position. 

 Valve Number

 [ ] 

 [ ] 

[18] months ] 

SR 3.5.2.10 Verify, by visual inspection, each ECCS train 

containment sump suction inlet is not restricted by 

debris and the suction inlet trash racks and screens 

show no evidence of structural distress or abnormal 

corrosion. 

[18] months 
ECCS - Shutdown 

3.5.3 

CEOG STS 3.5.3-1 Rev. 3.0, 03/31/04 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.3 ECCS - Shutdown 

LCO 3.5.3 One high pressure safety injection (HPSI) train shall be OPERABLE. 

APPLICABILITY: MODE 3 with pressurizer pressure < [1700] psia, 

 MODE 4. 

ACTIONS 

-----------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.4.b is not applicable to ECCS High Pressure Safety Injection subsystem when entering 

MODE 4. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Required HPSI train 

inoperable. 

A.1 Restore required HPSI train 

to OPERABLE status. 

1 hour 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 5. 24 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.5.3.1 The following SRs are applicable: 

 [SR 3.5.2.1] SR 3.5.2.6 

 SR 3.5.2.2 SR 3.5.2.7 

 [SR 3.5.2.3] [SR 3.5.2.9] 

 SR 3.5.2.4 SR 3.5.2.10 

In accordance 

with applicable 

SRs 
RWT 

3.5.4 

CEOG STS 3.5.4-1 Rev. 3.0, 03/31/04 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.4 Refueling Water Tank (RWT) 

LCO 3.5.4 The RWT shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. RWT boron 

concentration not within 

limits. 

 OR

 RWT borated water 

temperature not within 

limits. 

A.1 Restore RWT to 

OPERABLE status. 

8 hours 

B. RWT inoperable for 

reasons other than 

Condition A. 

B.1 Restore RWT to 

OPERABLE status 

1 hour 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 5. 

6 hours 

36 hours 
RWT 

3.5.4 

CEOG STS 3.5.4-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.5.4.1 -------------------------------NOTE------------------------------ 

 [ Only required to be performed when ambient air 

temperature is < [40]°F or > [100]°F. ] 

 --------------------------------------------------------------------- 

 Verify RWT borated water temperature is ≥ [40]°F 

and ≤ [100]°F. 

24 hours 

SR 3.5.4.2 Verify RWT borated water volume is 

≥ [362,800 gallons, (88)%] [above the ECCS suction 

connection]. 

7 days 

SR 3.5.4.3 Verify RWT boron concentration is ≥ [1720] ppm 

and ≤ [2500] ppm. 

7 days 
TSP 

3.5.5 

CEOG STS 3.5.5-1 Rev. 3.0, 03/31/04 

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 

3.5.5 Trisodium Phosphate (TSP) 

LCO 3.5.5 The TSP baskets shall contain ≥ [291] ft3

 of active TSP. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. TSP not within limits. A.1 Restore TSP to within 

limits. 

72 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4. 

6 hours 

[12] hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.5.5.1 Verify the TSP baskets contain ≥ [291] ft3

 of 

trisodium phosphate. 

[18] months 

SR 3.5.5.2 Verify that a sample from the TSP baskets provides 

adequate pH adjustment of RWT water. 

[18] months 
Containment (Atmospheric and Dual) 

3.6.1 

CEOG STS 3.6.1-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.1 Containment (Atmospheric and Dual) 

LCO 3.6.1 Containment shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Containment inoperable. A.1 Restore containment to 

OPERABLE status. 

1 hour 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.1.1 Perform required visual examinations and leakage 

rate testing except for containment air lock testing, 

in accordance with the Containment Leakage Rate 

Testing Program. 

In accordance 

with the 

Containment 

Leakage Rate 

Testing Program 

SR 3.6.1.2 [ Verify containment structural integrity in 

accordance with the Containment Tendon 

Surveillance Program. 

In accordance 

with the 

Containment 

Tendon 

Surveillance 

Program ]
Containment Air Locks (Atmospheric and Dual) 

3.6.2 

CEOG STS 3.6.2-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.2 Containment Air Locks (Atmospheric and Dual) 

LCO 3.6.2 [Two] containment air lock[s] shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

-----------------------------------------------------------NOTES---------------------------------------------------------- 

1. Entry and exit is permissible to perform repairs on the affected air lock components. 

2. Separate Condition entry is allowed for each air lock. 

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when 

leakage results in exceeding the overall containment leakage rate acceptance criteria. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more 

containment air locks 

with one containment air 

lock door inoperable. 

-------------------NOTES------------------ 

1. Required Actions A.1, A.2, 

and A.3 are not applicable if both 

doors in the same air lock are 

inoperable and Condition C is 

entered. 

2. Entry and exit is permissible for 

7 days under administrative 

controls [if both air locks are 

inoperable]. 

------------------------------------------------ 

A.1 Verify the OPERABLE door 

is closed in the affected air 

lock. 

AND

1 hour 
Containment Air Locks (Atmospheric and Dual) 

3.6.2 

CEOG STS 3.6.2-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.2 Lock the OPERABLE door 

closed in the affected air 

lock. 

AND

A.3 ---------------NOTE-------------- 

 Air lock doors in high 

radiation areas may be 

verified locked closed by 

administrative means. 

 ------------------------------------- 

 Verify the OPERABLE door 

is locked closed in the 

affected air lock. 

24 hours 

Once per 31 days 

B. One or more 

containment air locks 

with containment air lock 

interlock mechanism 

inoperable. 

-------------------NOTES------------------ 

1. Required Actions B.1, B.2, 

and B.3 are not applicable if both 

doors in the same air lock are 

inoperable and Condition C is 

entered. 

2. Entry and exit of containment is 

permissible under the control of a 

dedicated individual. 

------------------------------------------------ 

B.1 Verify an OPERABLE door 

is closed in the affected air 

lock. 

AND

1 hour 
Containment Air Locks (Atmospheric and Dual) 

3.6.2 

CEOG STS 3.6.2-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.2 Lock an OPERABLE door 

closed in the affected air 

lock. 

AND

B.3 ---------------NOTE-------------- 

 Air lock doors in high 

radiation areas may be 

verified locked closed by 

administrative means. 

 ------------------------------------- 

 Verify an OPERABLE door 

is locked closed in the 

affected air lock. 

24 hours 

Once per 31 days 

C. One or more 

containment air locks 

inoperable for reasons 

other than Condition A 

or B. 

C.1 Initiate action to evaluate 

overall containment 

leakage rate per LCO 3.6.1. 

AND

C.2 Verify a door is closed in 

the affected air lock. 

AND

C.3 Restore air lock to 

OPERABLE status. 

Immediately 

1 hour 

24 hours 

D. Required Action and 

associated Completion 

Time not met. 

D.1 Be in MODE 3. 

AND

D.2 Be in MODE 5. 

6 hours 

36 hours 
Containment Air Locks (Atmospheric and Dual) 

3.6.2 

CEOG STS 3.6.2-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.2.1 ------------------------------NOTES----------------------------- 

 1. An inoperable air lock door does not invalidate 

the previous successful performance of the 

overall air lock leakage test. 

 2. Results shall be evaluated against acceptance 

criteria applicable to SR 3.6.1.1. 

 --------------------------------------------------------------------- 

 Perform required air lock leakage rate testing in 

accordance with the Containment Leakage Rate 

Testing Program. 

In accordance 

with the 

Containment 

Leakage Rate 

Testing Program 

SR 3.6.2.2 Verify only one door in the air lock can be opened at 

a time. 

24 months 
Containment Isolation Valves (Atmospheric and Dual) 

3.6.3 

CEOG STS 3.6.3-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.3 Containment Isolation Valves (Atmospheric and Dual) 

LCO 3.6.3 Each containment isolation valve shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

-----------------------------------------------------------NOTES---------------------------------------------------------- 

1. Penetration flow paths [except for [42] inch purge valve penetration flow paths] may be 

unisolated intermittently under administrative controls. 

2. Separate Condition entry is allowed for each penetration flow path. 

3. Enter applicable Conditions and Required Actions for system(s) made inoperable by 

containment isolation valves. 

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when 

leakage results in exceeding the overall containment leakage rate acceptance criteria. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. ------------NOTE------------ 

 Only applicable to 

penetration flow paths 

with two [or more] 

containment isolation 

valves. 

 --------------------------------- 

 One or more penetration 

flow paths with one 

containment isolation 

valve inoperable [for 

reasons other than 

Condition[s] D [and E]]. 

A.1 Isolate the affected 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

blind flange, or check valve 

with flow through the valve 

secured. 

AND

4 hours 
Containment Isolation Valves (Atmospheric and Dual) 

3.6.3 

CEOG STS 3.6.3-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.2 --------------NOTES------------- 

 1. Isolation devices in high 

radiation areas may be 

verified by use of 

administrative means. 

 2. Isolation devices that 

are locked, sealed, or 

otherwise secured may 

be verified by use of 

administrative means. 

 ------------------------------------- 

 Verify the affected 

penetration flow path is 

isolated. 

Once per 31 days for 

isolation devices 

outside containment 

AND

Prior to entering 

MODE 4 from 

MODE 5 if not 

performed within the 

previous 92 days for 

isolation devices 

inside containment 

B. ------------NOTE------------ 

 Only applicable to 

penetration flow paths 

with two [or more] 

containment isolation 

valves. 

 --------------------------------- 

 One or more penetration 

flow paths with two [or 

more] containment 

isolation valves 

inoperable [for reasons 

other than Condition[s] D 

[and E]]. 

B.1 Isolate the affected 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

or blind flange. 

1 hour 
Containment Isolation Valves (Atmospheric and Dual) 

3.6.3 

CEOG STS 3.6.3-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. ------------NOTE------------ 

 Only applicable to 

penetration flow paths 

with only one 

containment isolation 

valve and a closed 

system. 

 --------------------------------- 

 One or more penetration 

flow paths with one 

containment isolation 

valve inoperable. 

C.1 Isolate the affected 

penetration flow path by 

use of at least one closed 

and de-activated automatic 

valve, closed manual valve, 

or blind flange. 

AND

C.2 --------------NOTES------------- 

 1. Isolation devices in high 

radiation areas may be 

verified by use of 

administrative means. 

 2. Isolation devices that 

are locked, sealed, or 

otherwise secured may 

be verified by use of 

administrative means. 

 ------------------------------------- 

 Verify the affected 

penetration flow path is 

isolated. 

[72] hours 

Once per 31 days 

D. [ One or more secondary 

containment bypass 

leakage [or purge valve 

leakage] not within limit. 

D.1 Restore leakage within 

limit. 

4 hours for secondary 

containment bypass 

leakage 

AND

24 hours for purge 

valve leakage ] 
Containment Isolation Valves (Atmospheric and Dual) 

3.6.3 

CEOG STS 3.6.3-4 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

E. [ One or more 

penetration flow paths 

with one or more 

containment purge 

valves not within purge 

valve leakage limits. 

E.1 Isolate the affected 

penetration flow path by 

use of at least one [closed 

and de-activated automatic 

valve with resilient seals, 

closed manual valve with 

resilient seals, or blind 

flange]. 

AND

E.2 --------------NOTES------------- 

 1. Isolation devices in high 

radiation areas may be 

verified by use of 

administrative means. 

 2. Isolation devices that 

are locked, sealed, or 

otherwise secured may 

be verified by use of 

administrative means. 

 ------------------------------------- 

 Verify the affected 

penetration flow path is 

isolated. 

AND

24 hours 

Once per 31 days for 

isolation devices 

outside containment 

AND

Prior to entering 

MODE 4 from 

MODE 5 if not 

performed within the 

previous 92 days for 

isolation devices 

inside containment 
Containment Isolation Valves (Atmospheric and Dual) 

3.6.3 

CEOG STS 3.6.3-5 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

 

E.3 Perform SR 3.6.3.6 for the 

resilient seal purge valves 

closed to comply with 

Required Action E.1. 

Once per [ ] days ] 

F. Required Action and 

associated Completion 

Time not met. 

F.1 Be in MODE 3 

AND

F.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.3.1 [ Verify each [42] inch purge valve is sealed closed 

except for one purge valve in a penetration flow 

path while in Condition E of this LCO. 

31 days ] 

SR 3.6.3.2 Verify each [8] inch purge valve is closed except 

when the [8] inch purge valves are open for 

pressure control, ALARA or air quality 

considerations for personnel entry, or for 

Surveillances that require the valves to be open. 

31 days 

SR 3.6.3.3 -------------------------------NOTE------------------------------ 

 Valves and blind flanges in high radiation areas may 

be verified by use of administrative means. 

 --------------------------------------------------------------------- 

 Verify each containment isolation manual valve and 

blind flange that is located outside containment and 

not locked, sealed, or otherwise secured and is 

required to be closed during accident conditions is 

closed, except for containment isolation valves that 

are open under administrative controls. 

31 days 
Containment Isolation Valves (Atmospheric and Dual) 

3.6.3 

CEOG STS 3.6.3-6 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.6.3.4 -------------------------------NOTE------------------------------ 

 Valves and blind flanges in high radiation areas may 

be verified by use of administrative means. 

 --------------------------------------------------------------------- 

 Verify each containment isolation manual valve and 

blind flange that is located inside containment and 

not locked, sealed, or otherwise secured and 

required to be closed during accident conditions is 

closed, except for containment isolation valves that 

are open under administrative controls. 

Prior to entering 

MODE 4 from 

MODE 5 if not 

performed within 

the previous 

92 days 

SR 3.6.3.5 Verify the isolation time of each automatic power 

operated containment isolation valve is within limits. 

[ In accordance 

with the Inservice 

Testing Program 

or 92 days ] 

SR 3.6.3.6 Perform leakage rate testing for containment purge 

valves with resilient seals. 

184 days 

AND

Within 92 days 

after opening the 

valve 

SR 3.6.3.7 Verify each automatic containment isolation valve 

that is not locked, sealed, or otherwise secured in 

position, actuates to the isolation position on an 

actual or simulated actuation signal. 

[18] months 

SR 3.6.3.8 [ Verify each [ ] inch containment purge valve is 

blocked to restrict the valve from opening > [50]%. 

[18] months ] 

SR 3.6.3.9 [ Verify the combined leakage rate for all secondary 

containment bypass leakage paths is ≤ [ La] when 

pressurized to ≥ [ psig]. 

In accordance 

with the 

Containment 

Leakage Rate 

Testing Program ]
Containment Pressure (Atmospheric and Dual) 

3.6.4 

CEOG STS 3.6.4-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.4 Containment Pressure (Atmospheric and Dual) 

LCO 3.6.4 Containment pressure shall be [Dual: > 14.375 psia and < 27 inches 

water gauge] [or] [Atmospheric: ≥ -0.3 psig and ≤ +1.5 psig]. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Containment pressure 

not within limits. 

A.1 Restore containment 

pressure to within limits. 

1 hour 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.4.1 Verify containment pressure is within limits. 12 hours 
Containment Air Temperature (Atmospheric and Dual) 

3.6.5 

CEOG STS 3.6.5-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.5 Containment Air Temperature (Atmospheric and Dual) 

LCO 3.6.5 Containment average air temperature shall be ≤ [120]°F. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Containment average air 

temperature not within 

limit. 

A.1 Restore containment 

average air temperature to 

within limit. 

8 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.5.1 Verify containment average air temperature is within 

limit. 

24 hours 
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6A 

CEOG STS 3.6.6A-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.6A Containment Spray and Cooling Systems (Atmospheric and Dual) 

 (Credit taken for iodine removal by the Containment Spray System) 

LCO 3.6.6A Two containment spray trains and two containment cooling trains shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and [4]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One containment spray 

train inoperable. 

A.1 Restore containment spray 

train to OPERABLE status. 

[7] days 

AND

14 days from 

discovery of failure to 

meet the LCO 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

84 hours 

C. One containment cooling 

train inoperable. 

C.1 Restore containment 

cooling train to OPERABLE 

status. 

7 days 

AND

14 days from 

discovery of failure to 

meet the LCO 

D. One containment spray 

and one containment 

cooling train inoperable. 

D.1 Restore containment spray 

train to OPERABLE status. 

OR

72 hours 
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6A 

CEOG STS 3.6.6A-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

 

D.2 Restore containment 

cooling train to OPERABLE 

status. 

72 hours 

E. Two containment cooling 

trains inoperable. 

E.1 Restore one containment 

cooling train to OPERABLE 

status. 

72 hours 

F. Required Action and 

associated Completion 

Time of Condition C, D, 

or E not met. 

F.1 Be in MODE 3. 

AND

F.2 Be in MODE 5. 

6 hours 

36 hours 

G. Two containment spray 

trains inoperable. 

 OR

 Any combination of three 

or more trains 

inoperable. 

G.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.6A.1 Verify each containment spray manual, power 

operated, and automatic valve in the flow path that 

is not locked, sealed, or otherwise secured in 

position is in the correct position. 

31 days 

SR 3.6.6A.2 Operate each containment cooling train fan unit for 

≥ 15 minutes. 

31 days 
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6A 

CEOG STS 3.6.6A-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.6.6A.3 Verify each containment cooling train cooling water 

flow rate is ≥ [2000] gpm to each fan cooler. 

31 days 

SR 3.6.6A.4 [ Verify the containment spray piping is full of water 

to the [100] ft level in the containment spray header. 

31 days ] 

SR 3.6.6A.5 Verify each containment spray pump's developed 

head at the flow test point is greater than or equal to 

the required developed head. 

In accordance 

with the Inservice 

Testing Program 

SR 3.6.6A.6 Verify each automatic containment spray valve in 

the flow path that is not locked, sealed, or otherwise 

secured in position, actuates to the correct position 

on an actual or simulated actuation signal. 

[18] months 

SR 3.6.6A.7 Verify each containment spray pump starts 

automatically on an actual or simulated actuation 

signal. 

[18] months 

SR 3.6.6A.8 Verify each containment cooling train starts 

automatically on an actual or simulated actuation 

signal. 

[18] months 

SR 3.6.6A.9 Verify each spray nozzle is unobstructed. [ At first refueling ] 

AND

10 years 
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6B 

CEOG STS 3.6.6B-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.6B Containment Spray and Cooling Systems (Atmospheric and Dual) (Credit not taken 

for iodine removal by the Containment Spray System) 

LCO 3.6.6B Two containment spray trains and two containment cooling trains shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and [4]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One containment spray 

train inoperable. 

A.1 Restore containment spray 

train to OPERABLE status. 

7 days 

AND

14 days from 

discovery of failure to 

meet the LCO 

B. One containment cooling 

train inoperable. 

B.1 Restore containment 

cooling train to OPERABLE 

status. 

7 days 

AND

14 days from 

discovery of failure to 

meet the LCO 

C. Two containment spray 

trains inoperable. 

C.1 Restore one containment 

spray train to OPERABLE 

status. 

72 hours 
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6B 

CEOG STS 3.6.6B-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. One containment spray 

train and one 

containment cooling 

train inoperable. 

D.1 Restore containment spray 

train to OPERABLE status. 

OR

D.2 Restore containment 

cooling train to OPERABLE 

status. 

