HOL TEC PILGRIM, LLC 

And HOL TEC DECOMMISSIONING INTERNATIONAL, LLC 

(PILGRIM NUCLEAR POWER STATION) 

DOCKET NO. 50-293 

RENEWED FACILITY LICENSE 

Renewed License No. DPR-35 

The Nuclear Regulatory Commission (the Commission) has found that: 

a. DELETED 

b. The facility will be maintained in conformity with the application, as amended, the 

provisions of the Act, and the rules and regulations of the Commission; and 

c. There is reasonable assurance (i) that the activities authorized by the renewed license 

can be conducted without endangering the health and safety of the public, and (ii) that 

such activities will be conducted in compliance with the rules and regulations of the 

Commission; and 

d. Holtec Pilgrim, LLC (Holtec Pilgrim) is financially qualified and Holtec Decommissioning 

International, LLC (HDI) is technically and financially qualified to engage in the activities 

authorized by this renewed license, in accordance with the rules and regulations of the 

Commission; and 

e. Holtec Pilgrim and HDI have satisfied the applicable provisions of 10 CFR Part 140, 

"Financial Protection Requirements and Indemnity Agreements" of the Commission's 

regulations; and 

f. The issuance of this renewed license will not be inimical to the common defense and 

security or to the health and safety of the public; and 

g. After weighing the environmental, economic, technical, and other benefits of the facility 

against environmental costs and considering available alternatives, the issuance of this 

renewed license ( subject to the condition for protection of the environment set forth 

herein) is in accordance with 10 CFR Part 51 of the Commission's regulations and all 

applicable requirements of said regulations have been satisfied. 

h. DELETED 

Amendment No. 250 Renewed License No. DPR-35 
- 2 -

Facility Operating License No. DPR-35, dated June 8, 1972, issued to the Boston Edison 

Company (Boston Edison) is hereby amended in its entirety, pursuant to an Initial Decision 

dated September 13, 1972, by the Atomic Safety and Licensing Board, to read as follows: 

1. This renewed license applies to the Pilgrim Nuclear Power Station, a single cycle, forced 

circulation, boiling water nuclear reactor and associated electric generating equipment 

(the facility), owned by Holtec Pilgrim and maintained and operated for decommissioning 

by HDI. The facility is located on the western shore of Cape Cod Bay in the town of 

Plymouth on the Holtec Pilgrim site in Plymouth County, Massachusetts, and is 

described in the "Final Safety Analysis Report," as supplemented and amended. 

2. Subject to the conditions and requirements incorporated herein, the Commission hereby 

licenses: 

A. Pursuant to the Section 104b of the Atomic Energy Act of 1954, as amended (the 

Act) and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," a) 

Holtec Pilgrim to possess, a_nd b) HDI to possess, maintain, and decommission 

the facility at the designated location on the Pilgrim site; 

B. HDI, pursuant to the Act and 10 CFR 70, to possess at any time special nuclear 

material that was used as reactor fuel, in accordance with the limitations for 

storage, as described in the Final Safety Analysis Report, as supplemented and 

amended; 

C. HDI, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess 

and use at any time any byproduct, source or special nuclear material as sealed 

neutron sources that were used for reactor startup, sealed sources that were 

used for calibration of reactor instrumentation and are used in radiation 

monitoring equipment, and as fission detectors in amounts as required; 

D. HDI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess 

and use in amounts as required any byproduct, source or special nuclear 

material without restriction to chemical or physical form, for sample analysis or 

instrument calibration or associated with radioactive apparatus or components; 

and 

E. HDI, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not 

separate, such byproduct and special nuclear materials as may be produced by 

the operation of the facility. 

3. This renewed license shall be deemed to contain and is subject to the conditions 

specified in the following Commission regulations; 10 CFR Part 20, Section 30.34 of 10 

CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR 

Part 50 and Section 70.32 of 10 CFR Part 70; and is subject to all applicable 

Amendment No. 250 Renewed License No. DPR-35 
- 3 -

provisions of the Act and to the rules, regulations, and orders of the Commission now or 

hereafter in effect; and is subject to the additional conditions specified below: 

A. DELETED 

B. Technical Specifications 

The Technical Specifications contained in Appendix A, as revised through 

Amendment No. 250, are hereby incorporated in the renewed license. The 

licensee shall maintain the facility in accordance with the Permanently Defueled 

Technical Specifications. 

