NUREG-1301 

Offsite Dose Calculation 

Manual Guidance: Standard 

Radiological Effluent Controls 

for Pressurized Water Reactors 

Generic Letter 89-01, Supplement No. 1 

Date poblished: April 1991 

W. W. Meinke, T. H. Ekig 

Division of Radiation Protection and Emergency Preparedness 

Office of Nuclear Reactor Regulation 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555 
-- 

ABSTRACT 

This report contains guidance which may be voluntarily used by licensees who 

choose to implement the provision of Generic Letter 89-01, which allows Radiological Effluent Technical Specifications (RETS) to be removed from the main 

body of the Technical Specifications and placed in the Offsite Dose Calculation 

Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, 

Controls for effluent monitoring instrumentation, Controls for effluent releases, 

Controls for radiological environmental monitoring, and the basis for Controls. 

Guidance on the formulation of RETS has been available in draft form (NUREG-0472 

and -0473) for a number of years; the current effort simply recasts those RETS 

into Standard Radiological Effluent Controls for application to the ODCM. Also 

included for completeness are: 

4 Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of 

Generic Letter 89-01. 

(1) radiological environmental monitoring program 

uidance previously which had been available as a Branch Technical Position 

iii 
PREFACE 

This compilation of Standard Radiological Effluent Controls (SREC) contains all 

of the controls addressed in Generic Letter 89-01, to be incorporated into a 

licensee's Offsite Dose Calculation Manual (ODCM) at the time the procedural 

detai 1s of the current Radiological Effluent Technical Specifications (RETS) 

are transferred out of the licensee's Technical specifications (TS). It has 

been developed by recasting the RETS of the most current Westinghouse Standard 

Technical Specifications (W STS) from the I'LCO'I format into the "Controls" format of an ODCM entry. SinEe the RETS guidance for Babcock and Wilcox and Combustion Engineering plants are identical to that for Westinghouse plants, the 

- W SREC are applicable to all Pressurized Water Reactors. 

The following W SREC provide the latest version of staff guidance, and document 

current practiEe in the operating procedures required by 10 CFR 20.106, 40 CFR 

Part 190, 10 CFR 50.36(a), and Appendix I to 10 CFR Part 50. This document contains no new requirements and its use is completely voluntary. 

V 
TA6LE OF CONTENTS 

ABST~CT................ ............................... PREFACE.. .............................................. FOREWORD.................. ............................. 1 DEFINITIONS. ........................................... 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS. ................ 3/4.0 Applicability .......................................... 3/4.3 Instru~entation........................................ 

3/4.11 Radioactive Effluents.. ................................ 3/4.12 Radiological Environmental Monitoring. ................. 3 /4 BASES........ .......................................... 

APPENDIX A: 

APPENDIX B: General Contents of the Offsite Dose 

Radiological Assessment Branch Technical 

Position, Revision 1, November 1979 

Ca 1 cu lat ion Manua 1 

APPENDIX C: Generic Letter 89-01 

Page 

iii 

V 

c13 

c43 

t-82 1 

I 

- W SREC vii 
FOREWORD 

RADIOLOGICAL EFFLUENT TECHNICAL SPEC IF I CATIONS 

Licensee Technical Specification (TS) amendment requests for incorporation of 

Radiological Effluent Technical Specifications (RETS) pursuant to 10 CFR 50.36a 

and Appendix I to 10 CFR Part 50 were approved in the mid-1980s for most 

operating reactors licensed before 1979 (ORs). Plants licensed after 1979 

(NfOls), included the RETS as part of their initial Technical Specifications. 

By November 1987, the RETS were implemented by all licensees of operating power 

reactors. Detailed Safety Evaluation Reports (SERs) documented the acccptabflity of the plant-specific RETS of the ORs, while the acceptance of the RETS 

for the NTOLs followed the regular pattern of the Standard Technical Specifications (STS). Thus, for all operating plants, the compliance of the licensee 

with 10 CFR 50.36a and Appendix I to 10 CFR Part 50 is a matter of record. 

Early draft revisions of mde1 RETS, distributed to licensees in mid-1978, 

contained equations for dose calculations, setpofnt determinations and meteorological dispersion factors, as well as the procedural details for complying 

with Appendix I to IO CFR Part 50. In later revisions, including Revision 2 

used as the bench mark for the NRC staff's acceptance of OR RETS, the equations 

were removed and Incorporated into an Offsite Dose Calculation Manual (ODCM) 

prepared by the licensee and provided to NRC for review along with the proposed 

RETS. 

Early guidance for preparation of the Radiological Effluent Technical Specifications (RETS) and Offsite Dose Calculation Manual (ODCM) was published in 

NURE6-0133, "Preparation of Radiological Effluent Technical Specifications for 

Nuclear Power Plants," October 1978. Copies of mode1 RETS, however, have been 

available only in draft form as NURE6-0472, Revision 2, "Radiological Effluent 

Technical Specif ications for PWRs," February 1, 1980; NURE6-0473, Revision 2, 

"Radiological Effluent Technical Specifications for BURS," February 1 , 1980; 

and succeeding draft revisions. Staff guidance for the Radiological 

Environmental Monitoring Program is contained in the Radiological Assessment 

Branch Technical Posttion (RAB-BTP), originally fssued in March 1978 and 

upgraded by Revision 1 in November 1979 as a result of the accident at Three 

Mile Island. This Revision 1 to the RAB-BTP was forwarded to all operating 

reactor licensees in November 1979 and remafns in effect at the present time. 