72 hours 

72 hours 

E. Two containment cooling 

trains inoperable. 

E.1 Restore one containment 

cooling train to OPERABLE 

status. 

72 hours 

F. Required Action and 

associated Completion 

Time of Condition A, B, 

C, D, or E not met. 

F.1 Be in MODE 3. 

AND

F.2 Be in MODE 5. 

6 hours 

36 hours 

G. Any combination of three 

or more trains 

inoperable. 

G.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.6B.1 Verify each containment spray manual, power 

operated, and automatic valve in the flow path that 

is not locked, sealed, or otherwise secured in 

position is in the correct position. 

31 days 

SR 3.6.6B.2 Operate each containment cooling train fan unit for 

≥ 15 minutes. 

31 days 
Containment Spray and Cooling Systems (Atmospheric and Dual) 

3.6.6B 

CEOG STS 3.6.6B-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.6.6B.3 Verify each containment cooling train cooling water 

flow rate is ≥ [2000] gpm to each fan cooler. 

31 days 

SR 3.6.6B.4 [ Verify the containment spray piping is full of water 

to the [100] ft level in the containment spray header. 

31 days ] 

SR 3.6.6B.5 Verify each containment spray pump's developed 

head at the flow test point is greater than or equal to 

the required developed head. 

In accordance 

with the Inservice 

Testing Program 

SR 3.6.6B.6 Verify each automatic containment spray valve in 

the flow path that is not locked, sealed, or otherwise 

secured in position, actuates to its correct position 

on an actual or simulated actuation signal. 

[18] months 

SR 3.6.6B.7 Verify each containment spray pump starts 

automatically on an actual or simulated actuation 

signal. 

[18] months 

SR 3.6.6B.8 Verify each containment cooling train starts 

automatically on an actual or simulated actuation 

signal. 

[18] months 

SR 3.6.6B.9 Verify each spray nozzle is unobstructed. [ At first refueling ] 

AND

10 years 
Spray Additive System (Atmospheric and Dual) 

3.6.7 

CEOG STS 3.6.7-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.7 Spray Additive System (Atmospheric and Dual) 

LCO 3.6.7 The Spray Additive System shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and [4]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Spray Additive System 

inoperable. 

A.1 Restore Spray Additive 

System to OPERABLE 

status. 

72 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

84 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.7.1 Verify each spray additive manual, power operated, 

and automatic valve in the flow path that is not 

locked, sealed, or otherwise secured in position is in 

the correct position. 

31 days 

SR 3.6.7.2 Verify spray additive tank solution volume is 

≥ [816] gal [90%] and ≤ [896] gal [100%]. 

184 days 

SR 3.6.7.3 Verify spray additive tank [N2H4] solution 

concentration is ≥ [33]% and ≤ [35]% by weight. 

184 days 
Spray Additive System (Atmospheric and Dual) 

3.6.7 

CEOG STS 3.6.7-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.6.7.4 [ Verify each spray additive pump develops a 

differential pressure of [100] psid on recirculation 

flow. 

In accordance 

with the Inservice 

Testing Program ]

SR 3.6.7.5 Verify each spray additive automatic valve in the 

flow path that is not locked, sealed, or otherwise 

secured in position, actuates to the correct position 

on an actual or simulated actuation signal. 

[18] months 

SR 3.6.7.6 [ Verify spray additive flow [rate] from each 

solution's flow path. 

5 years ] 
HMS (Atmospheric and Dual) 

3.6.9 

CEOG STS 3.6.9-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.9 Hydrogen Mixing System (HMS) (Atmospheric and Dual) 

LCO 3.6.9 [Two] HMS trains shall be OPERABLE. 

APPLICABILITY: MODES 1 and 2. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One HMS train 

inoperable. 

A.1 Restore HMS train to 

OPERABLE status. 

30 days 

B. [ Two HMS trains 

inoperable. 

B.1 Verify by administrative 

means that the hydrogen 

control function is 

maintained. 

AND

B.2 Restore one HMS train to 

OPERABLE status. 

1 hour 

AND

Once every 12 hours 

thereafter 

7 days ] 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Be in MODE 3. 6 hours 
HMS (Atmospheric and Dual) 

3.6.9 

CEOG STS 3.6.9-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.9.1 Operate each HMS train for ≥ 15 minutes. 92 days 

SR 3.6.9.2 Verify each HMS train flow rate on slow speed is 

≥ [37,000] cfm. 

[18] months 

SR 3.6.9.3 Verify each HMS train starts on an actual or 

simulated actuation signal. 

[18] months 
ICS (Atmospheric and Dual) 

3.6.10 

CEOG STS 3.6.10-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.10 Iodine Cleanup System (ICS) (Atmospheric and Dual) 

LCO 3.6.10 [Two] ICS trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One ICS train 

inoperable. 

A.1 Restore ICS train to 

OPERABLE status. 

7 days 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.10.1 Operate each ICS train for [≥ 10 continuous hours 

with heaters operating or (for systems without 

heaters) ≥ 15 minutes]. 

31 days 

SR 3.6.10.2 Perform required ICS filter testing in accordance 

with the Ventilation Filter Testing Program (VFTP). 

In accordance 

with the VFTP 

SR 3.6.10.3 Verify each ICS train actuates on an actual or 

simulated actuation signal. 

[18] months 
ICS (Atmospheric and Dual) 

3.6.10 

CEOG STS 3.6.10-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.6.10.4 [ Verify each ICS filter bypass damper can be 

opened. 

[18] months ] 
Shield Building (Dual) 

3.6.11 

CEOG STS 3.6.11-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.11 Shield Building (Dual) 

LCO 3.6.11 Shield building shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Shield building 

inoperable. 

A.1 Restore shield building to 

OPERABLE status. 

24 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.11.1 Verify annulus negative pressure is > [5] inches 

water gauge. 

12 hours 

SR 3.6.11.2 Verify one shield building access door in each 

access opening is closed. 

31 days 

SR 3.6.11.3 Verify shield building structural integrity by 

performing a visual inspection of the exposed 

interior and exterior surfaces of the shield building. 

During shutdown 

for SR 3.6.1.1 

Type A tests 
Shield Building (Dual) 

3.6.11 

CEOG STS 3.6.11-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.6.11.4 Verify the shield building can be maintained at a 

pressure equal to or more negative than [-0.25] inch 

water gauge in the annulus by one Shield Building 

Exhaust Air Cleanup System train with a final flow 

rate ≤ [ ] cfm within [1] minute after a start signal. 

[18] months on a 

STAGGERED 

TEST BASIS for 

each Shield 

Building Exhaust 

Air Cleanup 

System 
Vacuum Relief Valves (Dual) 

3.6.12 

CEOG STS 3.6.12-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.12 Vacuum Relief Valves (Dual) 

LCO 3.6.12 Two vacuum relief lines shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One vacuum relief line 

inoperable. 

A.1 Restore vacuum relief line 

to OPERABLE status. 

72 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.12.1 Verify each vacuum relief line OPERABLE in 

accordance with the Inservice Testing Program. 

In accordance 

with the Inservice 

Testing Program 
SBEACS (Dual) 

3.6.8 

CEOG STS 3.6.8-1 Rev. 3.0, 03/31/04 

3.6 CONTAINMENT SYSTEMS 

3.6.8 Shield Building Exhaust Air Cleanup System (SBEACS) (Dual) 

LCO 3.6.8 Two SBEACS trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One SBEACS train 

inoperable. 

A.1 Restore train to 

OPERABLE status. 

7 days 

B. Required Action and 

Associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.6.8.1 Operate each SBEACS train for [≥ 10 continuous 

hours with the heaters operating or (for systems 

without heaters) ≥ 15 minutes]. 

31 days 

SR 3.6.8.2 Perform required SBEACS filter testing in 

accordance with the Ventilation Filter Testing 

Program (VFTP). 

In accordance 

with the VFTP 

SR 3.6.8.3 Verify each SBEACS train actuates on an actual or 

simulated actuation signal. 

[18] months 
SBEACS (Dual) 

3.6.8 

CEOG STS 3.6.8-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.6.8.4 [ Verify each SBEACS filter bypass damper can be 

opened. 

[18] months ] 

SR 3.6.8.5 Verify each SBEACS train flow rate is ≥ [ ] cfm. [18] months on a 

STAGGERED 

TEST BASIS 
MSSVs 

3.7.1 

CEOG STS 3.7.1-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.1 Main Steam Safety Valves (MSSVs) 

LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and 

Table 3.7.1-2. 

APPLICABILITY: MODES 1, 2, and 3. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each MSSV. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more required 

MSSVs inoperable. 

A.1 Reduce power to less than 

or equal to the applicable 

% RTP listed in 

Table 3.7.1-1. 

AND

A.2 Reduce the [variable 

overpower trip - high] 

setpoint [ceiling] in 

accordance with 

Table 3.7.1-1. 

4 hours 

36 hours 

B. Required Action and 

associated Completion 

Time not met. 

 OR

 One or more steam 

generators with less 

than [two] MSSVs 

OPERABLE. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4. 

6 hours 

[12] hours 
MSSVs 

3.7.1 

CEOG STS 3.7.1-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.1.1 -------------------------------NOTE------------------------------ 

 Only required to be performed in MODES 1 and 2. 

 --------------------------------------------------------------------- 

 Verify each required MSSV lift setpoint per 

Table 3.7.1-2 in accordance with the Inservice 

Testing Program. Following testing, lift settings 

shall be within + 1%. 

In accordance 

with the Inservice 

Testing Program 
MSSVs 

3.7.1 

CEOG STS 3.7.1-3 Rev. 3.0, 03/31/04 

Table 3.7.1-1 (page 1 of 1) 

[Variable Overpower Trip] Setpoint versus 

OPERABLE Main Steam Safety Valves 

MINIMUM NUMBER OF 

MSSVs PER STEAM 

GENERATOR 

REQUIRED OPERABLE MAXIMUM POWER 

(% RTP) 

MAXIMUM ALLOWABLE 

[VARIABLE OVERPOWER 

TRIP] SETPOINT 

([CEILING] % RTP) 

[8] [ ] [ ] 

[7] [ ] [ ] 

[6] [ ] [ ] 

[5] [ ] [ ] 

[4] [ ] [ ] 

[3] [ ] [ ] 

[2] [ ] [ ] 
MSSVs 

3.7.1 

CEOG STS 3.7.1-4 Rev. 3.0, 03/31/04 

Table 3.7.1-2 (page 1 of 1) 

Main Steam Safety Valve Lift Settings

VALVE NUMBER 

Steam Generator #1 Steam Generator #2 

LIFT SETTING 

(psig ± [3]%) 

[ ] [ ] [ ] 

[ ] [ ] [ ] 

[ ] [ ] [ ] 

[ ] [ ] [ ] 
MSIVs 

3.7.2 

CEOG STS 3.7.2-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.2 Main Steam Isolation Valves (MSIVs) 

LCO 3.7.2 [Two] MSIVs shall be OPERABLE. 

APPLICABILITY: MODE 1, 

 MODES 2 and 3 except when all MSIVs are closed [and de-activated]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One MSIV inoperable in 

MODE 1. 

A.1 Restore MSIV to 

OPERABLE status. 

[8] hours 

B. Required Action and 

Associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 2. 6 hours 

C. ------------NOTE------------ 

 Separate Condition entry 

is allowed for each 

MSIV. 

 --------------------------------- 

 One or more MSIVs 

inoperable in MODE 2 

or 3. 

C.1 Close MSIV. 

AND

C.2 Verify MSIV is closed. 

[8] hours 

Once per 7 days 

D. Required Action and 

associated Completion 

Time of Condition C not 

met. 

D.1 Be in MODE 3. 

AND

D.2 Be in MODE 4. 

6 hours 

[12] hours 
MSIVs 

3.7.2 

CEOG STS 3.7.2-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.2.1 -------------------------------NOTE------------------------------ 

 Only required to be performed in MODES 1 and 2. 

 --------------------------------------------------------------------- 

 Verify the isolation time of each MSIV is 

≤ [4.6] seconds. 

In accordance 

with the Inservice 

Testing Program 

SR 3.7.2.2 -------------------------------NOTE------------------------------ 

 Only required to be performed in MODES 1 and 2. 

 --------------------------------------------------------------------- 

 Verify each MSIV actuates to the isolation position 

on an actual or simulated actuation signal. 

[18] months 
MFIVs [and [MFIV] Bypass Valves] 

3.7.3 

CEOG STS 3.7.3-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.3 Main Feedwater Isolation Valves (MFIVs) [and [MFIV] Bypass Valves] 

LCO 3.7.3 [Two] MFIVs [and [MFIV] bypass valves] shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, [and 3] except when MFIV [or [MFIV] bypass valve] is 

closed and [de-activated] or [isolated by a closed manual valve]. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each valve. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more MFIVs [or 

[MFIV] bypass valves] 

inoperable. 

A.1 Close or isolate inoperable 

MFIV [or [MFIV] bypass 

valve]. 

AND

A.2 Verify inoperable MFIV [or 

[MFIV] bypass valve] is 

closed or isolated. 

[8 or 72] hours 

Once per 7 days 

B. [ [Two] valves in the 

same flow path 

inoperable. 

B.1 Isolate affected flow path. 

AND

B.2 Verify inoperable MFIV [or 

[MFIV] bypass valve] is 

closed or isolated. 

8 hours 

Once per 7 days ] 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Be in MODE 3. 

[ AND

C.2 Be in MODE 4. 

6 hours 

[12] hours ] 
MFIVs [and [MFIV] Bypass Valves] 

3.7.3 

CEOG STS 3.7.3-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.3.1 Verify the isolation time of each MFIV [and [MFIV] 

bypass valve] is ≤ [7] seconds. 

In accordance 

with the Inservice 

Testing Program 

SR 3.7.3.2 Verify each MFIV [and [MFIV] bypass valve] 

actuates to the isolation position on an actual or 

simulated actuation signal. 

[18] months 
ADVs 

3.7.4 

CEOG STS 3.7.4-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.4 Atmospheric Dump Valves (ADVs) 

LCO 3.7.4 [Two] ADV lines shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3, 

 [MODE 4 when steam generator is being relied upon for heat removal]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One required ADV line 

inoperable. 

A.1 Restore ADV line to 

OPERABLE status. 

7 days 

B. Two or more [required] 

ADV lines inoperable. 

B.1 Restore all but one ADV 

line to OPERABLE status. 

24 hours 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Be in MODE 3. 

[ AND

C.2 Be in MODE 4 without 

reliance upon steam 

generator for heat removal. 

6 hours 

[24] hours ] 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.4.1 Verify one complete cycle of each ADV. [18] months 
ADVs 

3.7.4 

CEOG STS 3.7.4-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.7.4.2 [ Verify one complete cycle of each ADV block 

valve. 

[18] months ] 
AFW System 

3.7.5 

CEOG STS 3.7.5-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.5 Auxiliary Feedwater (AFW) System 

LCO 3.7.5 [Three] AFW trains shall be OPERABLE. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Only one AFW train, which includes a motor driven pump, is required to 

be OPERABLE in MODE 4. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 1, 2, and 3, 

 [MODE 4 when steam generator is relied upon for heat removal]. 

ACTIONS 

-----------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.4.b is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. [ One steam supply to 

turbine driven AFW 

pump inoperable. 

 OR

 ------------NOTE------------ 

 Only applicable if 

MODE 2 has not been 

entered following 

refueling. 

 --------------------------------- 

 One turbine driven AFW 

pump inoperable in 

MODE 3 following 

refueling. 

A.1 Restore affected equipment 

to OPERABLE status. 

7 days 

AND

10 days from 

discovery of failure to 

meet the LCO ] 
AFW System 

3.7.5 

CEOG STS 3.7.5-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. One AFW train 

inoperable [for reasons 

other than Condition A] 

in MODE 1, 2, or 3. 

B.1 Restore AFW train to 

OPERABLE status. 

72 hours 

AND

[10 days from 

discovery of failure to 

meet the LCO] 

C. Required Action and 

associated Completion 

Time of Condition A 

[or B] not met. 

[ OR

 [Two] AFW trains 

inoperable in MODE 1, 

2, or 3. ] 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 4. 

6 hours 

[18] hours 

D. [ [Three] AFW trains 

inoperable in MODE 1, 

2, or 3. 

D.1 ---------------NOTE-------------- 

 LCO 3.0.3 and all other 

LCO Required Actions 

requiring MODE changes 

are suspended until one 

AFW train is restored to 

OPERABLE status. 

 ------------------------------------- 

 Initiate action to restore one 

AFW train to OPERABLE 

status. 

Immediately ] 
AFW System 

3.7.5 

CEOG STS 3.7.5-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

E. Required AFW train 

inoperable in MODE 4. 

E.1 ---------------NOTE-------------- 

 LCO 3.0.3 and all other 

LCO Required Actions 

requiring MODE changes 

are suspended until one 

AFW train is restored to 

OPERABLE status. 

 ------------------------------------- 

 Initiate action to restore one 

AFW train to OPERABLE 

status. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.5.1 Verify each AFW manual, power operated, and 

automatic valve in each water flow path and in both 

steam supply flow paths to the steam turbine driven 

pump, that is not locked, sealed, or otherwise 

secured in position, is in the correct position. 

31 days 

SR 3.7.5.2 -------------------------------NOTE------------------------------ 

 Not required to be performed for the turbine driven 

AFW pump until [24] hours after reaching [800] psig 

in the steam generators. 

 --------------------------------------------------------------------- 

 Verify the developed head of each AFW pump at the 

flow test point is greater than or equal to the 

required developed head. 

In accordance 

with the Inservice 

Testing Program 
AFW System 

3.7.5 

CEOG STS 3.7.5-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.7.5.3 ------------------------------NOTES----------------------------- 

 1. Not required to be performed for the turbine 

driven AFW pump until [24] hours after reaching 

[800] psig in the steam generators. 

 2. Not required to be met in MODE 4 when steam 

generator is relied upon for heat removal. 

 --------------------------------------------------------------------- 

 Verify each AFW automatic valve that is not locked, 

sealed, or otherwise secured in position, actuates to 

the correct position on an actual or simulated 

actuation signal. 

[18] months 

SR 3.7.5.4 ------------------------------NOTES----------------------------- 

 1. Not required to be performed for the turbine 

driven AFW pump until [24] hours after reaching 

[800] psig in the steam generators. 

 2. Not required to be met in MODE 4 when steam 

generator is relied upon for heat removal. 

 --------------------------------------------------------------------- 

 Verify each AFW pump starts automatically on an 

actual or simulated actuation signal when in 

MODE 1, 2, or 3. 

[18] months 

SR 3.7.5.5 Verify the proper alignment of the required AFW 

flow paths by verifying flow from the condensate 

storage tank to each steam generator. 

Prior to entering 

MODE 2 

whenever unit has 

been in MODE 5, 

MODE 6, or 

defueled for a 

cumulative period 

of > 30 days 
CST 

3.7.6 

CEOG STS 3.7.6-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.6 Condensate Storage Tank (CST) 

LCO 3.7.6 The CST shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, and 3, 

 [MODE 4 when steam generator is relied upon for heat removal]. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. CST inoperable. A.1 Verify OPERABILITY of 

backup water supply. 