C. Records 

D. 

E. 

F. 

G. 

HDI shall keep facility records in accordance with the requirements of the Technical 

Specifications. 

DELETED 

DELETED 

DELETED 

Physical Protection 

The licensee shall fully implement and maintain in effect all provisions of the 

Commission-approved physical security, training and qualification, and 

safeguards contingency plans including amendments made pursuant to 

provisions of the Miscellaneous Amendments and Search Requirements 

revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 

10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain 

Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim 

Nuclear Power Station Physical Security, Training and Qualification, and 

Safeguards Contingency Plan, Revision O" submitted by letter dated 

October 13, 2004, as supplemented by letter dated May 15, 2006. 

Amendment No. 252 Renewed License No. DPR-35 
- 4 -

H. DELETED 

I. DELETED 

J. Conditions Related to the Sale and Transfer 

K. 

(1) Deleted 

(2) Deleted 

(3) Deleted 

(4) Deleted 

(5) The Decommissioning Trust agreement(s) shall be in a form which is 

acceptable to the NRC and shall provide, in addition to any other clauses, 

that: 

a) Investments in the securities or other obligations of Holtec 

Pilgrim, Holtec International, their affiliates, subsidiaries or 

associates, or their successors or assigns shall be 

prohibited. In addition, except for investments tied to 

market indexes or other non-nuclear sector mutual funds, 

investments in any entity owning one or more nuclear 

power plants is prohibited. 

b) The Director, Office of Nuclear Reactor Regulation, shall 

be given 30 days prior written notice of any material 

amendment to the trust agreement(s). 

Mitigation Strategy License Condition 

Develop and maintain strategies for addressing large fires and explosions and 

that include the following key areas: 

(a) Fire fighting response strategy with the following elements: 

1. Pre-defined coordinated fire response strategy and guidance 

2. Assessment of mutual aid fire fighting assets 

3. Designated staging areas for equipment and materials 

4. Command and control 

5. Training of response personnel 

(b) Operations to mitigate fuel damage considering the following: 

1. Protection and use of personnel assets 

2. Communications 

3. Minimizing fire spread 

4. Procedures for implementing integrated fire response strategy 

5. Identification of readily-available pre-staged equipment 

6. Training on integrated fire response strategy 

7. Spent fuel pool mitigation measures 

Amendment No. 250 Renewed License No. DPR-35 
- 5 -

(c) Actions to minimize release to include consideration of: 

1. Water spray scrubbing 

2. Dose to onsite responders 

L. The licensee shall implement and maintain all Actions required by Attachment 2 

to NRC Order EA-06-137, issued June 20, 2006, except the last action that 

requires incorporation of the strategies into the site security plan, contingency 

plan, emergency plan and/or guard training and qualification plan, as appropriate. 

M. DELETED 

4. DELETED 

5. DELETED 

6. DELETED 

7. The information in the FSAR supplement, submitted pursuant to 10 CFR 54.21(d), as 

supplemented by Commitments Nos. 3, 8, 9, 13, 15, 18, 19, 21, 22, 24, 25, 26, 27, 28, 

30, 31, 33, 34, 35, 36, 37, 39, 40, 46, 51, and 52 of Appendix A of NUREG-1891, "Safety 

Evaluation Report Related to the License Renewal of Pilgrim Nuclear Power Station" 

dated June 2007, as supplemented, is henceforth part of the FSAR which will be 

updated in accordance with 10 CFR 50.71(e). 

The licensee may make changes to the programs and activities described in the FSAR 

supplement and Commitments Nos. 3, 8, 9, 13, 15, 18, 19, 21, 22, 24, 25, 26, 27, 28, 30, 

31, 33, 34, 35, 36, 37, 39, 40, 46, 51, and 52 of Appendix A of NUREG-1891, as 

supplemented, provided the licensee evaluates such changes pursuant to the criteria set 

forth in 10 CFR 50.59 and otherwise complies with the requirements in that section. 

8. DELETED 

9. DELETED 

Amendment No. 250 Renewed License No. DPR-35 
- 6 -

10. This license is effective as of the date of issuance and until the Commission notifies the 

licensee in writing that the license is terminated. 