Since this BTP was never incorporated into the Regulatory Guide System, a copy 

is reproduced in this document as Appendix A. Even though it has been used 

-extensively in reviewing ODCMs, guidance for the contents of the ODCN is found 

only in an appendix to a paper presented at an Atomic Industrial Forum conference in 1981, and has had only informal distribution since that time. 

OFFSITE DOSE CALCULATION MANUAL 

The potential for augmentatfon of e licensee's ODCM through transfer of the 

procedural details of the RETS following the guidance of Generic Letter 89-01, 

provides an opportunity to assemble in one set of documents the staff guidance 

for the ODCM. 

- W SREC 113 
The current overview guidance for development of the ODCM was prepared originally in July 1978 and revised in February 1979 after discussions with conmittees of the Atomic Industrial Forum. This guidance was made generally 

avaflable as "Appendix B - General Contents of the Offsite Dose Calculation 

Manual (ODCM) (Revision 1, February 1979)" to the paper authored by 

C. A. Willis and F. J. Congel, "Status of NRC Radiological Effluent Technical 

Specification Activities" presented at the Atomic Industrial Forum Conference 

on NEPA and Nuclear Regulation, October 4-7, 1981, Washington, D.C. A copy of 

this guidance that continues in effect to date, is reproduced in this document 

as Appendix B. 

During the discussions leading up to the implementation of the RETS by the ORs, 

it became important to record in a "living" document certain interpretations 

and understandings reached in these discussions. The ODCM thus became a 

repository for such interpretations, as well as for other information requested 

by the staff in connection with its evaluation of licensee's comnitments and 

performance under 10 CFR 50.36a and Appendix I to 10 CFR Part 50. 

TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM 

Recently, the NRC staff has examined the contents of the RETS in relation to 

the Conmission's Interim Policy Statement on Technical Specification Improvements. The staff has determined that programtic controls can be fmplenented 

in the Administrative Controls section of the Technical Specifications (TS) to 

satisfy existing regulatory requirements for RETS. At the same, time, the 

procedural detai 1s of the current TS on radioactive effluents and radiological 

environmental monitoring can be relocated to the Offsite Dose Calculation 

Manua 1 (ODCM) . To ,initiate the change, new programnatic controls for radioactive effluents and 

radiological environmental monitoring are incorporated in the TS to conform to 

the regulatory requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, 

and Appendix I to 10 CFR Part 50. The procedural details included in 

licensees' present TS on radioactive effluents, environmental monitoring, and 

associated reporting requirements will be relocated to the ODCM. Licensees 

will handle future changes to these procedural details in the ODCM under the 

administrative controls for changes to the ODCM. Detailed guidance to effect 

the transfer of the RETS to the ODCM is given in Generic Letter 89-01, reproduced in its entirety as Appendix C. 

' GUIDANCE FOR THE TRANSFER OF RETS ?O ODCM 

Enclosure 1 of Generic Letter (6L) 89-01 of Appendix B provides detailed 

guidance for the preparation of a license amendment request to Implement the 

transfer of RETS to ODCH. Page 1 of the enclosure states: 

"The NRC staff's intent in recomnending --- the relocation of procedural 

details of the current RETS to the ODCM is to fulfill the goal of the 

Comission Policy Statement for Technical Specification Improvements. 

is not the staff's intent to reduce the level of radiological effluent 

control. 

RETS consistent with regulatory requirements and allow relocation of the 

procedural details of current RETS to the ODCM." 

It 

Rather, this amendment wi 11 provide programnatic controls for 

- W SREC 
Page 2 of Enclosure 1 states: 

"...the procedural details covered in the licensee's current RETS, 

consisting of the limiting conditions for operation, their applicability, remedial actions, surveillance requirements, and the Bases 

section of the TS for these requirements, are to be relocated to the 

OOCM --- in a manner that ensures that these details are incorporated 

in plant operating procedures. The NRC staff does not intend to repeat 

technical reviews of the relocated procedural detai Is because their 

consistency with the applicable regulatory requirements is a matter 

of record from past NRC reviews of RETS." 

DISCUSS ION 

For the purpose of the transfer described in GL 89-01 of Appendix B, the RETS 

will consist of the specifications from the STS listed in Enclosure 2 of Appendix B of GL 89-01. Licensees with nonstandard TS should consider the analogous 

TS in their format. 

It is suggested that the most straightforward method of transferring a licensee's 

comitments in the RETS to the ODCM in accordance with GL 98-01 is to recast 

the RETS in the licensee's present TS from the "Limiting Condition for Operation (LCO)" format of the TS into the "Controls" format of the ODCM entry. The 

accompanying package provides an example of this recasting into Standard Radiological Effluent Controls (SREC) from the ride1 RETS for Pressurized Water 

Reactors (PWRs). This recasting is in format only. The TS pages have been 

transferred to the ODCM without change except for the substitution of "Controls" 

for 'LCO." Plants that have RETS that closely follow the STS format will be 

able to use the accompanying examples directly as guidance. For plants wlth 

nonstandard RETS, the transfer of TS commitments to the ODCH should be made 

similarly page by page, again with the substitution of "Controls" for "LCO." 