AND

A.2 Restore CST to 

OPERABLE status. 

4 hours 

AND

Once per 12 hours 

thereafter 

7 days 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 4 without 

reliance on steam 

generator for heat removal. 

6 hours 

[24] hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.6.1 Verify CST level is ≥ [350,000] gal. 12 hours 
CCW System 

3.7.7 

CEOG STS 3.7.7-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.7 Component Cooling Water (CCW) System 

LCO 3.7.7 Two CCW trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One CCW train 

inoperable. 

A.1 ---------------NOTE-------------- 

 Enter applicable Conditions 

and Required Actions of 

LCO 3.4.6, "RCS Loops - 

MODE 4," for shutdown 

cooling made inoperable by 

CCW. 

 ------------------------------------- 

 Restore CCW train to 

OPERABLE status. 

72 hours 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 
CCW System 

3.7.7 

CEOG STS 3.7.7-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.7.1 -------------------------------NOTE------------------------------ 

 Isolation of CCW flow to individual components 

does not render the CCW System inoperable. 

 --------------------------------------------------------------------- 

 Verify each CCW manual, power operated, and 

automatic valve in the flow path servicing safety 

related equipment, that is not locked, sealed, or 

otherwise secured in position, is in the correct 

position. 

31 days 

SR 3.7.7.2 Verify each CCW automatic valve in the flow path 

that is not locked, sealed, or otherwise secured in 

position, actuates to the correct position on an 

actual or simulated actuation signal. 

[18] months 

SR 3.7.7.3 Verify each CCW pump starts automatically on an 

actual or simulated actuation signal. 

[18] months 
SWS 

3.7.8 

CEOG STS 3.7.8-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.8 Service Water System (SWS) 

LCO 3.7.8 Two SWS trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One SWS train 

inoperable. 

A.1 --------------NOTES------------- 

 1. Enter applicable 

Conditions and 

Required Actions of 

LCO 3.8.1, 

"AC Sources - 

Operating," for 

emergency diesel 

generator made 

inoperable by SWS. 

 2. Enter applicable 

Conditions and 

Required Actions of 

LCO 3.4.6, "RCS Loops 

- MODE 4," for 

shutdown cooling made 

inoperable by SWS. 

 ------------------------------------- 

 Restore SWS train to 

OPERABLE status. 

72 hours 

B. Required Action and 

associated Completion 

Time of Condition A not 

met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 
SWS 

3.7.8 

CEOG STS 3.7.8-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.8.1 -------------------------------NOTE------------------------------ 

 Isolation of SWS flow to individual components does 

not render the SWS inoperable. 

 --------------------------------------------------------------------- 

 Verify each SWS manual, power operated, and 

automatic valve in the flow path servicing safety 

related equipment, that is not locked, sealed, or 

otherwise secured in position, is in the correct 

position. 

31 days 

SR 3.7.8.2 Verify each SWS automatic valve in the flow path 

that is not locked, sealed, or otherwise secured in 

position, actuates to the correct position on an 

actual or simulated actuation signal. 

[18] months 

SR 3.7.8.3 Verify each SWS pump starts automatically on an 

actual or simulated actuation signal. 

[18] months 
UHS 

3.7.9 

CEOG STS 3.7.9-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.9 Ultimate Heat Sink (UHS) 

LCO 3.7.9 The UHS shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. [ One or more cooling 

towers with one cooling 

tower fan inoperable. 

A.1 Restore cooling tower 

fan(s) to OPERABLE 

status. 

7 days ] 

-----REVIEWER’S NOTE----- 

The [ ]°F is the maximum 

allowed UHS temperature 

value and is based on 

temperature limitations of 

the equipment that is relied 

upon for accident mitigation 

and safe shutdown of the 

unit. 

-------------------------------------- 

B. [ Water temperature of 

the UHS > [90]°F and 

≤ [ ]°F. 

B.1 Verify water temperature of 

the UHS is ≤ [90]°F 

averaged over the previous 

24 hour period. 

Once per hour] 

C. [ Required Action and 

associated Completion 

Time of Condition A or B 

not met. 

 OR ] 

 UHS inoperable [for 

reasons other than 

Condition A or B]. 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 5. 

6 hours 

36 hours 
UHS 

3.7.9 

CEOG STS 3.7.9-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.9.1 [ Verify water level of UHS is ≥ [562] ft [mean sea 

level]. 

24 hours ] 

SR 3.7.9.2 [ Verify average water temperature of UHS is 

≤ [90]°F. 

24 hours ] 

SR 3.7.9.3 [ Operate each cooling tower fan for ≥ [15] minutes. 31 days ] 
ECW 

3.7.10 

CEOG STS 3.7.10-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.10 Essential Chilled Water (ECW) 

LCO 3.7.10 [Two] ECW trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One ECW train 

inoperable. 

A.1 Restore ECW train to 

OPERABLE status. 

7 days 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.10.1 -------------------------------NOTE------------------------------ 

 Isolation of ECW flow to individual components does 

not render the ECW System inoperable. 

 --------------------------------------------------------------------- 

 Verify each ECW manual, power operated, and 

automatic valve in the flow path, that is not locked, 

sealed, or otherwise secured in position, is in the 

correct position. 

31 days 
ECW 

3.7.10 

CEOG STS 3.7.10-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.7.10.2 Verify the proper actuation of each ECW System 

component on an actual or simulated actuation 

signal. 

[18] months 
CREACS 

3.7.11 

CEOG STS 3.7.11-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.11 Control Room Emergency Air Cleanup System (CREACS) 

LCO 3.7.11 Two CREACS trains shall be OPERABLE. 

 ---------------------------------------------NOTE-------------------------------------------- 

 The control room boundary may be opened intermittently under 

administrative control. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6,] 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One CREACS train 

inoperable. 

A.1 Restore CREACS train to 

OPERABLE status. 

7 days 

Two CREACS trains 

inoperable due to 

inoperable control room 

boundary in MODE 1, 2, 

3, or 4. 

B.1 Restore control room 

boundary to OPERABLE 

status. 

24 hours 

C. Required Action and 

associated Completion 

Time of Condition A or B 

not met in MODE 1, 2, 3, 

or 4. 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 5. 

6 hours 

36 hours 
CREACS 

3.7.11 

CEOG STS 3.7.11-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

D. Required Action and 

associated Completion 

Time of Condition A not 

met [in MODES 5 and 6, 

or] during movement of 

[recently] irradiated fuel 

assemblies. 

D.1 ---------------NOTE-------------- 

 Place in toxic gas 

protection mode if 

automatic transfer to toxic 

gas mode inoperable. 

 ------------------------------------- 

 Place OPERABLE 

CREACS train in 

emergency radiation 

protection mode. 

OR

D.2 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

Immediately 

Immediately 

E. Two CREACS trains 

inoperable [in MODES 5 

and 6, or] during 

movement of [recently] 

irradiated fuel 

assemblies. 

E.1 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

Immediately 

F. Two CREACS trains 

inoperable in MODE 1, 

2, 3, or 4 for reasons 

other than Condition B. 

F.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.11.1 Operate each CREACS train for [≥ 10 continuous 

hours with heaters operating or (for systems without 

heaters) ≥ 15 minutes]. 

31 days 
CREACS 

3.7.11 

CEOG STS 3.7.11-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.7.11.2 Perform required CREACS filter testing in 

accordance with [Ventilation Filter Testing Program 

(VFTP)]. 

In accordance 

with the [VFTP] 

SR 3.7.11.3 Verify each CREACS train actuates on an actual or 

simulated actuation signal. 

[18] months 

SR 3.7.11.4 Verify one CREACS train can maintain a positive 

pressure of ≥ [0.125] inches water gauge, relative to 

the adjacent [area] during the emergency radiation 

state of the emergency mode of operation at a 

emergency ventilation flow rate of ≤ [3000] cfm. 

[18] months on a 

STAGGERED 

TEST BASIS 
CREATCS 

3.7.12 

CEOG STS 3.7.12-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.12 Control Room Emergency Air Temperature Control System (CREATCS) 

LCO 3.7.12 Two CREATCS trains shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, 4, [5, and 6,] 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One CREATCS train 

inoperable. 

A.1 Restore CREATCS train to 

OPERABLE status. 

30 days 

B. Required Action and 

associated Completion 

Time of Condition A not 

met in MODE 1, 2, 3, 

or 4. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 

C. Required Action and 

associated Completion 

Time of Condition A not 

met [in MODE 5 or 6, or] 

during movement of 

[recently] irradiated fuel 

assemblies. 

C.1 Place OPERABLE 

CREATCS train in 

operation. 

OR

C.2 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

Immediately 

Immediately 

D. Two CREATCS trains 

inoperable [in MODE 5 

or 6, or] during 

movement of [recently] 

irradiated fuel 

assemblies. 

D.1 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

Immediately 
CREATCS 

3.7.12 

CEOG STS 3.7.12-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

E. Two CREATCS trains 

inoperable in MODE 1, 

2, 3, or 4. 

E.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.12.1 Verify each CREATCS train has the capability to 

remove the assumed heat load. 

[18] months 
ECCS PREACS 

3.7.13 

CEOG STS 3.7.13-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.13 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup 

 System (PREACS) 

LCO 3.7.13 Two ECCS PREACS trains shall be OPERABLE. 

 ---------------------------------------------NOTE-------------------------------------------- 

 The ECCS pump room boundary may be opened intermittently under 

administrative control. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One ECCS PREACS 

train inoperable. 

A.1 Restore ECCS PREACS 

train to OPERABLE status. 

7 days 

B. Two ECCS PREACS 

trains inoperable due to 

inoperable ECCS pump 

room boundary. 

B.1 Restore ECCS pump room 

boundary to OPERABLE 

status. 

24 hours 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 5. 

6 hours 

36 hours 
ECCS PREACS 

3.7.13 

CEOG STS 3.7.13-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.13.1 Operate each ECCS PREACS train for 

[≥ 10 continuous hours with the heater operating or 

(for systems without heaters) ≥ 15 minutes]. 

31 days 

SR 3.7.13.2 Perform required ECCS PREACS filter testing in 

accordance with the [Ventilation Filter Testing 

Program (VFTP)]. 

In accordance 

with the [VFTP] 

SR 3.7.13.3 Verify each ECCS PREACS train actuates on an 

actual or simulated actuation signal. 

[18] months 

SR 3.7.13.4 Verify one ECCS PREACS train can maintain a 

negative pressure ≥ [ ] inches water gauge relative 

to atmospheric pressure during the [post accident] 

mode of operation at a flow rate of ≤ [20,000] cfm. 

[18] months on a 

STAGGERED 

TEST BASIS 

SR 3.7.13.5 [ Verify each ECCS PREACS filter bypass damper 

can be opened. 

[18] months ]
FBACS 

3.7.14 

CEOG STS 3.7.14-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.14 Fuel Building Air Cleanup System (FBACS) 

LCO 3.7.14 Two FBACS trains shall be OPERABLE. 

 ---------------------------------------------NOTE-------------------------------------------- 

 The fuel building boundary may be opened intermittently under 

administrative control. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: [MODES 1, 2, 3, and 4,] 

 During movement of [recently] irradiated fuel assemblies in the fuel 

building. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One FBACS train 

inoperable. 

A.1 Restore FBACS train to 

OPERABLE status. 

7 days 

B. Two FBACS trains 

inoperable due to 

inoperable fuel building 

boundary in MODE 1, 2, 

3, or 4. 

B.1 Restore fuel building 

boundary to OPERABLE 

status. 

24 hours 
FBACS 

3.7.14 

CEOG STS 3.7.14-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. [ Required Action and 

associated Completion 

Time of Condition A or B 

not met in MODE 1, 2, 3, 

or 4. 

 OR

 Two FBACS trains 

inoperable in MODE 1, 

2, 3, or 4 for reasons 

other than Condition B. 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 5. 

6 hours 

36 hours ] 

D. Required Action and 

Associated Completion 

Time [of Condition A] not 

met during movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building. 

D.1 Place OPERABLE FBACS 

train in operation. 

OR

D.2 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building. 

Immediately 

Immediately 

E. Two FBACS trains 

inoperable during 

movement of [recently] 

irradiated fuel 

assemblies in the fuel 

building. 

E.1 Suspend movement of 

[recently] irradiated fuel 

assemblies in the fuel 

building. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.14.1 Operate each FBACS train for [≥ 10 continuous 

hours with the heaters operating or (for systems 

without heaters) ≥ 15 minutes]. 

31 days 
FBACS 

3.7.14 

CEOG STS 3.7.14-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.7.14.2 Perform required FBACS filter testing in accordance 

with the [Ventilation Filter Testing Program (VFTP)]. 

In accordance 

with the [VFTP] 

SR 3.7.14.3 [ Verify each FBACS train actuates on an actual or 

simulated actuation signal. 

[18] months ] 

SR 3.7.14.4 Verify one FBACS train can maintain a negative 

pressure ≥ [ ] inches water gauge with respect to 

atmospheric pressure, during the [post accident] 

mode of operation at a flow rate ≤ [3000] cfm. 

[18] months on a 

STAGGERED 

TEST BASIS 

SR 3.7.14.5 [ Verify each FBACS filter bypass damper can be 

opened. 

[18] months ] 
PREACS 

3.7.15 

CEOG STS 3.7.15-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.15 Penetration Room Exhaust Air Cleanup System (PREACS) 

LCO 3.7.15 Two PREACS trains shall be OPERABLE. 

 ---------------------------------------------NOTE-------------------------------------------- 

 The penetration room boundary may be opened intermittently under 

administrative control. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One PREACS train 

inoperable. 

A.1 Restore PREACS train to 

OPERABLE status. 

7 days 

B. Two PREACS trains 

inoperable due to 

inoperable penetration 

room boundary. 

B.1 Restore penetration room 

boundary to OPERABLE 

status. 

24 hours 

C. Required Action and 

associated Completion 

Time not met. 

C.1 Be in MODE 3. 

AND

C.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.15.1 Operate each PREACS train for [≥ 10 continuous 

hours with the heater operating or (for systems 

without heaters) ≥ 15 minutes]. 

31 days 
PREACS 

3.7.15 

CEOG STS 3.7.15-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.7.15.2 Verify required PREACS filter testing in accordance 

with the [Ventilation Filter Testing Program (VFTP)]. 

In accordance 

with the [VFTP] 

SR 3.7.15.3 [ Verify each PREACS train actuates on an actual or 

simulated actuation signal. 

[18] months ] 

SR 3.7.15.4 [ Verify one PREACS train can maintain a negative 

pressure ≥ [ ] inches water gauge with respect to 

atmospheric pressure during the [post accident] 

mode of operation at a flow rate of ≤ [3000] cfm. 

[18] months on a 

STAGGERED 

TEST BASIS ] 

SR 3.7.15.5 [ Verify each PREACS filter bypass damper can be 

opened. 

[18] months ] 
Fuel Storage Pool Water Level 

3.7.16 

CEOG STS 3.7.16-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.16 Fuel Storage Pool Water Level 

LCO 3.7.16 The fuel storage pool water level shall be ≥ 23 ft over the top of irradiated 

fuel assemblies seated in the storage racks. 

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel storage pool. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Fuel storage pool water 

level not within limit. 

A.1 ---------------NOTE-------------- 

 LCO 3.0.3 is not applicable. 

 ------------------------------------- 

 Suspend movement of 

irradiated fuel assemblies in 

fuel storage pool. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.16.1 Verify the fuel storage pool water level is ≥ 23 ft 

above the top of irradiated fuel assemblies seated in 

the storage racks. 

7 days 
Fuel Storage Pool Boron Concentration 

3.7.17 

CEOG STS 3.7.17-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.17 Fuel Storage Pool Boron Concentration 

LCO 3.7.17 The fuel storage pool boron concentration shall be ≥ [2000] ppm. 

APPLICABILITY: When fuel assemblies are stored in the fuel storage pool and a fuel 

storage pool verification has not been performed since the last 

movement of fuel assemblies in the fuel storage pool. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Fuel storage pool boron 

concentration not within 

limit. 

--------------------NOTE------------------- 

LCO 3.0.3 is not applicable. 

------------------------------------------------ 

A.1 Suspend movement of fuel 

assemblies in the fuel 

storage pool. 

AND

A.2.1 Initiate action to restore fuel 

storage pool boron 

concentration to within limit. 

 OR

A.2.2 Initiate action to perform a 

fuel storage pool 

verification. 

Immediately 

Immediately 

Immediately 
Fuel Storage Pool Boron Concentration 

3.7.17 

CEOG STS 3.7.17-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.17.1 Verify the fuel storage pool boron concentration is 

within limit. 

7 days 
Spent Fuel Pool Storage 

3.7.18 

CEOG STS 3.7.18-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.18 Spent Fuel Pool Storage 

LCO 3.7.18 The combination of initial enrichment and burnup of each fuel assembly 

stored in [Region 2] shall be within the acceptable [burnup domain] of 

Figure 3.7.18-1 [or in accordance with Specification 4.3.1.1]. 

APPLICABILITY: Whenever any fuel assembly is stored in [Region 2] of the fuel storage 

pool. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Requirements of the 

LCO not met. 

A.1 ---------------NOTE-------------- 

 LCO 3.0.3 is not applicable. 

 ------------------------------------- 

 Initiate action to move the 

noncomplying fuel 

assembly from [Region 2]. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.18.1 Verify by administrative means the initial enrichment 

and burnup of the fuel assembly is in accordance 

with Figure 3.7.18-1 or Specification 4.3.1.1. 

Prior to storing the 

fuel assembly in 

[Region 2] 
Spent Fuel Pool Storage 

3.7.18 

CEOG STS 3.7.18-2 Rev. 3.0, 03/31/04 
Secondary Specific Activity 

3.7.19 

CEOG STS 3.7.19-1 Rev. 3.0, 03/31/04 

3.7 PLANT SYSTEMS 

3.7.19 Secondary Specific Activity 

LCO 3.7.19 The specific activity of the secondary coolant shall be ≤ [0.10] μCi/gm 

DOSE EQUIVALENT I-131. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Specific activity not 

within limit. 

A.1 Be in MODE 3. 

AND

A.2 Be in MODE 5. 

6 hours 

36 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.7.19.1 Verify the specific activity of the secondary coolant 

is within limit. 

[31] days 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.1 AC Sources - Operating 

LCO 3.8.1 The following AC electrical sources shall be OPERABLE: 

 a. Two qualified circuits between the offsite transmission network and 

the onsite Class 1E AC Electrical Power Distribution System, 

 b. Two diesel generators (DGs) each capable of supplying one train of 

the onsite Class 1E AC Electrical Power Distribution System, and 

 [ c. Automatic load sequencers for Train A and Train B. ] 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

-----------------------------------------------------------NOTE------------------------------------------------------------ 

LCO 3.0.4.b is not applicable to DGs. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One [required] offsite 

circuit inoperable. 