Attachment: 

FOR THE NUCLEAR REGULATORY COMMISSION 

IRA/ 

Eric J. Leeds, Director 

Office of Nuclear Reactor Regulation 

Appendix A- Permanently Defueled Technical Specifications 

(Radiological) 

Date of Issuance: May 29, 2012 

Amendment No. 250 Renewed License No. DPR-35 
APPENDIX A 

TO 

FACILITY LICENSE DPR-35 

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS AND BASES 

FOR 

PILGRIM NUCLEAR POWER STATION 

PLYMOUTH,MASSACHUSETTS 

Holtec Pilgrim, LLC and Holtec Decommissioning International, LLC 

Amendment No. 250 
TABLE OF CONTENTS 

1.0 DEFINITIONS 1.0-1 

2.0 NOT USED 2.0-1 

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 

3.0 LIMITING CONDITION FOR 4.0 3/4.0-1 

OPERATION (LCO) 

APPLICABILITY 

BASES B3/4.0-1 

3.10 SPENT FUEL STORAGE 4.10 3/4.10-1 

C. Spent Fuel Pool Water Level C. 3/4.10-1 

BASES B3/4.10-1 

4.0 DESIGN FEATURES 4.0-1 

4.1 Site Location 4.0-1 

4.2 Not Used 4.0-1 

4.3 Spent Fuel Storaqe 4.0-1 

4.3.1 Criticality 4.0-1 

4.3.2 Drainaqe 4.0-2 

4.3.3 Capacity 4.0-2 

4.3.4 Heavv Loads 4.0-2 

5.0 ADMINISTRATIVE CONTROLS 5.0-1 

5.1 Responsibility 5.0-1 

5.2 Organization 5.0-2 

5.3 Facility Staff Qualifications 5.0-4 

5.4 Procedures 5.0-5 

5.5 Proqrams and Manuals 5.0-6 

5.6 Reporting Requirements 5.0-10 

5.7 Hiqh Radiation Area 5.0-11 

Amendment No. 250 
1.0 DEFINITIONS 

The succeeding frequently used terms are explicitly defined so that a uniform interpretation of 

the specifications may be achieved. 

ACTION 

CERTIFIED FUEL 

HANDLER 

IMMEDIATE 

LIMITING CONDITIONS 

FOR OPERATION (LCO) 

NON-GERTI FIED 

OPERATOR 

SURVEILLANCE 

FREQUENCY 

SURVEILLANCE 

INTERVAL 

Amendment No. 250 

ACTION shall be that part of a specification which prescribes remedial 

measures required under designated conditions. 

A CERTIFIED FUEL HANDLER is an individual who complies with the 

provisions of the CERTIFIED FUEL HANDLER Training and 

Retraining Program. 

IMMEDIATE means that the required action will be initiated as soon as 

practicable considering the safe maintenance of the facility and the 

importance of the required action. 

The LIMITING CONDITIONS FOR OPERATION specify the minimum 

acceptable levels of system performance necessary to assure safe 

maintenance of the facility. When these conditions are met, the facility 

can be maintained safely and abnormal situations can be safely 

controlled. 

Failure to meet a Surveillance, whether such failure is experienced 

during the performance of the Surveillance or between performances 

of the Surveillance, shall be considered a failure to meet the LCO. 

A NON-CERTIFIED OPERATOR is a non-licensed operator who 

complies with the qualification requirements of Specification 5.3.1, but 

is not a CERTIFIED FUEL HANDLER. 

Each Surveillance Requirement shall be performed within the specified 

SURVEILLANCE INTERVAL with a maximum allowable extension not 

to exceed 25 percent of the specified SURVEILLANCE INTERVAL. 

The SURVEILLANCE FREQUENCY establishes the limit for which the 

specified time interval for Surveillance Requirements may be 

extended. It permits an allowable extension of the normal surveillance 

interval to facilitate surveillance schedule and consideration of facility 

conditions that may not be suitable for conducting the surveillance; 

e.g., transient conditions or other ongoing surveillance or maintenance 

activities. It is not intended that this provision be used repeatedly as a 

convenience to extend surveillance intervals beyond that specified. 

This limitation of this definition is based on engineering judgment and 

the recognition that the most probable result of any particular 

surveillance being performed is the verification of conformance with 

the Surveillance Requirements. This provision is sufficient to ensure 

that the reliability ensured through surveillance activities is not 

significantly degraded beyond that obtained from the specified 

surveillance interval. 