This NUREG report contains no new requirements; licensee implementation of this 

guidance is completely voluntary. 

SUMMARY 

As part of the license amendment request for TS improvement relative to the 

RETS, a licensee confirms that the guidance of Generic Letter 89-01 has been 

followed. This guidance includes the following: 

"The procedura 1 detai 1 s covered in the 1 i censee' s current RETS, consisting of the limiting conditions for operation, their applicability, 

remedial actions, survei 1 lance requirements, and the Sases section of 

the TS for these requirements, are to be relocated to the ODCM --- in 

a manner that ensures that these details are incorporated in plant 

operating procedures. " 

The Standard Radiological Effluent Controls (SREC) compiled in this report 

document current staff practice in the operating procedures required by 

10 CFR 2G.106, 40 CFR Part 190, 10 CFR 50.36(a), and Appendix I to 10 CFR 

Part 50. Thus they contain all of the controls required by Generic letter 

89-01, to be incorporated into a licensee's ODCM at the time the procedural 

details of the current RETS are transferred out of' the licensee's TS. 

- W SREC c3i 
- W SREC 

SECTION 1.0 

DEFINITIONS 

143 
1.0 DEFINITIONS 

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

throughout these Controls. 

ACTION 

1.1 ACTION shall be that part of a Control that prescribes remedial measures 

required under designated conditions. 

ANALOG CHANNEL OPERATIONAL TEST 

1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated 

signal into the channel as close to the sensor as practicable to verify 

OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL 

OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that the setpoints are within the required 

range and accuracy. 

CHANNEL CALIBRATION 

1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the 

channel such that it responds within the requlred range and accuracy to known 

values of input. The CHANNEL CALIBRATION shall encompass the entire channel 

including the sensors and alarm, interlock and/or trip functions and may be 

performed by any series of sequential, overlapping, or total channel steps 

such that the entire channel 4s calibrated. 

CHANNEL CHECK 

1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior 

during operation by observation. 

possible, comparison of the channel indication and/or status wfth other 

indications and/or status derived from independent instrument channels 

measuring the same parameter. 

This determination shall include, where 

- W SREC c53 
DEFINITIONS 

DOSE EQUIVALENT 1-131 . 

1.10 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microCurie/grarn) 

which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. dose conversion factors used for this calculation shall be those listed in 

[Table 111 of TID-14844, "Calculation of Distance factors for Power and Test 

Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109, Revision 1, 

October 1977 3. 

The thyroid 

- W SREC C63 
DEFINITIONS 

FREQUENCY NOTATION 

1.13 The FREQUENCY NOTATION specified for the performance of Surveillance 

RequSrements shall correspond to the intervals defined in Table 1.1. 

WEMBER(S) OF THE PUBLIC 

1.16 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees 

of the licensee, its contractors, or vendors. 

are persons who enter the site to service equipment or to make deliveries. 

This category does include persons who use portions of the site for recreational, occupational, or other purposes not assqciated with the plant. 

OFFSITE DOSE CALCULATION MANUAL 

1.17 The OFFSITE DOSE CALCULATION MANUAL (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 AlaMrip Setpoints, and in the conduct of the 

Environmental Radiological Monitoring Program. The ODCM shall also contain 

(1) the Radioactive Effluent Controls and Radiological Environmental Monitoring 

Programs required by Section 6.8.4 and (2) descriptions of the information that 

should be included in the Annual Radiological Environmental Operating and 

Semiannual Radioactive Eff iuent Release Reports required by TS 6.9.1.3 and 

6.9.1.4. 

Also excluded from this category 

- U SREC 
DEFINITIONS 

OPERABLE - OPERABILITY 

1.18 A system, subsystem, train, component or device shall be OPERABLE or 

have OPERABILITY when it is capable of performing its specified function(s), 

and when a1 I necessary attendant instrumentation, controls, electrjcal power, 

cooling or seal water, lubricatfon or other auxiliary equipment that are 

required for the system, subsystem, train, component, or device to perform its 

function(s) are also capable of performing their related support function(s). 

OPERATIONAL MODE - MODE 

1.19 An OPERATIONAL MODE ($.e., MODE) shall correspond to any one inclusive 

combination of core reactivity condition, power level, and average reactor 

coolant temperature specified in Table 1.2 of the [plant name] TS. 

PURGE - PURGING 

1.23 PURGE or PURGING shall be any controlled process of discharging air or gas 

from a confinement to maintain temperature, pressure, humidity, concentration 

or other operating condition, in such a manner that replacement air or gas is 

requ i red to puti fy the conf i nement. 

W - SREC 181 
DEFINTTIONS 

RATED THERMAL POWER 

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

the reactor coolant of - Mwt. 

REPORTABLE EVENT 

1.27 A REPORTABLE EVENT shall be any of those conditions specified in 

Section 50.73 of 10 CFR Part 50. 

SITE BOUNDARY 

1.30 The SITE BOUNDARY shall be that line beyond which the land is neither 

owned, nor leased, nor otherwise controlled by the licensee. 