A.1 Perform SR 3.8.1.1 for 

[required] OPERABLE 

offsite circuit. 

AND

A.2 Declare required feature(s) 

with no offsite power 

available inoperable when 

its redundant required 

feature(s) is inoperable. 

AND

1 hour 

AND

Once per 8 hours 

thereafter 

24 hours from 

discovery of no offsite 

power to one train 

concurrent with 

inoperability of 

redundant required 

feature(s) 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.3 Restore [required] offsite 

circuit to OPERABLE 

status. 

72 hours 

AND

6 days from discovery 

of failure to meet LCO 

B. One [required] DG 

inoperable. 

B.1 Perform SR 3.8.1.1 for the 

OPERABLE [required] 

offsite circuit(s). 

AND

B.2 Declare required feature(s) 

supported by the inoperable 

DG inoperable when its 

redundant required 

feature(s) is inoperable. 

AND

B.3.1 Determine OPERABLE 

DG(s) is not inoperable due 

to common cause failure. 

 OR

B.3.2 Perform SR 3.8.1.2 for 

OPERABLE DG(s). 

AND

1 hour 

AND

Once per 8 hours 

thereafter 

4 hours from 

discovery of 

Condition B 

concurrent with 

inoperability of 

redundant required 

feature(s) 

[24] hours 

[24] hours 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.4 Restore [required] DG to 

OPERABLE status. 

72 hours 

AND

6 days from discovery 

of failure to meet LCO 

C. Two [required] offsite 

circuits inoperable. 

C.1 Declare required feature(s) 

inoperable when its 

redundant required 

feature(s) is inoperable. 

AND

C.2 Restore one [required] 

offsite circuit to OPERABLE 

status. 

12 hours from 

discovery of 

Condition C 

concurrent with 

inoperability of 

redundant required 

feature(s) 

24 hours 

D. One [required] offsite 

circuit inoperable. 

 AND

 One [required] DG 

inoperable. 

--------------------NOTE------------------- 

Enter applicable Conditions and 

Required Actions of LCO 3.8.9, 

"Distribution Systems - Operating," 

when Condition D is entered with no 

AC power source to any train. 

------------------------------------------------ 

D.1 Restore [required] offsite 

circuits to OPERABLE 

status. 

OR

D.2 Restore [required] DG to 

OPERABLE status. 

12 hours 

12 hours 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-4 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

E. Two [required] DGs 

inoperable. 

E.1 Restore one [required] DG 

to OPERABLE status. 

2 hours 

F. ------------NOTE------------ 

 [ This Condition may be 

deleted if the unit design 

is such that any 

sequencer failure mode 

will only affect the ability 

of the associated DG to 

power its respective 

safety loads following a 

loss of offsite power 

independent of, or 

coincident with, a Design 

Basis Event. 

--------------------------------- 

 One [required] 

[automatic load 

sequencer] inoperable. 

F.1 Restore [required] 

[automatic load sequencer] 

to OPERABLE status. 

[12] hours ] 

G. Required Action and 

associated Completion 

Time of Condition A, B, 

C, D, E, or [F] not met. 

G.1 Be in MODE 3. 

AND

G.2 Be in MODE 5. 

6 hours 

36 hours 

H. Three or more [required] 

AC sources inoperable. 

H.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.1.1 Verify correct breaker alignment and indicated 

power availability for each [required] offsite circuit. 

7 days 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-5 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.2 ------------------------------NOTES----------------------------- 

 1. All DG starts may be preceded by an engine 

prelube period and followed by a warmup 

period prior to loading. 

 2. [ A modified DG start involving idling and 

gradual acceleration to synchronous speed may 

be used for this SR as recommended by the 

manufacturer. When modified start procedures 

are not used, the time, voltage, and frequency 

tolerances of SR 3.8.1.7 must be met. ] 

 --------------------------------------------------------------------- 

 Verify each DG starts from standby conditions and 

achieves steady state voltage ≥ [3740] V and 

≤ [4580] V, and frequency ≥ [58.8] Hz and 

≤ [61.2] Hz. 

31 days 

SR 3.8.1.3 ------------------------------NOTES----------------------------- 

 1. DG loadings may include gradual loading as 

recommended by the manufacturer. 

 2. Momentary transients outside the load range do 

not invalidate this test. 

 3. This Surveillance shall be conducted on only 

one DG at a time. 

 4. This SR shall be preceded by and immediately 

follow without shutdown a successful 

performance of SR 3.8.1.2 or SR 3.8.1.7. 

 --------------------------------------------------------------------- 

 Verify each DG is synchronized and loaded, and 

operates for ≥ 60 minutes at a load ≥ [4500] kW and 

≤ [5000] kW. 

31 days 

SR 3.8.1.4 Verify each day tank [and engine mounted tank] 

contains ≥ [220] gal of fuel oil. 

31 days 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-6 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.5 Check for and remove accumulated water from each 

day tank [and engine mounted tank]. 

[31] days 

SR 3.8.1.6 Verify the fuel oil transfer system operates to 

[automatically] transfer fuel oil from storage tank[s] 

to the day tank [and engine mounted tank]. 

[92] days 

SR 3.8.1.7 -------------------------------NOTE------------------------------ 

 All DG starts may be preceded by an engine prelube 

period. 

 --------------------------------------------------------------------- 

 Verify each DG starts from standby condition and 

achieves: 

 a. In ≤ [10] seconds, voltage ≥ [3740] V and 

frequency ≥ [58.8] Hz and 

 b. Steady state voltage ≥ [3740] V and ≤ [4580] V, 

and frequency ≥ [58.8] Hz and ≤ [61.2] Hz. 

184 days 

SR 3.8.1.8 -------------------------------NOTE------------------------------ 

 [ This Surveillance shall not normally be performed 

in MODE 1 or 2. However, this Surveillance may be 

performed to reestablish OPERABILITY provided an 

assessment determines the safety of the plant is 

maintained or enhanced. Credit may be taken for 

unplanned events that satisfy this SR. ] 

 --------------------------------------------------------------------- 

 [ Verify [automatic [and] manual] transfer of AC 

power sources from the normal offsite circuit to each 

alternate [required] offsite circuit. 

[18] months ] 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-7 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.9 ------------------------------NOTES----------------------------- 

 1. [ This Surveillance shall not normally be 

performed in MODE 1 or 2. However, this 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment 

determines the safety of the plant is maintained 

or enhanced. Credit may be taken for 

unplanned events that satisfy this SR. 

 2. If performed with the DG synchronized with 

offsite power, it shall be performed at a power 

factor ≤ [0.9]. However, if grid conditions do not 

permit, the power factor limit is not required to 

be met. Under this condition the power factor 

shall be maintained as close to the limit as 

practicable. ] 

 --------------------------------------------------------------------- 

 Verify each DG rejects a load greater than or equal 

to its associated single largest post-accident load 

and: 

 a. Following load rejection, the frequency is 

≤ [63] Hz, 

 b. Within [3] seconds following load rejection, the 

voltage is ≥ [3740] V and ≤ [4580] V, and 

 c. Within [3] seconds following load rejection, the 

frequency is ≥ [58.8] Hz and ≤ [61.2] Hz. 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-8 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.10 ------------------------------NOTES----------------------------- 

 1. [ This Surveillance shall not normally be 

performed in MODE 1 or 2. However, this 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment 

determines the safety of the plant is maintained 

or enhanced. Credit may be taken for 

unplanned events that satisfy this SR. 

 2. If performed with DG synchronized with offsite 

power, it shall be performed at a power factor 

≤ [0.9]. However, if grid conditions do not 

permit, the power factor limit is not required to 

be met. Under this condition the power factor 

shall be maintained as close to the limit as 

practicable. ] 

 --------------------------------------------------------------------- 

 Verify each DG does not trip, and voltage is 

maintained ≤ [5000] V during and following a load 

rejection of ≥ [4500] kW and ≤ [5000] kW. 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-9 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.11 ------------------------------NOTES----------------------------- 

 1. All DG starts may be preceded by an engine 

prelube period. 

 2. This Surveillance shall not normally be 

performed in MODE 1, 2, 3, or 4. However, 

portions of the Surveillance may be performed 

to reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR. 

 --------------------------------------------------------------------- 

 Verify on an actual or simulated loss of offsite power 

signal: 

 a. De-energization of emergency buses, 

 b. Load shedding from emergency buses, 

 c. DG auto-starts from standby condition and: 

 1. Energizes permanently connected loads 

in ≤ [10] seconds, 

 2. Energizes auto-connected shutdown 

loads through [automatic load sequencer], 

 3. Maintains steady state voltage ≥ [3740] V 

and ≤ [4580] V, 

 4. Maintains steady state frequency 

≥ [58.8] Hz and ≤ [61.2] Hz, and 

 5. Supplies permanently connected [and 

auto-connected] shutdown loads for 

≥ 5 minutes. 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-10 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.12 ------------------------------NOTES----------------------------- 

 1. [ All DG starts may be preceded by an engine 

prelube period. 

 2. This Surveillance shall not normally be 

performed in MODE 1 or 2. However, portions 

of the Surveillance may be performed to 

reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR. 

 --------------------------------------------------------------------- 

 Verify on an actual or simulated Engineered Safety 

Feature (ESF) actuation signal each DG auto-starts 

from standby condition and: 

 a. In ≤ [10] seconds after auto-start and during 

tests, achieves voltage ≥ [3740] V and 

frequency ≥ [58.8] Hz, 

 b. Achieves steady state voltage ≥ [3740] V and 

≤ [4580] V and frequency ≥ [58.8] Hz and 

≤ [61.2] Hz, 

 c. Operates for ≥ 5 minutes, 

 d. Permanently connected loads remain energized 

from the offsite power system, and 

 e. Emergency loads are energized [or autoconnected through the automatic load 

sequencer] from the offsite power system. 

[18] months ] 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-11 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.13 -------------------------------NOTE------------------------------ 

 [ This Surveillance shall not normally be performed 

in MODE 1 or 2. However, this Surveillance may be 

performed to reestablish OPERABILITY provided an 

assessment determines the safety of the plant is 

maintained or enhanced. Credit may be taken for 

unplanned events that satisfy this SR. ] 

 --------------------------------------------------------------------- 

 Verify each DG automatic trip is bypassed on [actual 

or simulated loss of voltage signal on the 

emergency bus concurrent with an actual or 

simulated ESF actuation signal] except: 

 a. Engine overspeed, 

 b. Generator differential current, 

 [ c. Low lube oil pressure, 

 d. High crankcase pressure, and 

 e. Start failure relay. ] 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-12 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.14 ------------------------------NOTES----------------------------- 

 1. Momentary transients outside the load and 

power factor ranges do not invalidate this test. 

 2. This Surveillance shall not normally be 

performed in MODE 1 or 2. However, this 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment 

determines the safety of the plant is maintained 

or enhanced. Credit may be taken for 

unplanned events that satisfy this SR. 

 3. If performed with DG synchronized with offsite 

power, it shall be performed at a power factor 

≤ [0.9]. However, if grid conditions do not 

permit, the power factor limit is not required to 

be met. Under this condition the power factor 

shall be maintained as close to the limit as 

practicable. 

 --------------------------------------------------------------------- 

 Verify each DG operates for ≥ 24 hours: 

 a. For ≥ [2] hours loaded ≥ [5250] kW and 

≤ [5500] kW and 

 b. For the remaining hours of the test loaded 

≥ [4500] kW and ≤ [5000] kW. 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-13 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.15 ------------------------------NOTES----------------------------- 

 1. This Surveillance shall be performed within 

5 minutes of shutting down the DG after the DG 

has operated ≥ [2] hours loaded ≥ [4500] kW 

and ≤ [5000] kW. 

 Momentary transients outside of load range do 

not invalidate this test. 

 2. All DG starts may be preceded by an engine 

prelube period. 

 --------------------------------------------------------------------- 

 Verify each DG starts and achieves: 

 a. In ≤ [10] seconds, voltage ≥ [3740] V and 

frequency ≥ [58.8] Hz and 

 b. Steady state voltage ≥ [3740] V and ≤ [4580] V, 

and frequency ≥ [58.8] Hz and ≤ [61.2] Hz. 

[18] months 

SR 3.8.1.16 -------------------------------NOTE------------------------------ 

 This Surveillance shall not normally be performed in 

MODE 1, 2, 3, or 4. However, this Surveillance may 

be performed to reestablish OPERABILITY provided 

an assessment determines the safety of the plant is 

maintained or enhanced. Credit may be taken for 

unplanned events that satisfy this SR. 

 --------------------------------------------------------------------- 

 Verify each DG: 

 a. Synchronizes with offsite power source while 

loaded with emergency loads upon a simulated 

restoration of offsite power, 

 b. Transfers loads to offsite power source, and 

 c. Returns to ready-to-load operation. 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-14 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.17 -------------------------------NOTE------------------------------ 

 [ This Surveillance shall not normally be performed 

in MODE 1, 2, 3, or 4. However, portions of the 

Surveillance may be performed to reestablish 

OPERABILITY provided an assessment determines 

the safety of the plant is maintained or enhanced. 

Credit may be taken for unplanned events that 

satisfy this SR. 

 --------------------------------------------------------------------- 

 Verify, with a DG operating in test mode and 

connected to its bus, an actual or simulated ESF 

actuation signal overrides the test mode by: 

 a. Returning DG to ready-to-load operation and 

 [ b. Automatically energizing the emergency load 

from offsite power. ] 

[18] months ] 

SR 3.8.1.18 -------------------------------NOTE------------------------------ 

 [ This Surveillance shall not normally be performed 

in MODE 1, 2, 3, or 4. However, this Surveillance 

may be performed to reestablish OPERABILITY 

provided an assessment determines the safety of 

the plant is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR. ] 

 --------------------------------------------------------------------- 

 Verify interval between each sequenced load block 

is within ± [10% of design interval] for each 

emergency [and shutdown] load sequencer. 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-15 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.19 ------------------------------NOTES----------------------------- 

 1. All DG starts may be preceded by an engine 

prelube period. 

 2. This Surveillance shall not normally be 

performed in MODE 1, 2, 3, or 4. However, 

portions of the Surveillance may be performed 

to reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR. 

 --------------------------------------------------------------------- 

 Verify on an actual or simulated loss of offsite power 

signal in conjunction with an actual or simulated 

ESF actuation signal: 

 a. De-energization of emergency buses, 

 b. Load shedding from emergency buses, 

 c. DG auto-starts from standby condition and: 

 1. energizes permanently connected loads 

in ≤ [10] seconds, 

 2. energizes auto-connected emergency 

loads through [load sequencer], 

 3. achieves steady state voltage ≥ [3740] V 

and ≤ [4580] V, 

 4. achieves steady state frequency 

≥ [58.8] Hz and ≤ [61.2] Hz, and 

 5. supplies permanently connected [and 

auto-connected] emergency loads for 

≥ [5] minutes. 

[18] months 
AC Sources - Operating 

3.8.1 

CEOG STS 3.8.1-16 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.1.20 -------------------------------NOTE------------------------------ 

 All DG starts may be preceded by an engine prelube 

period. 

 --------------------------------------------------------------------- 

 Verify, when started simultaneously from standby 

condition, each DG achieves: 

 a. In ≤ [10] seconds, voltage ≥ [3740] V and 

frequency ≥ [58.8] Hz and 

 b. Steady state voltage ≥ [3740] V and ≤ [4580] V, 

and frequency ≥ [58.8] Hz and ≤ [61.2] Hz. 

10 years 
AC Sources - Shutdown 

3.8.2 

CEOG STS 3.8.2-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.2 AC Sources - Shutdown 

LCO 3.8.2 The following AC electrical power sources shall be OPERABLE: 

 a. One qualified circuit between the offsite transmission network and 

the onsite Class 1E AC electrical power distribution subsystem(s) 

required by LCO 3.8.10, "Distribution Systems Shutdown" and 

 b. One diesel generator (DG) capable of supplying one train of the 

onsite Class 1E AC electrical power distribution subsystem(s) 

required by LCO 3.8.10. 

APPLICABILITY: MODES 5 and 6, 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One required offsite 

circuit inoperable. 

--------------------NOTE------------------- 

Enter applicable Conditions and 

Required Actions of LCO 3.8.10, 

with one required train de-energized 

as a result of Condition A. 

------------------------------------------------ 

A.1 Declare affected required 

feature(s) with no offsite 

power available inoperable. 

OR

Immediately 
AC Sources - Shutdown 

3.8.2 

CEOG STS 3.8.2-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.2.1 Suspend CORE 

ALTERATIONS. 

 AND

A.2.2 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

 AND

A.2.3 Suspend operations 

involving positive reactivity 

additions that could result in 

a loss of required SDM or 

boron concentration. 

 AND

A.2.4 Initiate action to restore 

required offsite power 

circuit to OPERABLE 

status. 

Immediately 

Immediately 

Immediately 

Immediately 

B. One required DG 

inoperable. 

B.1 Suspend CORE 

ALTERATIONS. 

AND

B.2 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

AND

B.3 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration. 

AND

Immediately 

Immediately 

Immediately 
AC Sources - Shutdown 

3.8.2 

CEOG STS 3.8.2-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B.4 Initiate action to restore 

required DG to OPERABLE 

status. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.2.1 ------------------------------NOTE------------------------------ 

The following SRs are not required to be performed: 

SR 3.8.1.3, SR 3.8.1.9 through SR 3.8.1.11, 

SR 3.8.1.13 through SR 3.8.1.16, and 

[SR 3.8.1.18]. 

 --------------------------------------------------------------------- 

 For AC sources required to be OPERABLE, the SRs 

of Specification 3.8.1, "AC Sources - Operating," 

except SR 3.8.1.8, SR 3.8.1.12, SR 3.8.1.17, 

SR 3.8.1.19, and SR 3.8.1.20, are applicable. 

In accordance 

with applicable 

SRs 
Diesel Fuel Oil, Lube Oil, and Starting Air 

3.8.3 

CEOG STS 3.8.3-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 

LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be 

within limits for each required diesel generator (DG). 

APPLICABILITY: When associated DG is required to be OPERABLE. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each DG. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more DGs with 

fuel level < [33,000] gal 

and > [28,285] gal in 

storage tank. 

A.1 Restore fuel oil level to 

within limits. 

48 hours 

B. One or more DGs with 

lube oil inventory 

< [500] gal and 

> [425] gal. 

B.1 Restore lube oil inventory to 

within limits. 

48 hours 

C. One or more DGs with 

stored fuel oil total 

particulates not within 

limits. 

C.1 Restore fuel oil total 

particulates to within limits. 

7 days 

D. One or more DGs with 

new fuel oil properties 

not within limits. 

D.1 Restore stored fuel oil 

properties to within limits. 

30 days 

E. One or more DGs with 

starting air receiver 

pressure < [225] psig 

and ≥ [125] psig. 

E.1 Restore starting air receiver 

pressure to ≥ [225] psig. 

48 hours 
Diesel Fuel Oil, Lube Oil, and Starting Air 

3.8.3 

CEOG STS 3.8.3-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

F. Required Action and 

associated Completion 

Time not met. 