The SURVEILLANCE INTERVAL is the calendar time between 

surveillance tests to be performed to confirm that a parameter is within 

limits. 

1.0-1 
2.0 NOT USED 

Not Used 

Amendment No. 250 2.0-1 
3.0 NOT USED 

Not Used 

Amendment No. 250 3/4.0-1 
I . a

4.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

4.0.1 Not Used

4.0.2 Not Used

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

specified Surveillance 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 Surveillance 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.

Amendment 2W2-4-l , 229 3/4.0-2 .1
3/4.10 SPENT FUEL STORAGE 

LIMITING CONDITION FOR OPERATION 

3.10 SPENT FUEL STORAGE 

Applicability: 

Applies to the storage of spent fuel. 

Objective: 

To ensure safe storage of spent fuel. 

Specification: 

A. Not Used 

B. Not Used 

C. Spent Fuel Pool Water Level 

Whenever irradiated fuel is stored 

in the spent fuel pool, the pool 

water level shall be maintained at 

or above 33 feet. 

SURVEILLANCE REQUIREMENT 

4.10 SPENT FUEL STORAGE 

Applicability: 

Applies to the parameter which monitors 

the storage of spent fuel. 

Objective: 

To verify that spent fuel is being stored 

safely. 

Specification: 

A. Not Used 

B. Not Used 

C. Spent Fuel Pool Water Level 

Whenever irradiated fuel is stored in 

the spent fuel pool, the water level 

shall be recorded daily. 

Amendment No. 250 3/4.10-1 
4.0 

4.1 

DESIGN FEATURES 

Site Location 

Pilgrim Nuclear Power Station is located on the western shore of Cape Cod Bay in the Town 

of Plymouth, Plymouth County, Massachusetts and contains approximately 517 acres 

owned by Holtec Pilgrim as shown on FSAR Figures 2.2-1 and 2.2-2. The site boundary is 

posted and a perimeter security fence provides a distinct security boundary for the protected 

area of the station. 

The reactor (center line) is located approximately 1800 feet from the nearest property 

boundary. 

4.2 Not Used 

4.3 Spent Fuel Storage 

4.3.1 Criticality 

4.3.1.1 

4.3.2 Drainage 

The spent fuel storage racks are designed and shall be maintained with: 

a. Fuel assemblies having a maximum k-infinity of 1.32 for standard 

core geometry, calculated at the burnup of maximum bundle 

reactivity, and an average U-235 enrichment of 4.6 % averaged 

over the axial planar zone of highest average enrichment; and 

b. Kett s 0.95 if fully flooded with unborated water, which includes an 

allowance for uncertainties as described in the applicable section of 

the FSAR. 

The spent fuel storage pool is designed and shall be maintained to prevent 

inadvertent draining of the pool below elevation 115 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 3859 fuel assemblies. 

4.3.4 Heavy Loads 

a. Loads in excess of 2000 lb. shall be prohibited from travel over fuel 

assemblies in the spent fuel storage pool with the exception that heavy load 

handling over irradiated fuel in the Multi-Purpose Canister is permitted using 

a single-failure-proof handling system. 

b. No fuel which has decayed for less than 200 days shall be stored in racks 

within an arc described by the height of the cask around the periphery of the 

leveling platform during cask handling operations in the spent fuel pool or 

when a cask is in the spent fuel pool. 

Amendment No. 250 4.0-1 
5.0 ADMINISTRATIVE CONTROLS 

5.1 Responsibility 

Responsibility 

5.1 

5.1.1 The plant manager shall be responsible for overall facility 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 control room supervisor (CRS) shall be responsible for the shift command 

function. ' 

Amendment No. 177, 223, 246 5.0-1 
5.0 ADMINISTRATIVE CONTROLS 

5.2 Organization 

5.2.1 Onsite and Offsite Organizations 

Organization 

5.2 

Onsite and offsite organizations shall be established for facility staff and 

corporate management, respectively. The onsite and offsite organizations shall 

include the positions for activities affecting safety of the nuclear fuel. 