W SREC 193 I 
DEFINITIONS 

SOURCE CHECK 

1.33 A SOURCE CHECK shall be the qualitative assessment of channel response 

when the channe’l sensor is exposed to a source of increased radioactivity. 

THERMAL POWER 

1.35 THERMAL POWER shall be the total reactor core heat transfer rate to the 

reactor cool ant. 

- w SREC [IO3 
UNRESTRICTED AREA 

1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY 

access to which is not controlled by the licensee for purposes of protection of 

individuals from exposure to radiation and radioactive materials, or any area 

within the SITE BOUNDARY used for residential quarters or for industrial, 

commercial, institutional, and/or recreational purposes. 

VENTILATION EXHAUST TREATMENT SYSTEM 

1.39 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and 

installed to reduce gaseous radioiodine or radioactive material in particulate 

form in effluents by passing ventilation or vent exhaust gases through charcoal 

adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. 

Such a system is not considered to have any effect on noble gas effluents. 

Engineered Safety Features Atmospheric Cleanup Systems are not considered 

to be VENTILATION EXHAUST TREATMENT SYSTEM components. 

V€NT I NG 

1.40 VENTING shall be the controlled process of discharging air or gas from a 

conffnement to maintain temperature, pressure, humidity, concentration, or other 

operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply 

a VENTING process. 

WASTE GAS HOLDUP SYSTEM 

1.41 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to 

reduce radioactive gaseous effluents by collecting Reactor Coolant System 

offgases frola the Reactor Coolant System and providing for delay or holdup 

for the purpose of reducing the total radioactivity prior to release to the 

environment. 

- W SREC 
NOT AT I ON 

S 

D 

W 

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SA 

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s/u 

N. A. 

P 

TABLE 1.1 

FREQUENCY NOTATION 

FREQUENCY 

At least once per 12 hours. 

At least once per 24 hours. 

At least once per 7 days. 

At least once per 31 days. 

At least once per 92 days. 

At least once per 184 days. 

At least once per 18 months. 

Prior to each reactor startup. 

Not applicable. 

Completed prior to each release. 

W c SREC c121 
- MODE 

TABLE 1.2 

OPERATIONAL MODES 

REACTIVITY % RATED 

CONDITION, Keff THERMAL POWER* 

1. POWER OPERATION - > 0.99 > 5% 

2. STARTUP - > 0.99 - < 5% 

3. HOT STANDBY < 0.99 0 

4. HOT SHUTDOWN < 0.99 0 

5. COLD SHUT DO^ c 0.99 0 

6. REFUELING** - 0.95 0 

AVERAGE COOLANT 

TEMPERATURE 

- 350°F 

- > 35O0f 

- > 350'f 

350'F > TaVg 

> 200°F 

*Exc 1 ud i ng decay heat . 

tensioned or with the head removed. 

**Fuel in the reactor vessel with the vessel head closure bolts less than fully 

- W SREC 1137 
- W SREC 

SECTIONS 3.0 AND 4.0 

CONTROLS 

AND 

SURVEILLANCE REQUIREMENTS 

c141 
314 CONTROLS AND SURVEILLANCE REQUIREMENTS 

314.0 APPLICABILITY 

3.0.1 Compliance with the Controls contained in the succeeding controls is 

required during the OPERATIONAL MODES or other conditions specified therein; 

except that upon failure to meet the Control, the associated ACTION requirements shall be met. 

3.0.2 Noncompliance with a control shall exist when the requirements of the 

Control and associated ACTION requirements are not met within the specified 

time intervals. If the Control is restored prior to expiration of the 

specified time intervals, completion of the ACTION requirements is not 

required. 

3.0.3 When a Control is not met, except as provided in the associated ACTION 

requirements, within 1 hour action shall be initiated to place the unit in a 

HODE in which the control does not apply by placing it, as applicable, in: 

a. At least HOT STANDBY within the next 6 hours, 

b. At least HOT SHUTDOWN within the following 6 hours, and 

c. At least COLD SHUTDOWN within the subsequent 24 hours. 

Where corrective measures are completed that permit operation under the ACTION 

requirements, the action may be taken in accordance with the specified time 

limits as measured from the time of failure to meet the Control. Exceptions 

to these requirements are stated in the individual controls. 

This control is not applicable in MODE 5 or 6. 

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not 

be made when the conditions for the Control are not met and the associated 

ACTION requires a shutdown if they are not met within a specified the 

fnterval. Entry into an OPERATIONAL MODE or speciffed condition may be made 

in accordance with ACTION requirements when conformance to them permits 

continued operation of the facility for an unlimited period of time. 

provision shall not prevent passage through or to OPERATIONAL MODES as 

required to comply with ACTION requirements. 

requirements are stated in the individual specifications. 

This 

Exceptions to these 

- W SREC c151 
APPLICABILITY 

SURVEILLANCE REQUIREMENTS 

4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES 

or other conditions specified for individual Controls unless otherwise stated 

in an individual Surveillance Requirement. 

4.0.2 Each Surveillance Requirement shall be performed within the specified 

time interval with: 

a. A maximum allowable extension not to exceed 25% of the surveillance 

interval , but 

b. The cbmbined time interval for any three consecutive surveillance 

intervals shall not exceed 3.25 times the specified surveillance 

interval . 