 OR

 One or more DGs with 

diesel fuel oil, lube oil, or 

starting air subsystem 

not within limits for 

reasons other than 

Condition A, B, C, D, 

or E. 

F.1 Declare associated DG 

inoperable. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.3.1 Verify each fuel oil storage tank contains 

≥ [33,000] gal of fuel. 

31 days 

SR 3.8.3.2 Verify lubricating oil inventory is ≥ [500] gal. 31 days 

SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil 

are tested in accordance with, and maintained within 

the limits of, the Diesel Fuel Oil Testing Program. 

In accordance 

with the Diesel 

Fuel Oil Testing 

Program 

SR 3.8.3.4 Verify each DG air start receiver pressure is 

≥ [225] psig. 

31 days 

SR 3.8.3.5 Check for and remove accumulated water from each 

fuel oil storage tank. 

[31] days 
DC Sources - Operating 

3.8.4 

CEOG STS 3.8.4-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.4 DC Sources - Operating 

LCO 3.8.4 The Train A and Train B DC electrical power subsystems shall be 

OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One [or two] battery 

charger[s on one train] 

inoperable. 

A.1 Restore battery terminal 

voltage to greater than or 

equal to the minimum 

established float voltage. 

AND

A.2 Verify battery float current 

≤ [2] amps. 

AND

A.3 Restore battery charger[s] 

to OPERABLE status. 

2 hours 

Once per [12] hours 

7 days 

B. One [or two] batter[y][ies 

on one train] inoperable. 

B.1 Restore batter[y][ies] to 

OPERABLE status. 

[2] hours] 

C. One DC electrical power 

subsystem inoperable 

for reasons other than 

Condition A [or B]. 

C.1 Restore DC electrical 

power subsystem to 

OPERABLE status. 

[2] hours 

D. Required Action and 

Associated Completion 

Time not met. 

D.1 Be in MODE 3. 

AND

D.2 Be in MODE 5. 

6 hours 

36 hours 
DC Sources - Operating 

3.8.4 

CEOG STS 3.8.4-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.4.1 Verify battery terminal voltage is greater than or 

equal to the minimum established float voltage. 

7 days 

SR 3.8.4.2 Verify each battery charger supplies ≥ [400] amps at 

greater than or equal to the minimum established 

float voltage for ≥ [8] hours. 

 OR

 Verify each battery charger can recharge the battery 

to the fully charged state within [24] hours while 

supplying the largest combined demands of the 

various continuous steady state loads, after a 

battery discharge to the bounding design basis 

event discharge state. 

[18] months 

SR 3.8.4.3 ------------------------------NOTES----------------------------- 

 1. The modified performance discharge test in 

SR 3.8.6.6 may be performed in lieu of 

SR 3.8.4.3. 

 2. This Surveillance shall not normally be 

performed in MODE 1, 2, 3, or 4. However, 

portions of the Surveillance may be performed 

to reestablish OPERABILITY provided an 

assessment determines the safety of the plant 

is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR. 

 --------------------------------------------------------------------- 

 Verify battery capacity is adequate to supply, and 

maintain in OPERABLE status, the required 

emergency loads for the design duty cycle when 

subjected to a battery service test. 

[18] months 
DC Sources - Shutdown 

3.8.5 

CEOG STS 3.8.5-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.5 DC Sources - Shutdown 

LCO 3.8.5 [DC electrical power subsystem shall be OPERABLE to support the DC 

electrical power distribution subsystem(s) required by LCO 3.8.10, 

"Distribution Systems - Shutdown."] 

 [One DC electrical power subsystem shall be OPERABLE.] 

 -----------------------------------REVIEWER’S NOTE----------------------------------- 

 This second option above applies for plants having a pre-ITS licensing 

basis (CTS) for electrical power requirements during shutdown conditions 

that required only one DC electrical power subsystem to be OPERABLE. 

Action A and the bracketed optional wording in Condition B are also 

eliminated for this case. The first option above is adopted for plants that 

have a CTS requiring the same level of DC electrical power subsystem 

support as is required for power operating conditions. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 5 and 6, 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

[ A. One [or two] battery 

charger[s on one train] 

inoperable. 

 AND

 The redundant train 

battery and charger[s] 

OPERABLE. 

A.1 Restore battery terminal 

voltage to greater than or 

equal to the minimum 

established float voltage. 

AND

A.2 Verify battery float current 

≤ [2] amps. 

AND

2 hours 

Once per [12] hours 
DC Sources - Shutdown 

3.8.5 

CEOG STS 3.8.5-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.3 Restore battery charger[s] 

to OPERABLE status. 

7 days ] 

B. One [or more] required 

DC electrical power 

subsystem[s] inoperable 

[for reasons other than 

Condition A. 

 OR

 Required Action and 

associated Completion 

Time of Condition A not 

met]. 

B.1 Declare affected required 

feature(s) inoperable. 

OR

B.2.1 Suspend CORE 

ALTERATIONS. 

 AND

B.2.2 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

 AND

B.2.3 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration. 

 AND

B.2.4 Initiate action to restore 

required DC electrical 

power subsystems to 

OPERABLE status. 

Immediately 

Immediately 

Immediately 

Immediately 

Immediately 
DC Sources - Shutdown 

3.8.5 

CEOG STS 3.8.5-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.5.1 -------------------------------NOTE------------------------------ 

 The following SRs are not required to be performed: 

SR 3.8.4.2 and SR 3.8.4.3. 

 --------------------------------------------------------------------- 

 For DC sources required to be OPERABLE, the 

following SRs are applicable: 

 SR 3.8.4.1 

 SR 3.8.4.2 

 SR 3.8.4.3 

In accordance 

with applicable 

SRs 
Battery Parameters 

3.8.6 

CEOG STS 3.8.6-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.6 Battery Parameters 

--------------------------------------------------REVIEWER'S NOTE------------------------------------------------- 

Licensees must implement a program, as specified in Specification 5.5.17, to monitor battery 

parameters that is based on the recommendations of IEEE Standard 450-1995, "IEEE 

Recommended Practice For Maintenance, Testing, And Replacement Of Vented Lead-Acid 

Batteries For Stationary Applications." 

-------------------------------------------------------------------------------------------------------------------------------

LCO 3.8.6 Battery parameters for the Train A and Train B batteries shall be within 

limits. 

APPLICABILITY: When associated DC electrical power subsystems are required to be 

OPERABLE. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

Separate Condition entry is allowed for each battery. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One [or two] batter[y][ies 

on one train] with one or 

more battery cells float 

voltage < [2.07] V. 

A.1 Perform SR 3.8.4.1. 

AND

A.2 Perform SR 3.8.6.1. 

AND

A.3 Restore affected cell 

voltage ≥ [2.07] V. 

2 hours 

2 hours 

24 hours 

B. One [or two] batter[y][ies 

on one train] with float 

current > [2] amps. 

B.1 Perform SR 3.8.4.1. 

AND

B.2 Restore battery float current 

to ≤ [2] amps. 

2 hours 

[12] hours 
Battery Parameters 

3.8.6 

CEOG STS 3.8.6-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

---------------NOTE-------------- 

Required Action C.2 shall be 

completed if electrolyte level 

was below the top of plates. 

-------------------------------------- 

C. One [or two] batter[y][ies 

on one train] with one or 

more cells electrolyte 

level less than minimum 

established design 

limits. 

--------------------NOTE------------------- 

Required Actions C.1 and C.2 are 

only applicable if electrolyte level 

was below the top of plates. 

------------------------------------------------ 

C.1 Restore electrolyte level to 

above top of plates. 

AND

C.2 Verify no evidence of 

leakage. 

AND

C.3 Restore electrolyte level to 

greater than or equal to 

minimum established 

design limits. 

8 hours 

12 hours 

31 days 

D. One [or two] batter[y][ies 

on one train] with pilot 

cell electrolyte 

temperature less than 

minimum established 

design limits. 

D.1 Restore battery pilot cell 

temperature to greater than 

or equal to minimum 

established design limits. 

12 hours 

E. One or more batteries in 

redundant trains with 

battery parameters not 

within limits. 

E.1 Restore battery parameters 

for batteries in one train to 

within limits. 

2 hours 
Battery Parameters 

3.8.6 

CEOG STS 3.8.6-3 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

F. Required Action and 

associated Completion 

Time of Condition A, B, 

C, D, or E not met. 

 OR

 One [or two] batter[y][ies 

on one train] with one or 

more battery cells float 

voltage < [2.07] V and 

float current > [2] amps. 

F.1 Declare associated battery 

inoperable. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.6.1 -------------------------------NOTE------------------------------ 

 Not required to be met when battery terminal 

voltage is less than the minimum established float 

voltage of SR 3.8.4.1. 

 --------------------------------------------------------------------- 

 Verify each battery float current is ≤ [2] amps. 7 days 

SR 3.8.6.2 Verify each battery pilot cell voltage is ≥ [2.07] V. 31 days 

SR 3.8.6.3 Verify each battery connected cell electrolyte level is 

greater than or equal to minimum established 

design limits. 

31 days 

SR 3.8.6.4 Verify each battery pilot cell temperature is greater 

than or equal to minimum established design limits. 

31 days 
Battery Parameters 

3.8.6 

CEOG STS 3.8.6-4 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.8.6.5 Verify each battery connected cell voltage is 

≥ [2.07] V. 

92 days 

SR 3.8.6.6 -------------------------------NOTE------------------------------ 

 This Surveillance shall not be performed in MODE 

1, 2, 3, or 4. However, portions of this Surveillance 

may be performed to reestablish OPERABILITY 

provided an assessment determines the safety of 

the plant is maintained or enhanced. Credit may be 

taken for unplanned events that satisfy this SR. 

 --------------------------------------------------------------------- 

 Verify battery capacity is ≥ [80%] of the 

manufacturer's rating when subjected to a 

performance discharge test or a modified 

performance discharge test. 

60 months 

AND

12 months when 

battery shows 

degradation, or 

has reached 

[85]% of the 

expected life with 

capacity < 100% 

of manufacturer's 

rating 

AND

24 months when 

battery has 

reached [85]% of 

the expected life 

with capacity 

≥ 100% of 

manufacturer's 

rating 
Inverters - Operating 

3.8.7 

CEOG STS 3.8.7-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.7 Inverters - Operating 

LCO 3.8.7 The required Train A and Train B inverters shall be OPERABLE. 

 ---------------------------------------------NOTE-------------------------------------------- 

 [ [One/two] inverter[s] may be disconnected from [its/their] associated DC 

bus for ≤ 24 hours to perform an equalizing charge on [its/their] 

associated [common] battery, provided: 

 a. The associated AC vital bus(es) [is/are] energized from [its/their] 

[Class 1E constant voltage source transformers] [inverter using 

internal AC source] and 

 b. All other AC vital buses are energized from their associated 

OPERABLE inverters. ] 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One [required] inverter 

inoperable. 

A.1 ---------------NOTE-------------- 

 Enter applicable Conditions 

and Required Actions of 

LCO 3.8.9, "Distribution 

Systems – Operating," with 

any vital bus de-energized. 

 ------------------------------------- 

 Restore inverter to 

OPERABLE status. 

24 hours 

B. Required Action and 

associated Completion 

Time not met. 

B.1 Be in MODE 3. 

AND

B.2 Be in MODE 5. 

6 hours 

36 hours 
Inverters - Operating 

3.8.7 

CEOG STS 3.8.7-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.7.1 Verify correct inverter voltage, [frequency,] and 

alignment to required AC vital buses. 

7 days 
Inverters - Shutdown 

3.8.8 

CEOG STS 3.8.8-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.8 Inverters - Shutdown 

LCO 3.8.8 [Inverter(s) shall be OPERABLE to support the onsite Class 1E AC vital 

bus electrical power distribution subsystem(s) required by LCO 3.8.10, 

"Distribution Systems - Shutdown."] 

 [One] inverter[s] shall be OPERABLE.] 

 ------------------------------------REVIEWER’S NOTE---------------------------------- 

 This second option above applies for plants having a pre-ITS licensing 

basis (CTS) for electrical power requirements during shutdown conditions 

that required only [one] inverter to be OPERABLE. The "[or more]" 

optional wording in Condition A is also eliminated for this case. The first 

option above is adopted for plants that have a CTS requiring the same 

level of DC electrical power subsystem/inverter support as is required for 

power operating conditions. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODES 5 and 6, 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One [or more] [required] 

inverter[s] inoperable. 

A.1 Declare affected required 

feature(s) inoperable. 

OR

A.2.1 Suspend CORE 

ALTERATIONS. 

 AND

Immediately 

Immediately 
Inverters - Shutdown 

3.8.8 

CEOG STS 3.8.8-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.2.2 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

 AND

A.2.3 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration. 

 AND

A.2.4 Initiate action to restore 

required inverters to 

OPERABLE status. 

Immediately 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.8.1 Verify correct inverter voltage, [frequency,] and 

alignments to required AC vital buses. 

7 days 
Distribution Systems - Operating 

3.8.9 

CEOG STS 3.8.9-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.9 Distribution Systems - Operating 

LCO 3.8.9 Train A and Train B AC, DC, and AC vital bus electrical power distribution 

subsystems shall be OPERABLE. 

APPLICABILITY: MODES 1, 2, 3, and 4. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more AC 

electrical power 

distribution subsystems 

inoperable. 

--------------------NOTE------------------- 

Enter applicable Conditions and 

Required Actions of LCO 3.8.4, "DC 

Sources - Operating," for DC trains 

made inoperable by inoperable 

power distribution subsystems. 

------------------------------------------------ 

A.1 Restore AC electrical power 

distribution subsystem(s) to 

OPERABLE status. 

8 hours 

AND

16 hours from 

discovery of failure to 

meet LCO 

B. One or more AC vital 

buses inoperable. 

B.1 Restore AC vital bus 

subsystem(s) to 

OPERABLE status. 

2 hours 

AND

16 hours from 

discovery of failure to 

meet LCO 
Distribution Systems - Operating 

3.8.9 

CEOG STS 3.8.9-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

C. One or more 

DC electrical power 

distribution subsystems 

inoperable. 

C.1 Restore DC electrical 

power distribution 

subsystem(s) to 

OPERABLE status. 

2 hours 

AND

16 hours from 

discovery of failure to 

meet LCO 

D. Required Action and 

associated Completion 

Time not met. 

D.1 Be in MODE 3. 

AND

D.2 Be in MODE 5. 

6 hours 

36 hours 

E. Two or more electrical 

power distribution 

subsystems inoperable 

that result in a loss of 

safety function. 

E.1 Enter LCO 3.0.3. Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.9.1 Verify correct breaker alignments and voltage to 

[required] AC, DC, and AC vital bus electrical power 

distribution subsystems. 

7 days 
Distribution Systems - Shutdown 

3.8.10 

CEOG STS 3.8.10-1 Rev. 3.0, 03/31/04 

3.8 ELECTRICAL POWER SYSTEMS 

3.8.10 Distribution Systems - Shutdown 

LCO 3.8.10 The necessary portion of AC, DC, and AC vital bus electrical power 

distribution subsystems shall be OPERABLE to support equipment 

required to be OPERABLE. 

APPLICABILITY: MODES 5 and 6, 

 During movement of [recently] irradiated fuel assemblies. 

ACTIONS 

------------------------------------------------------------NOTE----------------------------------------------------------- 

LCO 3.0.3 is not applicable. 

-------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more required 

AC, DC, or AC vital bus 

electrical power 

distribution subsystems 

inoperable. 

A.1 Declare associated 

supported required 

feature(s) inoperable. 

OR

A.2.1 Suspend CORE 

ALTERATIONS. 

 AND

A.2.2 Suspend movement of 

[recently] irradiated fuel 

assemblies. 

 AND

A.2.3 Suspend operations 

involving positive reactivity 

additions that could result in 

loss of required SDM or 

boron concentration. 

 AND

Immediately 

Immediately 

Immediately 

Immediately 
Distribution Systems - Shutdown 

3.8.10 

CEOG STS 3.8.10-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.2.4 Initiate actions to restore 

required AC, DC, and AC 

vital bus electrical power 

distribution subsystems to 

OPERABLE status. 

 AND

A.2.5 Declare associated 

required shutdown cooling 

subsystem(s) inoperable 

and not in operation. 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.8.10.1 Verify correct breaker alignments and voltage to 

required AC, DC, and AC vital bus electrical power 

distribution subsystems. 

7 days 
Boron Concentration 

3.9.1 

CEOG STS 3.9.1-1 Rev. 3.0, 03/31/04 

3.9 REFUELING OPERATIONS 

3.9.1 Boron Concentration 

LCO 3.9.1 Boron concentrations of the Reactor Coolant System, [the refueling canal, 

and the refueling cavity] shall be maintained within the limit specified in 

the COLR. 

APPLICABILITY: MODE 6. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Only applicable to the refueling canal and refueling cavity when 

connected to the RCS. 

 -------------------------------------------------------------------------------------------------- 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Boron concentration not 

within limit. 

A.1 Suspend CORE 

ALTERATIONS. 

AND

A.2 Suspend positive reactivity 

additions. 

AND

A.3 Initiate action to restore 

boron concentration to 

within limit. 

Immediately 

Immediately 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.9.1.1 Verify boron concentration is within the limit 

specified in the COLR. 

72 hours 
Nuclear Instrumentation 

3.9.2 

CEOG STS 3.9.2-1 Rev. 3.0, 03/31/04 

3.9 REFUELING OPERATIONS 

3.9.2 Nuclear Instrumentation 

LCO 3.9.2 Two source range monitors (SRMs) shall be OPERABLE. 

APPLICABILITY: MODE 6. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One [required] SRM 

inoperable. 

A.1 Suspend CORE 

ALTERATIONS. 

AND

A.2 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet the 

boron concentration of 

LCO 3.9.1. 

Immediately 

Immediately 

B. Two [required] SRMs 

inoperable. 

B.1 Initiate action to restore one 

SRM to OPERABLE status. 

AND

B.2 Perform SR 3.9.1.1. 

Immediately 

Once per 12 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.9.2.1 Perform CHANNEL CHECK. 12 hours 
Nuclear Instrumentation 

3.9.2 

CEOG STS 3.9.2-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS (continued) 

SURVEILLANCE FREQUENCY 

SR 3.9.2.2 -------------------------------NOTE------------------------------ 

 Neutron detectors are excluded from CHANNEL 

CALIBRATION. 

 --------------------------------------------------------------------- 

 Perform CHANNEL CALIBRATION. [18] months 
Containment Penetrations 

3.9.3 

CEOG STS 3.9.3-1 Rev. 3.0, 03/31/04 

3.9 REFUELING OPERATIONS 

3.9.3 Containment Penetrations 

LCO 3.9.3 The containment penetrations shall be in the following status: 

 a. The equipment hatch closed and held in place by [four] bolts, 

 b. One door in each air lock is [capable of being] closed, and 

 c. Each penetration providing direct access from the containment 

atmosphere to the outside atmosphere either: 

 1. Closed by a manual or automatic isolation valve, blind flange, 

or equivalent or 

 2. Capable of being closed by an OPERABLE Containment 

Purge and Exhaust Isolation System. 