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 anq 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 

i:>ositions delineated in these Technical Specifications, shall be 

documented in the Pilgrim Station Final Safety Analysis Report (FSAR); 

b. The plant manager shall be responsible for overall safe operation of the 

facility and shall have control over those onsite activities necessary for 

safe storage and maintenance of the nuclear fuel; 

c. The specified corporate officer for Pilgrim shall have corporate 

responsibility for the safe storage and handling of nuclear fuel and shall 

take any measures needed to ensure acceptable performance of the 

staff in operating, maintaining, and providing technical support to the 

facility to ensure safe management of nuclear fuel; and 

d. The individuals who train the CERTIFIED FUEL HANDLERS, 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 ability to perform their 

assigned functions. 

5.2.2 Facility Staff 

The facility staff organization shall include the following: 

a. Each duty shift shall be composed of at least one control room 

supervisor and one NON-CERTIFIED OPERATOR. The NONCERTIFIED OPERATOR position may be filled by a CERTIFIED FUEL 

HANDLER. 

(continued) 

Amendment No. 477, 484, 223, 246 5.0-2 
5.0 ADMINISTRATIVE CONTROLS 

5.2 Organization (continued) 

5.2.2 Facility Staff (continued) 

b. At least one person qualified to stand watch in the control room (NONCERTIFIED OPERATOR or CERTIFIED FUEL HANDLER) shall be 

present in the Control Room when nuclear fuel is stored in the spent 

fuel pool. 

c. Oversight of fuel handling operations shall be provided by a 

CERTIFIED FUEL HANDLER. 

d. Shift crew composition may be less than the minimum requirement of 

5.2.2.a 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 and all of the following conditions 

are met: 

1) No fuel movements are in progress; 

2) No movement of loads over fuel are in progress; and 

3) No unmanned shift positions during shift turnover shall be 

permitted while the shift crew is less than the minimum. 

e. Not Used 

f. An individual qualified in radiation protection procedures shall be on site 

during fuel handling operations and during movement of heavy loads 

over the fuel storage racks. 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. 

g. Not Used 

h. The control room supervisor shall be a CERTIFIED FUEL HANDLER. 

i. Not Used 

Amendment No. 250 5.0-3 
5.0 ADMINISTRATIVE CONTROLS 

5.3 Facility Staff Qualifications 

Facility Staff Qualifications 

5.3 

5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications 

of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the 

Quality Assurance Program Manual (QAPM). 

5.3.2 An NRC approved training and retraining program for CERTIFIED FUEL 

HANDLERs shall be maintained. 

PNPS 5.0-4 Amendment No. 47+, ~. 246 
5.0 ADMINISTRATIVE CONTROLS 

5.4 Procedures 

5.4.1 Written procedures shall be established, implemented, and maintained covering 

the following activities: 

a. The procedures applicable to the safe storage of nuclear fuel 

recommended in Regulatory Guide 1.33, Revision 2, Appendix A, 

February 1978; 

b. Not Used 

c. Quality assurance for effluent and environmental monitoring; 

d. Fire Protection Program implementation; and 

e. All programs specified in Specification 5.5. 

Amendment No. 250 5.0-5 
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. 

c. Licensee initiated changes to the ODCM: 

1. Shall be documented and records of reviews performed shall be 

retained. This documentation shall contain: 

a. sufficient information to support the change(s) together with 

the appropriate analyses or evaluations justifying the 

change( s ), and 

b. 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; 

2. Shall become effective after the approval of the plant manager; 

and 

3. 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. 

( continued) 

Amendment No. 250 5.0-6 
5.0 ADMINISTRATIVE CONTROLS 

5.5 Programs and Manuals (continued) 

5.5.2 Not Used 

5.5.3 Not Used 

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: 

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 

to unrestricted areas, conforming to 10 CFR 50, Appendix I; 

e. Determination of cumulative 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; 

(continued) 

Amendment No. 250 5.0-7 
5.0 ADMINISTRATIVE CONTROLS 

5.5 Programs and Manuals (continued) 

5.5.4 Radioactive Effluent Controls Program (continued) 

g. Limitations on the dose rate resulting from radioactive material released in 

gaseous effluents from the site boundary to areas at or beyond the site 

boundary conforming to the following: 

1. For noble gases: Less than or equal to 500 mrem/yr to the whole 

body and less than or equal to 3000 mrem/yr to the skin, and 

2. For lodine-131, lodine-133, Tritium, and all radionuclides in 

particulate form with half-lives greater than 8 days: Less than or 

equal to 1500 mrem/yr to any organ. 

h. Limitations on the annual and quarterly air doses resulting from noble 

gases released in gaseous effluents to areas beyond the site boundary, 

conforming to 10 CFR 50, Appendix I; 

i. Limitations on the annual and quarterly doses to a member of the public 

from lodine-131, lodine-133, Tritium, and all radionuclides in particulate 

form with half lives > 8 days in gaseous effluents released 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. 