4.0.3 Failure to perform a Survefllance Requirement within the allowed 

surveillance interval, defined by Specification 4.0.2, shall constitute 

noncompliance with the OPERABILITY requirements for a Control. 

limits of the ACTION requirements are applicable at the time It is identified 

that a Surveillance Requirement has not been performed. 

requirements may be delayed for up to 24 hours to permit the completion of 

the surveillance when the allowable outage time limits of the ACTION 

requirements are less than 24 hours. 

to be performed on inoperable equipment. 

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be 

made unless the Survei 1 lance Requirement(s) associated with the Control has 

been performed within the stated surveillance interval or as otherwise 

specified. 

OPERATIONAL MODES as required to comply wlth ACTION requirements. 

to these requirements are stated in the individual controls. 

The time 

The ACTION 

Surveillance Requirements do not have 

u 

This provision shall not prevent passage through or to 

Exceptions 

- W SREC 
INSTRUMENTATION 

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 

CONTROLS 

3.3.3.10 In accordance with [plant name] TS 6.8.4.9.1). the radioactive liquid 

effluent monitoring instrumentation channels shown in Table 3.3-12 shall be 

OPERABLE with their Alardfrip Setpoints set to ensure that the limits of 

Control 3.11.1.1 are not exceeded. 

shall be determined and adjusted in accordance with the methodology and 

parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). 

The Alarmnrip Setpoints of these channels 

APPLICABILITY: At all times. 

- ACT I ON: 

8. 

b. 

C. 

With a radioactive liquid effluent monitoring instrumentation channel 

Alarmflrip Setpoint less conservative than required by the above 

control, immediately suspend the release of radioactive liquid 

effluents monitored by the affected channel, or declare the channel 

inoperable, or change the setpoint so it is acceptably conservative. 

With less than the minimum number of radioactive liquid effluent 

monitoring instrumentation channels OPERABLE, take the ACTION shown 

in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE 

status within 30 days and, if unsuccessful, explain in the next 

Semiannual Radioactive Effluent Release Report pursuant to Control 

6.9.1.4 why this inoperability was-not corrected in a timely manner. 

The provlsions of Controls 3.0.3 and 3.0.4 ape not applicable. 

Report all deviations in the Semiannual Radioactive Effluent Release 

Report. 

SURVEf LLkNCE REQUIREMENTS 

9.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel 

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE 

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies 

shown in fable 4.3-8. 

- W SREC C171 
TABLE 3.3-12 

RADIOACTXVE LIQUID EFFLUWT MONITORING INSTRUMENTAT ION 

INSTRUM€NT 

1. Radioactivity Monitors Providing Alarm and 

Automatic Termination of Release 

MINIMUM 

CHANNELS 

OPERABLE 

a. Liquid Radwaste Effluent Line 1 

b. Steam Generator Blowdown Effluent Line 1 

c. Turbine Building (Floor Drains) Sumps Effluent Line 1 

n A 2. Radioactivity Monitors Providing Alarm But Not Providing 

(x, Automatic Termination of Release U 

a, Service Water System Effluent line 

b. Component Cooling Water System Effluent Line 

3. Continuous Composite Samplers and Sampler Flow Monitor 

a. Steam Generator Blowdorm Effluent Cine 

(alternate to Item 1.b.) 

b. Turbine Building Sumps Effluent Line 

(alternate to Item 1.c.) 

4. Flaw Rate Measurement Devices 

a. Liquid Radwaste Effluent Line 

b. Steam Generator Blowdown Effluent Line 

c. Discharge Canal 

1 

1 

ACT I ON 

35 

36 

36 

37 

37 

36 

36 

38 

38 

38 
IS 

VI 

r) 

R 

TABLE 3.3-12 (Continued) 

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUHEMATION 

INSTRUMENT 

MINIMUM 

CHANNELS 

OPERABL€ 

5. Radioactivl ty Recorders* 

a. Liquid Radwaste Effluent Line 1 

b. Steam Generator Blowdom Effluent Line 1 

*Required only if AlaMrip Setpoint is based on recorder-controller. n 

ro 

d 

u 

ACTIOff 

35 

39 
TABLE 3.3-12 (Continued) 

ACTION STATEMENTS 

ACTION 35 - With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

this pathway may continue provided that prior to initiating a 

release: 

a. At ?east two independent samples are analyzed in accordance 

wi tn Control 4.11.1.1.1, and 

b. At least two technically qualified members of the facility 

staff independently verify the release rate calculations 

and discharge line valving. 

Otherwise, suspend release of radioactive effluents via this 

pathway . 

With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

this pathway may continue provided grab samples are analyzed 

for radioactivity at a lower limit of detection of no more than 

io-' microCurie/ml: 

ACTION 36 - 

a. At least once per 12 hours when the specific activity of 

the secondary coolant is greater than 0.01 microCurie/gram 

DOSE EQUJVALENT 1-131, or 

b. At least once per 24 hours when the specific activfty of 

the secondary coolant is less than or equal to 

0.01 microCurie/gram DOSE EQUIVALENT 1-131. 

ACTION 37 - With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

this pathway may continue provided that, at least once per 

12 hours, grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 

10-7 nicroCurie/ml. 

ACTION 38 - With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

this pathway may continue provided the flow rate is estimated 

at least once per 4 hours during actual releases. 

mance curves generated in place may be used to estimate flow. 