 ---------------------------------------------NOTE-------------------------------------------- 

 Penetration flow path(s) providing direct access from the containment 

atmosphere to the outside atmosphere may be unisolated under 

administrative controls. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: During movement of [recently] irradiated fuel assemblies within 

containment. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One or more 

containment 

penetrations not in 

required status. 

A.1 Suspend movement of 

[recently] irradiated fuel 

assemblies within 

containment. 

Immediately 
Containment Penetrations 

3.9.3 

CEOG STS 3.9.3-2 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.9.3.1 Verify each required containment penetration is in 

the required status. 

7 days 

SR 3.9.3.2 -------------------------------NOTE------------------------------ 

 Not required to be met for containment purge and 

exhaust valve(s) in penetrations closed to comply 

with LCO 3.9.3.c.1. 

 --------------------------------------------------------------------- 

 Verify each required containment purge and 

exhaust valve actuates to the isolation position on 

an actual or simulated actuation signal. 

[18] months 
SDC and Coolant Circulation - High Water Level 

3.9.4 

CEOG STS 3.9.4-1 Rev. 3.0, 03/31/04 

3.9 REFUELING OPERATIONS 

3.9.4 Shutdown Cooling (SDC) and Coolant Circulation - High Water Level 

LCO 3.9.4 One SDC loop shall be OPERABLE and in operation. 

 ---------------------------------------------NOTE-------------------------------------------- 

 The required SDC loop may be removed from operation for ≤ 1 hour per 

[8] hour period, provided no operations are permitted that would cause 

introduction of coolant into the Reactor Coolant System with boron 

concentration less than that required to meet the minimum required boron 

concentration of LCO 3.9.1. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 6 with the water level ≥ 23 ft above the top of reactor vessel 

flange. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One required SDC loop 

inoperable or not in 

operation. 

A.1 Initiate action to restore 

SDC loop to OPERABLE 

status and operation. 

AND

A.2 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet the 

boron concentration of 

LCO 3.9.1. 

AND

A.3 Suspend loading irradiated 

fuel assemblies in the core. 

AND

Immediately 

Immediately 

Immediately 
SDC and Coolant Circulation - High Water Level 

3.9.4 

CEOG STS 3.9.4-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

A.4 Close equipment hatch and 

secure with [four] bolts. 

AND

A.5 Close one door in each air 

lock. 

AND

A.6.1 Close each penetration 

providing direct access 

from the containment 

atmosphere to the outside 

atmosphere with a manual 

or automatic isolation valve, 

blind flange, or equivalent. 

 OR

A.6.2 Verify each penetration is 

capable of being closed by 

an OPERABLE 

Containment Purge and 

Exhaust Isolation System. 

4 hours 

4 hours 

4 hours 

4 hours 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.9.4.1 Verify one SDC loop is in operation and circulating 

reactor coolant at a flow rate of ≥ [2200] gpm. 

12 hours 
SDC and Coolant Circulation - Low Water Level 

3.9.5 

CEOG STS 3.9.5-1 Rev. 3.0, 03/31/04 

3.9 REFUELING OPERATIONS 

3.9.5 Shutdown Cooling (SDC) and Coolant Circulation - Low Water Level 

LCO 3.9.5 Two SDC loops shall be OPERABLE, and one SDC loop shall be in 

operation. 

 --------------------------------------------NOTES------------------------------------------- 

 1. All SDC pumps may be removed from operation for ≤ 15 minutes 

when switching from one train to another provided: 

 a. The core outlet temperature is maintained >10 degrees F 

below saturation temperature, 

 b. No operations are permitted that would cause introduction of 

coolant into the Reactor Coolant System with boron 

concentration less than that required to meet the minimum 

required boron concentration of LCO 3.9.1, and 

 c. No draining operations to further reduce RCS water volume 

are permitted. 

 2. One required SDC loop may be inoperable for up to 2 hours for 

surveillance testing, provided that the other SDC loop is 

OPERABLE and in operation. 

 -------------------------------------------------------------------------------------------------- 

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel 

flange. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. One SDC loop 

inoperable. 

A.1 Initiate action to restore 

SDC loop to OPERABLE 

status. 

OR

A.2 Initiate action to establish 

≥ 23 ft of water above the 

top of reactor vessel flange. 

Immediately 

Immediately 
SDC and Coolant Circulation - Low Water Level 

3.9.5 

CEOG STS 3.9.5-2 Rev. 3.0, 03/31/04 

ACTIONS (continued) 

CONDITION REQUIRED ACTION COMPLETION TIME 

B. No SDC loop 

OPERABLE or in 

operation. 

B.1 Suspend operations that 

would cause introduction of 

coolant into the RCS with 

boron concentration less 

than required to meet the 

boron concentration of 

LCO 3.9.1. 

AND

B.2 Initiate action to restore one 

SDC loop to OPERABLE 

status and to operation. 

AND

B.3 Close equipment hatch and 

secure with [four] bolts. 

AND

B.4 Close one door in each air 

lock. 

AND

B.5.1 Close each penetration 

providing direct access 

from the containment 

atmosphere to the outside 

atmosphere with a manual 

or automatic isolation valve, 

blind flange, or equivalent. 

OR

B.5.2 Verify each penetration is 

capable of being closed by 

an OPERABLE 

Containment Purge and 

Exhaust Isolation System. 

Immediately 

Immediately 

4 hours 

4 hours 

4 hours 

4 hours 
SDC and Coolant Circulation - Low Water Level 

3.9.5 

CEOG STS 3.9.5-3 Rev. 3.0, 03/31/04 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.9.5.1 Verify required SDC loops are OPERABLE and one 

SDC loop is in operation. 

12 hours 

SR 3.9.5.2 Verify correct breaker alignment and indicated 

power available to the required SDC pump that is 

not in operation. 

7 days 
Refueling Water Level 

3.9.6 

CEOG STS 3.9.6-1 Rev. 3.0, 03/31/04 

3.9 REFUELING OPERATIONS 

3.9.6 Refueling Water Level 

LCO 3.9.6 Refueling water level shall be maintained ≥ 23 ft above the top of reactor 

vessel flange. 

APPLICABILITY: During movement of [recently] irradiated fuel assemblies within 

containment. 

ACTIONS 

CONDITION REQUIRED ACTION COMPLETION TIME 

A. Refueling water level not 

within limit. 

A.1 Suspend movement of 

[recently] irradiated fuel 

assemblies within 

containment. 

Immediately 

SURVEILLANCE REQUIREMENTS 

SURVEILLANCE FREQUENCY 

SR 3.9.6.1 Verify refueling water level is ≥ 23 ft above the top of 

reactor vessel flange. 

24 hours 
Design Features 

4.0 

CEOG STS 4.0-1 Rev. 3.0, 03/31/04 

4.0 DESIGN FEATURES 

4.1 Site Location 

 [ Text description of site location. ] 

4.2 Reactor Core 

 4.2.1 Fuel Assemblies

 The reactor shall contain [217] fuel assemblies. Each assembly shall consist of a 

matrix of [Zircalloy or ZIRLO] fuel rods with an initial composition of natural or 

slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of 

zirconium alloy or stainless steel filler rods for fuel rods, in accordance with 

approved applications of fuel rod configurations, may be used. Fuel assemblies 

shall be limited to those fuel designs that have been analyzed with applicable 

NRC staff approved codes and methods and shown by tests or analyses to 

comply with all fuel safety design bases. A limited number of lead test 

assemblies that have not completed representative testing may be placed in 

nonlimiting core regions. 

 4.2.2 [Control Rod] Assemblies

 The reactor core shall contain [91] control element assemblies (CEAs). The 

control material shall be [silver indium cadmium, boron carbide, or hafnium metal] 

as approved by the NRC. 

4.3 Fuel Storage 

 4.3.1 Criticality

 4.3.1.1 The spent fuel storage racks are designed and shall be maintained 

with: 

 a. Fuel assemblies having a maximum U-235 enrichment of 

[4.5] weight percent, 

 b. keff ≤ 0.95 if fully flooded with unborated water, which includes an 

allowance for uncertainties as described in [Section 9.1 of the 

FSAR], 

 [ c. A nominal [9] inch center to center distance between fuel 

assemblies placed in [the high density fuel storage racks], ] 

 [ d. A nominal [10.4] inch center to center distance between fuel 

assemblies placed in [the low density fuel storage racks], ] 
Design Features 

4.0 

CEOG STS 4.0-2 Rev. 3.0, 03/31/04 

4.0 DESIGN FEATURES 

4.3 Fuel Storage (continued) 

 [ e. New or partially spent fuel assemblies with a discharge burnup in 

the “acceptable range” of Figure [3.7.18-1] may be allowed 

unrestricted storage in [either] fuel storage rack(s), and ] 

 [ f. New or partially spent fuel assemblies with a discharge burnup in 

the “unacceptable range” of Figure [3.7.18-1] will be stored in 

compliance with the NRC approved [specific document containing 

the analytical methods, title, date, or specific configuration or 

figure]. ] 

 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: 

 a. Fuel assemblies having a maximum U-235 enrichment of 

[4.5] weight percent, 

 b. keff ≤ 0.98 if fully flooded with unborated water, which includes an 

allowance for uncertainties as described in [Section 9.1 of the 

FSAR], 

 c. keff ≤ 0.98 if moderated by aqueous foam, which includes an 

allowance for uncertainties as described in [Section 9.1 of the 

FSAR], and 

 d. A nominal [10] inch center to center distance between fuel 

assemblies placed in the storage racks. 

 4.3.2 Drainage

 The spent fuel storage pool is designed and shall be maintained to prevent 

inadvertent draining of the pool below elevation [23 ft]. 

 4.3.3 Capacity

 The spent fuel storage pool is designed and shall be maintained with a storage 

capacity limited to no more than [1542] fuel assemblies. 
Responsibility 

5.1 

CEOG STS 5.1-1 Rev. 3.0, 03/31/04 

5.0 ADMINISTRATIVE CONTROLS 

5.1 Responsibility 

-------------------------------------------------REVIEWER'S NOTES------------------------------------------------ 

1. Titles for members of the unit staff shall be specified by use of an overall statement 

referencing an ANSI Standard acceptable to the NRC staff from which the titles were 

obtained, or an alternative title may be designated for this position. Generally, the first 

method is preferable; however, the second method is adaptable to those unit staffs 

requiring special titles because of unique organizational structures. 

2. The ANSI Standard shall be the same ANSI Standard referenced in Section 5.3, Unit Staff 

Qualifications. If alternative titles are used, all requirements of these Technical 

Specifications apply to the position with the alternative title as apply with the specified title. 

Unit staff titles shall be specified in the Final Safety Analysis Report or Quality Assurance 

Plan. Unit staff titles shall be maintained and revised using those procedures approved for 

modifying/revising the Final Safety Analysis Report or Quality Assurance Plan. 

-------------------------------------------------------------------------------------------------------------------------------

5.1.1 The plant manager shall be responsible for overall unit operation and shall 

delegate in writing the succession to this responsibility during his absence. 

 The plant manager or his designee shall approve, prior to implementation, each 

proposed test, experiment or modification to systems or equipment that affect 

nuclear safety. 

5.1.2 The [Shift Supervisor (SS)] shall be responsible for the control room command 

function. During any absence of the [SS] from the control room while the unit is 

in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator 

(SRO) license shall be designated to assume the control room command 

function. During any absence of the [SS] from the control room while the unit is 

in MODE 5 or 6, an individual with an active SRO license or Reactor Operator 

license shall be designated to assume the control room command function. 
Organization 

5.2 

CEOG STS 5.2-1 Rev. 3.0, 03/31/04 

5.0 ADMINISTRATIVE CONTROLS 

5.2 Organization 

5.2.1 Onsite and Offsite Organizations

 Onsite and offsite organizations shall be established for unit operation and 

corporate management, respectively. The onsite and offsite organizations shall 

include the positions for activities affecting safety of the nuclear power plant. 

 a. Lines of authority, responsibility, and communication shall be defined and 

established throughout highest management levels, intermediate levels, 

and all operating organization positions. These relationships shall be 

documented and updated, as appropriate, in organization charts, functional 

descriptions of departmental responsibilities and relationships, and job 

descriptions for key personnel positions, or in equivalent forms of 

documentation. These requirements including the plant-specific titles of 

those personnel fulfilling the responsibilities of the positions delineated in 

these Technical Specifications shall be documented in the [FSAR/QA Plan], 

 b. The plant manager shall be responsible for overall safe operation of the 

plant and shall have control over those onsite activities necessary for safe 

operation and maintenance of the plant, 

 c. A specified corporate officer shall have corporate responsibility for overall 

plant nuclear safety and shall take any measures needed to ensure 

acceptable performance of the staff in operating, maintaining, and providing 

technical support to the plant to ensure nuclear safety, and 

 d. The individuals who train the operating staff, carry out health physics, or 

perform quality assurance functions may report to the appropriate onsite 

manager; however, these individuals shall have sufficient organizational 

freedom to ensure their independence from operating pressures. 

5.2.2 Unit Staff

 The unit staff organization shall include the following: 

 a. A non-licensed operator shall be assigned to each reactor containing fuel 

and an additional non-licensed operator shall be assigned for each control 

room from which a reactor is operating in MODES 1, 2, 3, or 4. 

 ----------------------------------------REVIEWER'S NOTE---------------------------------------- 

 Two unit sites with both units shutdown or defueled require a total of three nonlicensed operators for the two units. 

 ------------------------------------------------------------------------------------------------------------ 
Organization 

5.2 

CEOG STS 5.2-2 Rev. 3.0, 03/31/04 

5.2 Organization 

5.2.2 Unit Staff (continued) 

 b. Shift crew composition may be less than the minimum requirement of 

10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to 

exceed 2 hours in order to accommodate unexpected absence of on-duty 

shift crew members provided immediate action is taken to restore the shift 

crew composition to within the minimum requirements. 

 c. A radiation protection technician shall be on site when fuel is in the reactor. 

The position may be vacant for not more than 2 hours, in order to provide 

for unexpected absence, provided immediate action is taken to fill the 

required position. 

 d. Administrative procedures shall be developed and implemented to limit the 

working hours of personnel who perform safety related functions 

(e.g., [licensed Senior Reactor Operators (SROs), licensed Reactor 

Operators (ROs), health physicists, auxiliary operators, and key 

maintenance personnel]). 

 The controls shall include guidelines on working hours that ensure 

adequate shift coverage shall be maintained without routine heavy use of 

overtime. 

 Any deviation from the above guidelines shall be authorized in advance by 

the plant manager or the plant manager's designee, in accordance with 

approved administrative procedures, and with documentation of the basis 

for granting the deviation. Routine deviation from the working hour 

guidelines shall not be authorized. 

 Controls shall be included in the procedures to require a periodic 

independent review be conducted to ensure that excessive hours have not 

been assigned. 

 e. The operations manager or assistant operations manager shall hold an 

SRO license. 

 f. An individual shall provide advisory technical support to the unit operations 

shift crew in the areas of thermal hydraulics, reactor engineering, and plant 

analysis with regard to the safe operation of the unit. This individual shall 

meet the qualifications specified by the Commission Policy Statement on 

Engineering Expertise on Shift. 
Unit Staff Qualifications 

5.3 

CEOG STS 5.3-1 Rev. 3.0, 03/31/04 

5.0 ADMINISTRATIVE CONTROLS 

5.3 Unit Staff Qualifications 

--------------------------------------------------REVIEWER'S NOTE------------------------------------------------- 

Minimum qualifications for members of the unit staff shall be specified by use of an overall 

qualification statement referencing an ANSI Standard acceptable to the NRC staff or by 

specifying individual position qualifications. Generally, the first method is preferable; however, 

the second method is adaptable to those unit staffs requiring special qualification statements 

because of unique organizational structures. 

-------------------------------------------------------------------------------------------------------------------------------

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of 

[Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI 

Standard acceptable to the NRC staff]. [The staff not covered by Regulatory 

Guide 1.8 shall meet or exceed the minimum qualifications of Regulations, 

Regulatory Guides, or ANSI Standards acceptable to NRC staff]. 

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and 

a licensed Reactor Operator (RO) are those individuals who, in addition to 

meeting the requirements of Specification 5.3.1, perform the functions described 

in 10 CFR 50.54(m). 
Procedures 

5.4 

CEOG STS 5.4-1 Rev. 3.0, 03/31/04 

5.0 ADMINISTRATIVE CONTROLS 

5.4 Procedures 

5.4.1 Written procedures shall be established, implemented, and maintained covering 

the following activities: 

 a. The applicable procedures recommended in Regulatory Guide 1.33, 

Revision 2, Appendix A, February 1978, 

 b. The emergency operating procedures required to implement the 

requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as 

stated in [Generic Letter 82-33], 

 c. Quality assurance for effluent and environmental monitoring, 

 d. Fire Protection Program implementation, and 

 e. All programs specified in Specification 5.5. 

 [ f. Modification of core protection calculator (CPC) addressable constants. 

These procedures shall include provisions to ensure that sufficient margin 

is maintained in CPC type I addressable constants to avoid excessive 

operator interaction with CPCs during reactor operation. 

 Modifications to the CPC software (including changes of algorithms and 

fuel cycle specific data) shall be performed in accordance with the most 

recent version of "CPC Protection Algorithm Software Change Procedure," 

CEN-39(A)-P, which has been determined to be applicable to the facility. 

Additions or deletions to CPC addressable constants or changes to 

addressable constant software limit values shall not be implemented 

without prior NRC approval. ] 
Programs and Manuals 

5.5 

CEOG STS 5.5-1 Rev. 3.0, 03/31/04 

5.0 ADMINISTRATIVE CONTROLS 

5.5 Programs and Manuals 

The following programs shall be established, implemented, and maintained. 

5.5.1 Offsite Dose Calculation Manual (ODCM)

 a. The ODCM shall contain the methodology and parameters used in the 

calculation of offsite doses resulting from radioactive gaseous and liquid 

effluents, in the calculation of gaseous and liquid effluent monitoring alarm 

and trip setpoints, and in the conduct of the radiological environmental 

monitoring program and 

 b. The ODCM shall also contain the radioactive effluent controls and 

radiological environmental monitoring activities, and descriptions of the 

information that should be included in the Annual Radiological 

Environmental Operating, and Radioactive Effluent Release Reports 

required by Specification [5.6.2] and Specification [5.6.3]. 

 Licensee initiated changes to the ODCM: 

 a. Shall be documented and records of reviews performed shall be retained. 