5.5.5 Not Used 

5.5.6 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: 

Amendment No. 250 

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. 

( continued) 

5.0-8 
5.0 ADMINISTRATIVE CONTROLS 

5.5 Programs and Manuals (continued) 

5.5.6 Technical Specifications (TS) Bases Program (continued) 

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 Specification 5.5.6b 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). 

Amendment No. 250 5.0-9 
5.0 ADMINISTRATIVE CONTROLS 

5.6 Reporting Requirements 

The following reports shall be submitted in accordance with 1 O CFR 50.4. 

5.6.1 Not Used 

5.6.2 Annual Radiological Environmental Operating Report 

5.6.3 

The Annual Radiological Environmental Operating Report covering the 

operation of the facility 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. 

The Annual Radiological Environmental Operating Report shall include a 

summary of 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. 

Radioactive Effluent Release Report 

The Radioactive Effluent Release Report covering the operation of the facility 

shall be submitted in accordance with 10 CFR 50.36a by May 15th of each year. 

The report shall include a summary of the quantities of radioactive liquid and 

gaseous effluents and solid waste released from the facility. The material 

provided shall be consistent with the objectives outlined in the ODCM and 

process control procedures and in conformance with 10 CFR 50.36a and 

10 CFR 50, Appendix I, Section IV.B.1. 

Amendment No. 250 5.0-10 
5.0 ADMINISTRATIVE CONTROLS 

5. 7 High Radiation Area 

5. 7 .1 Pursuant to 10 CFR 20, paragraph 20.1601 ( c ), in lieu of the requirements of 

10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which 

the intensity of radiation is > 100 mrem/hr but < 1000 mrem/hr, shall be 

barricaded and conspicuously posted as a high radiation area and entrance 

thereto shall be controlled by requiring issuance of a Radiation Work Permit 

(RWP). Individuals qualified in radiation protection procedures (e.g., radiation 

protection personnel) or personnel continuously escorted by such individuals 

may be exempt from the RWP issuance requirement during the performance of 

their assigned duties in high radiation areas with exposure rates 

~ 1000 mrem/hr, provided they are otherwise following facility radiation 

protection procedures for entry into such high radiation areas. 

Any individual or group of individuals permitted to enter such areas shall be 

provided with or accompanied by one or more of the following: 

a. A radiation monitoring device that continuously indicates the radiation 

dose rate in the area. 

b. A radiation monitoring device that continuously integrates the radiation 

dose rate in the area and alarms when a preset integrated dose is 

received. Entry into such areas with this monitoring device may be 

made after the dose rate levels in the area have been established and 

personnel are aware of them. 

c. An individual qualified in radiation protection procedures with a 

radiation dose rate monitoring device, who is responsible for providing 

positive control over the activities within the area and shall perform 

periodic radiation surveillance at the frequency specified by the 

radiation protection manager in the RWP. 

5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels 

~ 1000 mrem/hr shall be provided with locked or continuously guarded doors to 

prevent unauthorized entry and the keys shall be maintained under the 

administrative control of the control room supervisor on duty or radiation 

protection supervision. Doors shall remain locked except during periods of 

access by personnel under an approved RWP that shall specify the dose rate 

levels in the immediate work areas and the maximum allowable stay times for 

individuals in those areas. In lieu of the stay time specification of the RWP, 

direct or remote (such as closed circuit TV cameras) continuous surveillance 

may be made by personnel qualified in radiation protection procedures to 

provide positive exposure control over the activities being performed within the 

area. 

(continued) 

5. 7 High Radiation Area ( continued) 

Amendment No. 250 5.0-11 
5.0 ADMINISTRATIVE CONTROLS 

5.7.3 For individual high radiation areas with radiation levels of> 1000 mrem/hr, 

accessible to personnel, that are located within large areas such as reactor 

containment, where no enclosure exists for purposes of locking, or that cannot 

be continuously guarded, and where no enclosure can be reasonably 

constructed around the individual area, that individual area shall be barricaded 

and conspicuously posted, and a flashing light shall be activated as a warning 

device. 

Amendment No. 250 5.0-12