With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

this pathway may continue provided the radioactivity level is 

determined at least once per 4 hours during actual releases. 

Pump perforACTION 39 - 

- W SREC c201 
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TABLE 4.3-8 

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTAT ION SURVEILLANCE REQUIREMENTS 

INSTRUMENT 

1. Radioactivi ty Moni tors Providing 

Alarn and Automatic Termination 

of Release 

ANALOG 

CHANNEL 

CHANNEL SOURCE CHANNEL OPERATIONAL 

CHECK CHECK CALIBRATION TEST 

a. Liquid Radwaste Effluent Line D 

b. Steam Generator Blowdown Effluent Line D 

n c. Turbine Building (Floor Drains) Sms 

Radioactivity Monitors Providing Alarm But 

Effluent Line D r# 

4 

U 

2. 

Not Providing Autamatic Termination 

of Release 

a. Service Water System Effluent Line 0 

b. Component Cooling Water System Effluent 

line 0 

3. Continuous Composite Samplers and Sampler 

Flow Monitor 

a. Stem Generator Blowdown Effluent Line 0 

(alternate to Item 1.b.) 

b. Turbine Building Sumps Effluent Line O 

(alternate to Item 1.c.) 

N. A. R 

N. A. R 

Q 

Q 
I* 

v, 

;o 

m 

0 

TABLE 4.3-8 (Continued) 

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 

\ 

INSTRUMENT 

4. Flow Rate Measurement Devices 

ANALOG 

CHANNEL 

CHANNEL SOURCE CHANNEL OPERATIONAL 

CHECK CHECK CALI BRAT ION TEST 

a. liquid Radwaste Effluent Cine Q(4) N.A. R Q 

b. Steam Generator Blowdm Effluent Line Q(4) N. A. R Q 

c. Discharge Canal Q(4) N. A. R Q 

n 

N 

5. Radioactivity Recorded 

U 

a. Liquid Radwaste Effluent Line D N. A. R Q 

b. Steam Generator Blowdown Effluent Line . 0 N. A. R Q 

*Required only if Alarmnrip Setpoint In based on recorder-controller. 
TABLE 4.3-8 (Continuedl 

TABLE NOTATIONS 

(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic 

isolation of this pathway and control room alarm annunciation occur if any 

of the following conditions exists: 

a. Instrument indicates measured levels above the Alamnrip Setpoint, or 

b. Circuit failure, or 

c. Instrument indicates a downscale failure, or 

d. Instrument controls not set in operate mode. 

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control 

room alarm annunciation occurs if any of the following conditions exists: 

a. Instrument indicates measured levels rbove the Alarm Setpoint, or 

b. Circuit failure, or 

c. Instrument indicates a downscale failure, or 

d. Instrument controls not set in operate mode. 

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of 

the reference standards certified by the National Bureau of Standards (NBS) 

or using standards that have been obtained from suppliers that participate 

in measurement assurance activities with NBS. These standards shall permit 

calibrating the system over its intended range of energy and measurement 

range. For subsequent CHANNEL CALIBRATION, sources that have been related 

to the initial calibration shall be used. 

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods 

of release. 

days on which continuous, periodic, or batch releases are made. 

CHANNEL CHECK shall be made at least once per 24 hours on 

W - SREC c233 
INSTRUMENTATION 

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 

CON1 RO LS 

3.3.3.11 

effluent monitoring instrumentation channels shown in Table 3.3-13 shall be 

OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of 

Control 3.11.2.1 are not exceeded. 

shall be determined and adjusted in accordance with the methodology and 

parameters in the DDCM. 

APPLICABILITY: As shown in Table 3.3-13 

In accordance with [plant name) TS 6.8.4. g. 1) , the radioactive gaseous 

The Alarm/Trip Setpoints of these channels 

ACTION: 

a. 

b. 

C. 

With a radioactive gaseous effluent monitoring instrumentation 

channel Alarm/Trip Setpoint less conservative than required by the 

above control, immediately suspend the release of radioactive 

gaseous effluents monitored by the affected channel, or declare the 

channel inoperable, or change the setpoint so it is acceptably 

conservative. 

With less than the minimum number of radioactive gaseous effluent 

monitoring instrumentation channels OPERABLE, take the ACTION shown 

in Table 3.3-13. 

status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Control 

6.9.1.4 why this inoperability was not corrected in a timely 

manner. 

Restore the inoperable instrumentation to OPERABLE 

The provisions of Controls 3.0.3 and 3.0.4 are not rpplicable. 

Report a1 1 deviations in the Semiannual Radioactive Effluent Release 

Report. 

SURVEILLANCE REQUIREMENTS 

4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel 

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE 

CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown 

in Table 4.3-9. 