This documentation shall contain: 

 1. Sufficient information to support the change(s) together with the 

appropriate analyses or evaluations justifying the change(s) and 

 2. A determination that the change(s) maintain the levels of radioactive 

effluent control required by 10 CFR 20.1302, 40 CFR 190, 

10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely 

impact the accuracy or reliability of effluent, dose, or setpoint 

calculations, 

 b. Shall become effective after the approval of the plant manager, and 

 c. Shall be submitted to the NRC in the form of a complete, legible copy of the 

entire ODCM as a part of or concurrent with the Radioactive Effluent 

Release Report for the period of the report in which any change in the 

ODCM was made. Each change shall be identified by markings in the 

margin of the affected pages, clearly indicating the area of the page that 

was changed, and shall indicate the date (i.e., month and year) the change 

was implemented. 
Programs and Manuals 

5.5 

CEOG STS 5.5-2 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.2 Primary Coolant Sources Outside Containment

 This program provides controls to minimize leakage from those portions of 

systems outside containment that could contain highly radioactive fluids during a 

serious transient or accident to levels as low as practicable. The systems include 

[Low Pressure Injection, Reactor Building Spray, Makeup and Purification, and 

Hydrogen Recombiner]. The program shall include the following: 

 a. Preventive maintenance and periodic visual inspection requirements and 

 b. Integrated leak test requirements for each system at least once per 

[18] months. 

 The provisions of SR 3.0.2 are applicable. 

5.5.3 [ Post Accident Sampling

 ----------------------------------------REVIEWER'S NOTE---------------------------------------- 

 This program may be eliminated based on the implementation of Topical Report 

CE NPSD-1157, Rev. 1, "Technical Justification for the Elimination of the PostAccident Sampling System from the Plant Design and Licensing Basis for CEOG 

Utilities," and the associated NRC Safety Evaluation dated May 16, 2000. 

 ------------------------------------------------------------------------------------------------------------ 

 This program provides controls that ensure the capability to obtain and analyze 

reactor coolant, radioactive gases, and particulates in plant gaseous effluents 

and containment atmosphere samples under accident conditions. The program 

shall include the following: 

 a. Training of personnel, 

 b. Procedures for sampling and analysis, and 

 c. Provisions for maintenance of sampling and analysis equipment. ] 

5.5.4 Radioactive Effluent Controls Program

 This program conforms to 10 CFR 50.36a for the control of radioactive effluents 

and for maintaining the doses to members of the public from radioactive effluents 

as low as reasonably achievable. The program shall be contained in the ODCM, 

shall be implemented by procedures, and shall include remedial actions to be 

taken whenever the program limits are exceeded. The program shall include the 

following elements: 
Programs and Manuals 

5.5 

CEOG STS 5.5-3 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.4 Radioactive Effluent Controls Program (continued) 

 a. Limitations on the functional capability of radioactive liquid and gaseous 

monitoring instrumentation including surveillance tests and setpoint 

determination in accordance with the methodology in the ODCM, 

 b. Limitations on the concentrations of radioactive material released in liquid 

effluents to unrestricted areas, conforming to ten times the concentration 

values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, 

 c. Monitoring, sampling, and analysis of radioactive liquid and gaseous 

effluents in accordance with 10 CFR 20.1302 and with the methodology 

and parameters in the ODCM, 

 d. Limitations on the annual and quarterly doses or dose commitment to a 

member of the public from radioactive materials in liquid effluents released 

from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I, 

 e. Determination of cumulative dose contributions from radioactive effluents 

for the current calendar quarter and current calendar year in accordance 

with the methodology and parameters in the ODCM at least every 31 days. 

Determination of projected dose contributions from radioactive effluents in 

accordance with the methodology in the ODCM at least every 31 days, 

 f. Limitations on the functional capability and use of the liquid and gaseous 

effluent treatment systems to ensure that appropriate portions of these 

systems are used to reduce releases of radioactivity when the projected 

doses in a period of 31 days would exceed 2% of the guidelines for the 

annual dose or dose commitment, conforming to 10 CFR 50, Appendix I, 

 g. Limitations on the dose rate resulting from radioactive material released in 

gaseous effluents from the site to areas at or beyond the site boundary 

shall be in accordance with the following: 

 1. For noble gases: a dose rate ≤ 500 mrem/yr to the whole body and a 

dose rate ≤ 3000 mrem/yr to the skin and 

 2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate 

form with half-lives greater than 8 days: a dose rate ≤ 1500 mrem/yr 

to any organ, 

 h. Limitations on the annual and quarterly air doses resulting from noble 

gases released in gaseous effluents from each unit to areas beyond the 

site boundary, conforming to 10 CFR 50, Appendix I, 
Programs and Manuals 

5.5 

CEOG STS 5.5-4 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.4 Radioactive Effluent Controls Program (continued) 

 i. Limitations on the annual and quarterly doses to a member of the public 

from iodine-131, iodine-133, tritium, and all radionuclides in particulate form 

with half lives > 8 days in gaseous effluents released from each unit to 

areas beyond the site boundary, conforming to 10 CFR 50, Appendix I, and 

 j. Limitations on the annual dose or dose commitment to any member of the 

public, beyond the site boundary, due to releases of radioactivity and to 

radiation from uranium fuel cycle sources, conforming to 40 CFR 190. 

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive 

Effluent Controls Program surveillance frequency. 

5.5.5 Component Cyclic or Transient Limit

 This program provides controls to track the FSAR, Section [ ], cyclic and 

transient occurrences to ensure that components are maintained within the 

design limits. 

5.5.6 [ Pre-Stressed Concrete Containment Tendon Surveillance Program

 This program provides controls for monitoring any tendon degradation in prestressed concrete containments, including effectiveness of its corrosion 

protection medium, to ensure containment structural integrity. The program shall 

include baseline measurements prior to initial operations. The Tendon 

Surveillance Program, inspection frequencies, and acceptance criteria shall be in 

accordance with [Regulatory Guide 1.35, Revision 3, 1990]. 

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon 

Surveillance Program inspection frequencies. ] 

5.5.7 Reactor Coolant Pump Flywheel Inspection Program

 This program shall provide for the inspection of each reactor coolant pump 

flywheel per the recommendation of Regulatory position c.4.b of Regulatory 

Guide 1.14, Revision 1, August 1975. 

5.5.8 Inservice Testing Program

 This program provides controls for inservice testing of ASME Code Class 1, 2, 

and 3 components. The program shall include the following: 

 a. Testing frequencies specified in Section XI of the ASME Boiler and 

Pressure Vessel Code and applicable Addenda as follows: 
Programs and Manuals 

5.5 

CEOG STS 5.5-5 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.8 Inservice Testing Program (continued) 

ASME Boiler and Pressure 

Vessel Code and applicable 

Addenda terminology for 

inservice testing activities 

 

Required Frequencies for 

performing inservice testing 

activities 

Weekly At least once per 7 days 

Monthly At least once per 31 days 

Quarterly or every 3 months At least once per 92 days 

Semiannually or every 6 months At least once per 184 days 

Every 9 months At least once per 276 days 

Yearly or annually At least once per 366 days 

Biennially or every 2 years At least once per 731 days 

 b. The provisions of SR 3.0.2 are applicable to the above required 

Frequencies for performing inservice testing activities, 

 c. The provisions of SR 3.0.3 are applicable to inservice testing activities, and 

 d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed 

to supersede the requirements of any TS. 

5.5.9 Steam Generator (SG) Tube Surveillance Program

 ----------------------------------------REVIEWER'S NOTE---------------------------------------- 

 The Licensee's current licensing basis steam generator tube surveillance 

requirements shall be relocated from the LCO and included here. An appropriate 

administrative controls program format should be used. 

 ------------------------------------------------------------------------------------------------------------ 

 The provisions of SR 3.0.2 are applicable to the SG Tube Surveillance Program. 

5.5.10 Secondary Water Chemistry Program

 This program provides controls for monitoring secondary water chemistry to 

inhibit SG tube degradation and low pressure turbine disc stress corrosion 

cracking. The program shall include: 

 a. Identification of a sampling schedule for the critical variables and control 

points for these variables, 
Programs and Manuals 

5.5 

CEOG STS 5.5-6 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.10 Secondary Water Chemistry Program (continued) 

 b. Identification of the procedures used to measure the values of the critical 

variables, 

 c. Identification of process sampling points, which shall include monitoring the 

discharge of the condensate pumps for evidence of condenser in leakage, 

 d. Procedures for the recording and management of data, 

 e. Procedures defining corrective actions for all off control point chemistry 

conditions, and 

 f. A procedure identifying the authority responsible for the interpretation of the 

data and the sequence and timing of administrative events, which is 

required to initiate corrective action. 

5.5.11 Ventilation Filter Testing Program (VFTP)

 A program shall be established to implement the following required testing of 

Engineered Safety Feature (ESF) filter ventilation systems at the frequencies 

specified in [Regulatory Guide ], and in accordance with [Regulatory Guide 1.52, 

Revision 2, ASME N510-1989, and AG-1] at the system flowrate specified 

below [± 10%]. 

 a. Demonstrate for each of the ESF systems that an inplace test of the high 

efficiency particulate air (HEPA) filters shows a penetration and system 

bypass < [0.05]% when tested in accordance with [Regulatory Guide 1.52, 

Revision 2, and ASME N510-1989] at the system flowrate specified below 

[± 10%]. 

 ESF Ventilation System Flowrate 

 [ ] [ ] 

 b. Demonstrate for each of the ESF systems that an inplace test of the 

charcoal adsorber shows a penetration and system bypass < [0.05]% when 

tested in accordance with [Regulatory Guide 1.52, Revision 2, and 

ASME N510-1989] at the system flowrate specified below [± 10%]. 

 ESF Ventilation System Flowrate 

 [ ] [ ] 
Programs and Manuals 

5.5 

CEOG STS 5.5-7 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.11 Ventilation Filter Testing Program (continued) 

 c. Demonstrate for each of the ESF systems that a laboratory test of a sample 

of the charcoal adsorber, when obtained as described in [Regulatory 

Guide 1.52, Revision 2], shows the methyl iodide penetration less than the 

value specified below when tested in accordance with ASTM D3803-1989 

at a temperature of 30°C (86°F) and the relative humidity specified below. 

 ESF Ventilation System Penetration RH Face Velocity 

 [ ] [See Reviewer's [See [See Reviewer's 

 Note] Reviewer's Note] 

 Note] 

 ----------------------------------------REVIEWER'S NOTE---------------------------------------- 

 The use of any standard other than ASTM D3803-1989 to test the charcoal 

sample may result in an overestimation of the capability of the charcoal to adsorb 

radioiodine. As a result, the ability of the charcoal filters to perform in a manner 

consistent with the licensing basis for the facility is indeterminate. 

 ASTM D 3803-1989 is a more stringent testing standard because it does not 

differentiate between used and new charcoal, it has a longer equilibration period 

performed at a temperature of 30°C (86°F) and a relative humidity (RH) of 95% 

(or 70% RH with humidity control), and it has more stringent tolerances that 

improve repeatability of the test. 

 Allowable Penetration = [(100% - Methyl Iodide Efficiency * for Charcoal Credited 

in Licensee's Accident Analysis) / Safety Factor] 

 When ASTM D3803-1989 is used with 30°C (86°F) and 95% RH (or 70% RH 

with humidity control) is used, the staff will accept the following: 

 Safety factor ≥ 2 for systems with or without humidity control. 

 Humidity control can be provided by heaters or an NRC-approved analysis that 

demonstrates that the air entering the charcoal will be maintained less than or 

equal to 70 percent RH under worst case design basis conditions. 

 If the system has a face velocity greater than 110 percent of 0.203 m/s 

(40 ft/min), the face velocity should be specified. 

 *This value should be the efficiency that was incorporated in the licensee's 

accident analysis which was reviewed and approved by the staff in a safety 

evaluation. 

 ------------------------------------------------------------------------------------------------------------ 
Programs and Manuals 

5.5 

CEOG STS 5.5-8 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.11 Ventilation Filter Testing Program (continued) 

 d. Demonstrate for each of the ESF systems that the pressure drop across 

the combined HEPA filters, the prefilters, and the charcoal adsorbers is less 

than the value specified below when tested in accordance with [Regulatory 

Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate 

specified below [± 10%]. 

 ESF Ventilation System Delta P Flowrate 

 [ ] [ ] [ ] 

 [ e. Demonstrate that the heaters for each of the ESF systems dissipate the 

value specified below [± 10%] when tested in accordance with 

[ASME N510-1989]. 

 ESF Ventilation System Wattage ] 

 [ ] [ ] 

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test 

frequencies. 

5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program

 This program provides controls for potentially explosive gas mixtures contained 

in the [Waste Gas Holdup System], [the quantity of radioactivity contained in gas 

storage tanks or fed into the offgas treatment system, and the quantity of 

radioactivity contained in unprotected outdoor liquid storage tanks]. The gaseous 

radioactivity quantities shall be determined following the methodology in [Branch 

Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to 

Waste Gas System Leak or Failure"]. The liquid radwaste quantities shall be 

determined in accordance with [Standard Review Plan, Section 15.7.3, 

"Postulated Radioactive Release due to Tank Failures"]. 

 The program shall include: 

 a. The limits for concentrations of hydrogen and oxygen in the [Waste Gas 

Holdup System] and a surveillance program to ensure the limits are 

maintained. Such limits shall be appropriate to the system's design criteria 

(i.e., whether or not the system is designed to withstand a hydrogen 

explosion), 
Programs and Manuals 

5.5 

CEOG STS 5.5-9 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued) 

 b. A surveillance program to ensure that the quantity of radioactivity contained 

in [each gas storage tank and fed into the offgas treatment system] is less 

than the amount that would result in a whole body exposure of ≥ 0.5 rem to 

any individual in an unrestricted area, in the event of [an uncontrolled 

release of the tanks' contents], and 

 c. A surveillance program to ensure that the quantity of radioactivity contained 

in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, 

or walls, capable of holding the tanks' contents and that do not have tank 

overflows and surrounding area drains connected to the [Liquid Radwaste 

Treatment System] is less than the amount that would result in 

concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, 

Column 2, at the nearest potable water supply and the nearest surface 

water supply in an unrestricted area, in the event of an uncontrolled release 

of the tanks' contents. 

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and 

Storage Tank Radioactivity Monitoring Program surveillance frequencies. 

5.5.13 Diesel Fuel Oil Testing Program

 A diesel fuel oil testing program to implement required testing of both new fuel oil 

and stored fuel oil shall be established. The program shall include sampling and 

testing requirements, and acceptance criteria, all in accordance with applicable 

ASTM Standards. The purpose of the program is to establish the following: 

 a. Acceptability of new fuel oil for use prior to addition to storage tanks by 

determining that the fuel oil has: 

 1. An API gravity or an absolute specific gravity within limits, 

 2. A flash point and kinematic viscosity within limits for ASTM 2D fuel oil, 

and 

 3. A clear and bright appearance with proper color or a water and 

sediment content within limits, 

 b. Within 31 days following addition of the new fuel oil to storage tanks, verify 

that the properties of the new fuel oil, other than those addressed in a., 

above, are within limits for ASTM 2D fuel oil, and 
Programs and Manuals 

5.5 

CEOG STS 5.5-10 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.13 Diesel Fuel Oil Testing Program (continued) 

 c. Total particulate concentration of the fuel oil is ≤ 10 mg/l when tested every 

31 days. 

 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil 

Testing Program test frequencies. 

5.5.14 Technical Specifications (TS) Bases Control Program

 This program provides a means for processing changes to the Bases of these 

Technical Specifications. 

 a. Changes to the Bases of the TS shall be made under appropriate 

administrative controls and reviews. 

 b. Licensees may make changes to Bases without prior NRC approval 

provided the changes do not require either of the following: 

 1. A change in the TS incorporated in the license or 

 2. A change to the updated FSAR or Bases that requires NRC approval 

pursuant to 10 CFR 50.59. 

 c. The Bases Control Program shall contain provisions to ensure that the 

Bases are maintained consistent with the FSAR. 

 d. Proposed changes that meet the criteria of 5.5.14b above shall be reviewed 

and approved by the NRC prior to implementation. Changes to the Bases 

implemented without prior NRC approval shall be provided to the NRC on a 

frequency consistent with 10 CFR 50.71(e). 

5.5.15 Safety Function Determination Program (SFDP)

 This program ensures loss of safety function is detected and appropriate actions 

taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if 

loss of safety function exists. Additionally, other appropriate limitations and 

remedial or compensatory actions may be identified to be taken as a result of the 

support system inoperability and corresponding exception to entering supported 

system Condition and Required Actions. This program implements the 

requirements of LCO 3.0.6. The SFDP shall contain the following: 

 a. Provisions for cross train checks to ensure a loss of the capability to 

perform the safety function assumed in the accident analysis does not go 

undetected, 
Programs and Manuals 

5.5 

CEOG STS 5.5-11 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.13 Safety Function Determining Program (continued) 

 b. Provisions for ensuring the plant is maintained in a safe condition if a loss 

of function condition exists, 

 c. Provisions to ensure that an inoperable supported system's Completion 

Time is not inappropriately extended as a result of multiple support system 

inoperabilities, and 

 d. Other appropriate limitations and remedial or compensatory actions. 

 A loss of safety function exists when, assuming no concurrent single failure, no 

concurrent loss of offsite power, or no concurrent loss of onsite diesel 

generator(s), a safety function assumed in the accident analysis cannot be 

performed. For the purpose of this program, a loss of safety function may exist 

when a support system is inoperable, and 

 a. A required system redundant to the system(s) supported by the inoperable 

support system is also inoperable, or 

 b. A required system redundant to the system(s) in turn supported by the 

inoperable supported system is also inoperable, or 

 c. A required system redundant to the support system(s) for the supported 

systems (a) and (b) above is also inoperable. 

 The SFDP identifies where a loss of safety function exists. If a loss of safety 

function is determined to exist by this program, the appropriate Conditions and 

Required Actions of the LCO in which the loss of safety function exists are 

required to be entered. When a loss of safety function is caused by the 

inoperability of a single Technical Specification support system, the appropriate 

Conditions and Required Actions to enter are those of the support system. 

5.5.16 Containment Leakage Rate Testing Program

 [OPTION A] 

 a. A program shall establish the leakage rate testing of the containment as 

required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option A, as 

modified by approved exemptions. 

 b. The maximum allowable containment leakage rate, La at Pa, shall be [ ]% of 

containment air weight per day. 

 c. Leakage rate acceptance criteria are: 
Programs and Manuals 

5.5 

CEOG STS 5.5-12 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued) 

 1. Containment leakage rate acceptance criterion is ≤ 1.0 La. During the 

first unit startup following testing in accordance with this program, the 

leakage rate acceptance criteria are < 0.60 La for the Type B and C 

tests and < 0.75 La for Type A tests. 

 2. Air lock testing acceptance criteria are: 

 a) Overall air lock leakage rate is ≤ [0.05 La] when tested at ≥ Pa. 

 b) For each door, leakage rate is ≤ [0.01 La] when pressurized to 

[≥10 psig]. 

 d. The provisions of SR 3.0.3 are applicable to the Containment Leakage 

Rate Testing Program. 

 e. Nothing in these Technical Specifications shall be construed to modify the 

testing Frequencies required by 10 CFR 50, Appendix J. 