- W SREC [243 
TABLE 3.3-13 

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMEMTATION 

MINIMUM CHANNELS 

INSTRUMENT OPERABLE APPLICAB I LITY ACT ION 

1. WASTE GAS HOUlUP SYSTEM 

a. Noble Gas Activity Monitor - 

Providing Alarm and Automatic 

Termination of Release 

b. Iodine Sampler 

e. Particulate Sampler 

n d. Effluent System Flow Rate 

R) kasuring Device 

cn 

Y 

e. Sampler Flow Rate Measuring Device 

1 

1 

45 

51 

51 

46 

46 

2A. NOT USED 
IS 

rn 

W 

m 

0 

INSTRUMENT 

28. NOT USED 

TABLE 3.3-13 (Continuedl 

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENT AT ION 

MINIMUM CHANNELS 

OPERABLE APPLICABILITY ACT ION 

n 

h, 

U QI 3. Condenser Evacuation System 

a. Noble Gas Activity Monitor 

b. Iodine Sampler 

c. Particulate Sampler 

d. Flow Rate Monitor 

e. Sampler Flow Rate Monitor 

47 

51 

51 

46 

46 
If 

n 

Iu 

w 

U 

TABLE 3.3-13 (Continuedl 

RAD IOACT I VE GASEOUS EFFLUENT MONITOR I Nc INS1 RUMENTAT ION 

MINIMUM CHANNELS 

INSTRUMENT . OPERABLE APPLICABILITY ACTION 

4. Vent Header Systen 

a. Noble Gas Actlvlty Monitor 1 n 47 

51 b. n Iodlne Sampler 1 

c. Particulate Sanpltr 1 * 51 

d. Flaw Rate Monitor 

e. Sampler Flow Rate Honftor 

1 

1 

5. Contaimnt Purge System 

a. Noble Gas Activity Monitor - Providing ’ 

Alam and Autoaatic Terninatfon of Release 1 

b. Iodine Samplet 1 

c. Particulate Sampler 1 

d. Flow Rate Monitor 1 

e. Sampler Flow Rate Monitor 1 

46 

46 

48 

51 

51 

46 

46 
m 

a 

c) 

rn 

TABLE 3.3-13 (Continued) 

RADIOACTIVE GASEOUS EFFLUENT WN 1 TORING INSTRUMENT AT ION 

MINIMUM CHANNELS 

INSTRUMENT OPERABLE APPLICAEI LITY 

6. Auxiliary Building Ventilation 

system 

* a. Noble Gas Activity Monitor 1 

* b. Iodine Sampler 1 

* c. Particulate Sampler 1 

n d. Flow Rate Monitor 1 

rn 

)u e. Sampler Flow Rate Monitor 

0) 

U 

7. Fuel Storage Area Ventilation System 

1 n 

* a. Noble Gas Activity Monitor 1 

* b. Iodine Sampler 1 

* c. Particulate Sampler 1 

* d. Flow Rate Monitor 1 

e. Sampler Flow Rate Monitor 1 * 

ACTION 

47 

51 

51 

46 

46 

47 

51 

51 

46 

46 
IS 

ul 

;Q 

m 

n 

INSTRUFIENT 

TABk 3.3- 13 (Cant 4 nued) 

RADIOACTIVE GASEOUS EFF LUENT WNI TORI MG INSTRUMENT AT ION s 

MINIMUM CHANNELS 

OPERABLE APPLI CAE1 LITY ACTION 

0. Radwaste Area Ventilation System 

a. Noble Gas Activity Monitor 1 R 47 

b. Iodine Sampler 1 n 51 

c. Particulate Sampler 

d. Flow Rate Monitor 

e. Sampler Flow Rate Monitor 

Other Exhaust and Vent Systems such as: 

n 

N 

rg 

U 

9. 

Steam Generator Blowdown Vent System and 

Turbine Gland Seal Condenser Exhaust 

a. Noble Gas Activity Monitor 

b. Iodine Sampler 

c. Particulate Sampler 

d. Flow Rate Monitor 

e. Sampler Flow Rate Monftor 

1 

1 

1 

51 

46 

R 46 

47 

51 

51 

46 

46 
TABLE 3.3-13 (Continued) 

TABLE NOTATIONS 

*At all times. 

** During WASTE GAS HOLDUP SYSTEM operation. 

ACTXON STATEMENTS 

ACTION 45 - With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, the contents of the 

tank(s) may be released to the environment provided that prior 

to initiating the release: 

a. At least two independent samples of the tank's contents 

are analyzed, and 

b. At least two technically qualified members of the facility staff independently verify the release rate calculations 

and discharge valve lineup. 

Otherwise, suspend release of radioactive effluents via this 

pathway. 

With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

this pathway nay continue provided the flow rate is estimated at 

least once per 4 hours. 

With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

this pathway nay continue provided grab samples are taken at 

least once per 12 hours and these samples are analyzed for 

radioactivity wi thi n 24 hours. 

With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement , immediately suspend 

PURGING of radioactive effluents via this pathway. 

ACTION 46 - 

ACTION 47 - 

ACTION 48 - 

ACTXON 49 - NOT USE0 

ACTSON 50 - NOT USED 

- W SREC [303 
TABLE 3.3-13 (Continued) 

TABLE NOTATIONS (Continued) 

ACTION 51. - With the number of channels OPERABLE less than required by the 

Minimum Channels OPERABLE requirement, effluent releases via 

the affected pathway may continue provlded samples are continuously collected with auxiliary sampling equipment as required 

in Table 4.11-2. 