 [OPTION B] 

 a. A program shall establish the leakage rate testing of the containment as 

required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as 

modified by approved exemptions. This program shall be in accordance 

with the guidelines contained in Regulatory Guide 1.163, "PerformanceBased Containment Leak-Test Program," dated September, 1995 [,as 

modified by the following exceptions: 

 1. . . .] 

 b. The calculated peak containment internal pressure for the design basis loss 

of coolant accident, Pa is [45 psig]. The containment design pressure is 

[50 psig]. 

 c. The maximum allowable containment leakage rate, La at Pa, shall be [ ]% of 

containment air weight per day. 

 d. Leakage rate acceptance criteria are: 

 1. Containment leakage rate acceptance criterion is ≤ 1.0 La. During the 

first unit startup following testing in accordance with this program, the 

leakage rate acceptance criteria are < 0.60 La for the Type B and C 

tests and ≤ 0.75 La for Type A tests. 
Programs and Manuals 

5.5 

CEOG STS 5.5-13 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued) 

 2. Air lock testing acceptance criteria are: 

 a) Overall air lock leakage rate is ≤ [0.05 La] when tested at ≥ Pa. 

 b) For each door, leakage rate is ≤ [0.01 La] when pressurized to 

[≥10 psig]. 

 e. The provisions of SR 3.0.3 are applicable to the Containment Leakage 

Rate Testing Program. 

 f. Nothing in these Technical Specifications shall be construed to modify the 

testing Frequencies required by 10 CFR 50, Appendix J. 

 [OPTION A/B Combined] 

 a. A program shall establish the leakage rate testing of the containment as 

required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J. [Type A][Type B 

and C] test requirements are in accordance with 10 CFR 50, Appendix J, 

Option A, as modified by approved exemptions. [Type B and C] [Type A] 

test requirements are in accordance with 10 CFR 50, Appendix J, Option B, 

as modified by approved exemptions. The 10 CFR 50, Appendix J, Option 

B test requirements shall be in accordance with the guidelines contained in 

Regulatory Guide 1.163, "Performance-Based Containment Leak-Test 

Program," dated September, 1995 [,as modified by the following 

exceptions: 

 1. . . .] 

 b. The calculated peak containment internal pressure for the design basis loss 

of coolant accident, Pa is [45 psig]. The containment design pressure is 

[50 psig]. 

 c. The maximum allowable containment leakage rate, La, at Pa, shall be [ ]% 

of containment air weight per day. 

 d. Leakage rate acceptance criteria are: 

 1. Containment leakage rate acceptance criterion is ≤ 1.0 La. During the 

first unit startup following testing in accordance with this program, the 

leakage rate acceptance criteria are < 0.60 La for the Type B and C 

tests and [< 0.75 La for Option A Type A tests][≤ 0.75 La for Option B 

Type A tests]. 
Programs and Manuals 

5.5 

CEOG STS 5.5-14 Rev. 3.0, 03/31/04 

5.5 Programs and Manuals 

5.5.16 Containment Leakage Rate Testing Program (continued) 

 2. Air lock testing acceptance criteria are: 

 a) Overall air lock leakage rate is ≤ [0.05 La] when tested at ≥ Pa. 

 b) For each door, leakage rate is ≤ [0.01 La] when pressurized to 

[≥10 psig]. 

 e. The provisions of SR 3.0.3 are applicable to the Containment Leakage 

Rate Testing Program. 

 f. Nothing in these Technical Specifications shall be construed to modify the 

testing Frequencies required by 10 CFR 50, Appendix J. 

5.5.17 Battery Monitoring and Maintenance Program

 This Program provides for battery restoration and maintenance, based on [the 

recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice 

for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for 

Stationary Applications," or of the battery manufacturer] including the following 

 a. Actions to restore battery cells with float voltage < [2.13] V, and 

 b. Actions to equalize and test battery cells that had been discovered with 

electrolyte level below the minimum established design limit. 
Reporting Requirements 

5.6 

CEOG STS 5.6-1 Rev. 3.0, 03/31/04 

5.0 ADMINISTRATIVE CONTROLS 

5.6 Reporting Requirements 

The following reports shall be submitted in accordance with 10 CFR 50.4. 

5.6.1 Occupational Radiation Exposure Report

 --------------------------------------------------NOTE------------------------------------------------- 

 [ A single submittal may be made for a multiple unit station. The submittal should 

combine sections common to all units at the station. ] 

 ------------------------------------------------------------------------------------------------------------ 

 A tabulation on an annual basis of the number of station, utility, and other 

personnel (including contractors), for whom monitoring was performed, receiving 

an annual deep dose equivalent > 100 mrems and the associated collective deep 

dose equivalent (reported in person - rem) according to work and job functions 

(e.g., reactor operations and surveillance, inservice inspection, routine 

maintenance, special maintenance [describe maintenance], waste processing, 

and refueling). This tabulation supplements the requirements of 

10 CFR 20.2206. The dose assignments to various duty functions may be 

estimated based on pocket ionization chamber, thermoluminescence dosimeter 

(TLD), electronic dosimeter, or film badge measurements. Small exposures 

totaling < 20 percent of the individual total dose need not be accounted for. In 

the aggregate, at least 80 percent of the total deep dose equivalent received 

from external sources should be assigned to specific major work functions. The 

report covering the previous calendar year shall be submitted by April 30 of each 

year. [The initial report shall be submitted by April 30 of the year following the 

initial criticality.] 

5.6.2 Annual Radiological Environmental Operating Report

 --------------------------------------------------NOTE------------------------------------------------- 

 [ A single submittal may be made for a multiple unit station. The submittal should 

combine sections common to all units at the station. ] 

 ------------------------------------------------------------------------------------------------------------ 

 The Annual Radiological Environmental Operating Report covering the operation 

of the unit during the previous calendar year shall be submitted by May 15 of 

each year. The report shall include summaries, interpretations, and analyses of 

trends of the results of the Radiological Environmental Monitoring Program for 

the reporting period. The material provided shall be consistent with the 

objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 

10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. 
Reporting Requirements 

5.6 

CEOG STS 5.6-2 Rev. 3.0, 03/31/04 

5.6 Reporting Requirements 

5.6.2 Annual Radiological Environmental Operating Report (continued) 

 The Annual Radiological Environmental Operating Report shall include the 

results of analyses of all radiological environmental samples and of all 

environmental radiation measurements taken during the period pursuant to the 

locations specified in the table and figures in the ODCM, as well as summarized 

and tabulated results of these analyses and measurements [in the format of the 

table in the Radiological Assessment Branch Technical Position, Revision 1, 

November 1979]. In the event that some individual results are not available for 

inclusion with the report, the report shall be submitted noting and explaining the 

reasons for the missing results. The missing data shall be submitted in a 

supplementary report as soon as possible. 

5.6.3 Radiological Effluent Release Report

 --------------------------------------------------NOTE------------------------------------------------- 

 [ A single submittal may be made for a multiple unit station. The submittal shall 

combine sections common to all units at the station; however, for units with 

separate radwaste systems, the submittal shall specify the releases of 

radioactive material from each unit. ] 

 ------------------------------------------------------------------------------------------------------------ 

 The Radioactive Effluent Release Report covering the operation of the unit in the 

previous year shall be submitted prior to May 1 of each year in accordance with 

10 CFR 50.36a. The report shall include a summary of the quantities of 

radioactive liquid and gaseous effluents and solid waste released from the unit. 

The material provided shall be consistent with the objectives outlined in the 

ODCM and Process Control Program and in conformance with 10 CFR 50.36a 

and 10 CFR Part 50, Appendix I, Section IV.B.1. 

5.6.4 Monthly Operating Reports

 Routine reports of operating statistics and shutdown experience shall be 

submitted on a monthly basis no later than the 15th of each month following the 

calendar month covered by the report. 

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

 a. Core operating limits shall be established prior to each reload cycle, or prior 

to any remaining portion of a reload cycle, and shall be documented in the 

COLR for the following: 

 [ The individual specifications that address core operating limits must be 

referenced here. ] 
Reporting Requirements 

5.6 

CEOG STS 5.6-3 Rev. 3.0, 03/31/04 

5.6 Reporting Requirements 

5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 

 b. The analytical methods used to determine the core operating limits shall be 

those previously reviewed and approved by the NRC, specifically those 

described in the following documents: 

 [ Identify the Topical Report(s) by number and title or identify the staff 

Safety Evaluation Report for a plant specific methodology by NRC letter 

and date. The COLR will contain the complete identification for each of the 

TS referenced topical reports used to prepare the COLR (i.e., report 

number, title, revision, date, and any supplements).] 

 c. The core operating limits shall be determined such that all applicable limits 

(e.g., fuel thermal mechanical limits, core thermal hydraulic limits, 

Emergency Core Cooling System (ECCS) limits, nuclear limits such as 

SDM, transient analysis limits, and accident analysis limits) of the safety 

analysis are met. 

 d. The COLR, including any midcycle revisions or supplements, shall be 

provided upon issuance for each reload cycle to the NRC. 

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS 

REPORT (PTLR)

 a. RCS pressure and temperature limits for heat up, cooldown, low 

temperature operation, criticality, and hydrostatic testing as well as heatup 

and cooldown rates shall be established and documented in the PTLR for 

the following: 

 [ The individual specifications that address RCS pressure and temperature 

limits must be referenced here. ] 

 b. The analytical methods used to determine the RCS pressure and 

temperature limits shall be those previously reviewed and approved by the 

NRC, specifically those described in the following documents: 

 [ Identify the Topical Report(s) by number and title or identify the NRC 

Safety Evaluation for a plant specific methodology by NRC letter and date. 

The PTLR will contain the complete identification for each of the TS 

referenced Topical Reports used to prepare the PTLR (i.e., report number, 

title, revision, date, and any supplements). ] 

 c. The PTLR shall be provided to the NRC upon issuance for each reactor 

vessel fluence period and for any revision or supplement thereto. 
Reporting Requirements 

5.6 

CEOG STS 5.6-4 Rev. 3.0, 03/31/04 

5.6 Reporting Requirements 

5.6.6 RCS Pressure and Temperature Limits Report (continued) 

 ----------------------------------------REVIEWER'S NOTE---------------------------------------- 

 The methodology for the calculation of the P-T limits for NRC approval should 

include the following provisions: 

 1. The methodology shall describe how the neutron fluence is calculated 

(reference new Regulatory Guide when issued). 

 2. The Reactor Vessel Material Surveillance Program shall comply with 

Appendix H to 10 CFR 50. The reactor vessel material irradiation 

surveillance specimen removal schedule shall be provided, along with how 

the specimen examinations shall be used to update the PTLR curves. 

 3. Low Temperature Overpressure Protection (LTOP) System lift setting limits 

for the Power Operated Relief Valves (PORVs), developed using NRCapproved methodologies may be included in the PTLR. 

 4. The adjusted reference temperature (ART) for each reactor beltline material 

shall be calculated, accounting for radiation embrittlement, in accordance 

with Regulatory Guide 1.99, Revision 2. 

 5. The limiting ART shall be incorporated into the calculation of the pressure 

and temperature limit curves in accordance with NUREG-0800 Standard 

Review Plan 5.3.2, Pressure-Temperature Limits. 

 6. The minimum temperature requirements of Appendix G to 10 CFR Part 50 

shall be incorporated into the pressure and temperature limit curves. 

 7. Licensees who have removed two or more capsules should compare for 

each surveillance material the measured increase in reference temperature 

(RTNDT) to the predicted increase in RTNDT; where the predicted increase in 

RTNDT is based on the mean shift in RTNDT plus the two standard deviation 

value (2σ∆) specified in Regulatory Guide 1.99, Revision 2. If the measured 

value exceeds the predicted value (increase in RTNDT + 2σ∆), the licensee 

should provide a supplement to the PTLR to demonstrate how the results 

affect the approved methodology. 

 ------------------------------------------------------------------------------------------------------------ 

5.6.7 Post Accident Monitoring Report

 When a report is required by Condition B or F of LCO 3.3.[11], "Post Accident 

Monitoring (PAM) Instrumentation," a report shall be submitted within the 

following 14 days. The report shall outline the preplanned alternate method of 

monitoring, the cause of the inoperability, and the plans and schedule for 

restoring the instrumentation channels of the Function to OPERABLE status. 
Reporting Requirements 

5.6 

CEOG STS 5.6-5 Rev. 3.0, 03/31/04 

5.6 Reporting Requirements 

5.6.8 Tendon Surveillance Report

 [ Any abnormal degradation of the containment structure detected during the 

tests required by the Pre-stressed Concrete Containment Tendon Surveillance 

Program shall be reported to the NRC within 30 days. The report shall include a 

description of the tendon condition, the condition of the concrete (especially at 

tendon anchorages), the inspection procedures, the tolerances on cracking, and 

the corrective action taken. ] 

5.6.9 Steam Generator Tube Inspector Report

 ---------------------------------------REVIEWER'S NOTES--------------------------------------- 

 1. Reports required by the Licensee's current licensing basis regarding steam 

generator tube surveillance requirements shall be included here. An 

appropriate administrative controls format should be used. 

 2. These reports may be required covering inspection, test, and maintenance 

activities. These reports are determined on an individual basis for each unit 

and their preparation and submittal are designated in the Technical 

Specifications. 

 ------------------------------------------------------------------------------------------------------------ 
High Radiation Area 

5.7 

CEOG STS 5.7-1 Rev. 3.0, 03/31/04 

5.0 ADMINISTRATIVE CONTROLS 

[ 5.7 High Radiation Area ] 

As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied 

to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 

10 CFR Part 20: 

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 

30 Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation

 a. Each entryway to such an area shall be barricaded and conspicuously 

posted as a high radiation area. Such barricades may be opened as 

necessary to permit entry or exit of personnel or equipment. 

 b. Access to, and activities in, each such area shall be controlled by means of 

Radiation Work Permit (RWP) or equivalent that includes specification or 

radiation dose rates in the immediate work area(s) and other appropriate 

radiation protection equipment and measurers. 

 c. Individuals qualified in radiation protection procedures and personnel 

continuously escorted by such individuals may be exempted from the 

requirement for an RWP or equivalent while performing their assigned 

duties provided that they are otherwise following plant radiation protection 

procedures for entry to, exit from, and work in such areas. 

 d. Each individual or group entering such an area shall possess: 

 1. A radiation monitoring device that continuously displays radiation 

dose rates in the area, or 

 2. A radiation monitoring device that continuously integrates the 

radiation dose rates in the area and alarms when the device's dose 

alarm setpoint is reached, with an appropriate alarm setpoint, or 

 3. A radiation monitoring device that continuously transmits dose rate 

and cumulative dose information to a remote receiver monitored by 

radiation protection personnel responsible for controlling personnel 

radiation exposure within the area, or 

 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic 

dosimeter) and, 
High Radiation Area 

5.7 

CEOG STS 5.7-2 Rev. 3.0, 03/31/04 

5.7 High Radiation Area 

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters 

from the Radiation Source or from any Surface Penetrated by the Radiation

 (continued) 

 (i) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, of an individual qualified in 

radiation protection procedures, equipped with a radiation 

monitoring device that continuously displays radiation dose 

rates in the area; who is responsible for controlling personnel 

exposure within the area, or 

 (ii) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, by means of closed circuit 

television, or personnel qualified in radiation protection 

procedures, responsible for controlling personnel radiation 

exposure in the area, and with the means to communicate with 

individuals in the area who are covered by such surveillance. 

 e. Except for individuals qualified in radiation protection procedures, or 

personnel continuously escorted by such individuals, entry into such areas 

shall be made only after dose rates in the area have been determined and 

entry personnel are knowledgeable of them. These continuously escorted 

personnel will receive a pre-job briefing prior to entry into such areas. This 

dose rate determination, knowledge, and pre-job briefing does not require 

documentation prior to initial entry. 

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 

30 Centimeters from the Radiation Source or from any Surface Penetrated by the 

Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or 

from any Surface Penetrated by the Radiation

 a. Each entryway to such an area shall be conspicuously posted as a high 

radiation area and shall be provided with a locked or continuously guarded 

door or gate that prevents unauthorized entry, and, in addition: 

 1. All such door and gate keys shall be maintained under the 

administrative control of the shift supervisor, radiation protection 

manager, or his or her designee. 

 2. Doors and gates shall remain locked except during periods of 

personnel or equipment entry or exit. 

 b. Access to, and activities in, each such area shall be controlled by means of 

an RWP or equivalent that includes specification of radiation dose rates in 

the immediate work area(s) and other appropriate radiation protection 

equipment and measures. 
High Radiation Area 

5.7 

CEOG STS 5.7-3 Rev. 3.0, 03/31/04 

5.7 High Radiation Area 

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters 

from the Radiation Source or from any Surface Penetrated by the Radiation, but less 

than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface 

Penetrated by the Radiation (continued) 

 c. Individuals qualified in radiation protection procedures my be exempted 

from the requirement for an RWP or equivalent while performing radiation 

surveys in such areas provided that they are otherwise following plant 

radiation protection procedures for entry to, exit from, and work in such 

areas. 

 d. Each individual or group entering such an area shall possess: 

 1. A radiation monitoring device that continuously integrates the 

radiation rates in the area and alarms when the device's dose alarm 

setpoint is reached, with an appropriate alarm setpoint, or 

 2. A radiation monitoring device that continuously transmits dose rate 

and cumulative dose information to a remote receiver monitored by 

radiation protection personnel responsible for controlling personnel 

radiation exposure within the area with the means to communicate 

with and control every individual in the area, or 

 3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic 

dosimeter) and 

 (i) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, of an individual qualified in 

radiation protection procedures, equipped with a radiation 

monitoring device that continuously displays radiation dose 

rates in the area; who is responsible for controlling personnel 

exposure within the area, or 

 (ii) Be under the surveillance, as specified in the RWP or 

equivalent, while in the area, by means of closed circuit 

television, of personnel qualified in radiation protection 

procedures, responsible for controlling personnel radiation 

exposure in the area, and with the means to communicate with 

and control every individual in the area. 

 4. In those cases where options (2) and (3), above, are impractical or 

determined to be inconsistent with the "As Low As is Reasonably 

Achievable" principle, a radiation monitoring device that continuously 

displays radiation dose rates in the area. 
High Radiation Area 

5.7 

CEOG STS 5.7-4 Rev. 3.0, 03/31/04 

5.7 High Radiation Area 

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters 

from the Radiation Source or from any Surface Penetrated by the Radiation, but less 

than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface 

Penetrated by the Radiation (continued) 

 e. Except for individuals qualified in radiation protection procedures, or 

personnel continuously escorted by such individuals, entry into such areas 

shall be made only after dose rates in the area have been determined and 

entry personnel are knowledgeable of them. These continuously escorted 

personnel will receive a pre-job briefing prior to entry into such areas. This 

dose rate determination, knowledge, and pre-job briefing does not require 

documentation prior to initial entry. 

 f. Such individual areas that are within a larger area where no enclosure 

exists for the purpose of locking and where no enclosure can reasonably be 

constructed around the individual area need not be controlled by a locked 

door or gate, nor continuously guarded, but shall be barricaded, 

conspicuously posted, and a clearly visible flashing light shall be activated 

at the area as a warning device.