ACTION 52 - NOT USED 

W - SREC C313 
TABLE 4.3-9 

m 

;o 

m 

0 

INSTRUMENT 

RADIOACT WE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 

1. WASTE GAS HOLDUP SYSTEM 

ANALOG 

CHANNE 1 MODES FOR WilICH 

CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE 

CHECK - CHECK CALIBRATION TEST IS REQUIRED 

a. Noble Gas Activity Monitor - 

Providing Alarm and Autoinat4c 

Termination of Release P P R(3) 

b. Iodine Sampler W N. A. N. A. 

c. Particulate Sampler n 

W N. A. N. A. 

w 

ru d. Effluent System Flow Rate P N. A. R U Measuri ng Oev i ce 

e. Sampler Flow Rate Monitor 0. N. A. R 

Q( 1) 

N. A. 

N. A. 

Q 

Q * 

2A. NOT USED 
TABLE 4.3-9 (Continued) I* 

RADIOACTIVE GAS€OUS EFFLUENT m)NITORING INSTRUHENTATION SURVEILLANCE REQUIREMENTS m 

c) 

R 

INSTRUMENT 

28. NOT USED 

n 

w 

W 

U 

3. Condenser Evacuation System 

ANALOG 

CHANNEL MODES FOR WHICH 

CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE 

CHECK CHECK CALIBRATION TEST IS REQUIRED 

a. Noble Gas Activity Monitor 0. M R(3) 

b. Iodfne Sampler W N. A. N. A. 

c. Particulate Sampler W N. A. N. A. 

d. Flow Rate Monitor 0 N. A. R 

e. Sampler Flow Rate Monitor D N. A. R 

4. Vent Hcackr System 

a. Noble Gas Activity Honitor 0 M R(3) 

b. Iodlne Smler W N. A. N. A. 

Q(2) 

N. A. 

N. A. 

Q 

Q 

Q(2) 

N. A. 

* 

* 
TABLE 4.3-9 (Continued) 

1* 

cn ;L) 

m 

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 

INSTRUMENT 

4. Vent Header System (Continued) 

c. Particulate Sampler 

d. Flow Rate Monitor 

e. Sampler Flow Rate Monitor 

5. Containment Purge System 

u P a. Noble Gas Activity Monitor - n 

G, 

Providing Alarm and Automatic 

Termination of Release 

b. Iodine Sampler 

c. Particulate Sampler 

d. Flow Rate Monitor 

e. Sampler Flow Rate Monitor 

6. Auxiliary Building Ventilation 

system 

a. Noble Gas Activity Monitor 

CHANNEL 

CHECK 

w 

0 

0 

D 

w 

W 

D 

0 

0 

ANALOG 

CHANNEL 

SOURCE CHANNEL OPERATIONAL 

CHECK CALIBRATION TEST 

N. A. N. A. 

N. A. R 

N. A. R 

P R(3) 

N. A. N. A. 

N. A. N. A. 

N. A. R 

N. A. R 

N. A. 

Q 

Q 

Q(1) 

N. A. 

N. A. 

Q 

Q 

MODES FOR WHICH 

SURVEILLANCE 

IS REQUIRE0 

* 

* 

* 
la: 

tn 

m 

r) 

m 

TA6k 4.3-9 (Continued) 

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSfRUmNfATlON SURVEILLANCE REQUIREMENTS 

9 

INSTRUMENT 

6. Auxiliary Building Ventilation 

System (Cont i nwd ) 

b. Iodine SalApler 

c. Particulate Sampler 

d. Flow Rate Monitor 

n 

v1 

w e. Saapler Flow Rate Monitor U 

7. Fuel Storage Area Ventilation 

System 

a. Noble Gas Activity Monitor 

b. Iodine Sampler 

c. Particulate Sqler 

d. Flow Rate Monitor 

e. Sampler Flow Rate Monitor 

CHANNEL 

CHECK 

W 

w 

0 

0 

0 

w 

W 

0 

0 

SOURCE CHANNEL 

CHECK CALIBRATION 

N. A. N. A. 

N. A. N. A. 

N. A. R 

N. A. R 

M R(3) 

N. A. N. A. 

N. A. N. A. 

N. A. R 

N. A. R 

ANALOG 

CHANNEL 

OPERATlONAL 

TEST 

N. A. 

N. A. 

Q 

Q 

QW 

N. A. 

N. A. 

Q 

Q 

MODES FOR WHICH 

SURVE I LLANCL 

IS REQUIRE0 
IS 

m 

vi 

W 

0 

TABLE 4.3-9 (Cont i nued) 

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 

INSTRUMENT 

8. Radwaste Area Ventilation System 

a. Noble Gas Activity Monitor 

b. fodine Sampler 

c. Particulate Sampler 

n d. Flaw Rate Monitor 

U e. Sampler Flow Rate Monitor 

W 

ol 

9. Other Exhaust and Vent Systems 

such as: 

Steam Generator Blowdown Vent 

System, Turbine Gland Seal 

Condenser Exhaust 

a. Noble Gas Activity Monitor 

b. Iodine Sampler 

c. Partlculate Sampler 

d. Flow Rate Monitor 

e. Sampler Flow Rate Monitor 

CHANNEL 

 CHECK 

D 

W 

W 

0 

D 

0 

W 

W 

D 

D 

SOURCE CHANNEL 

CHECK CALIBRATION 

M R(3) 

N. A. N. A. 

N. A. N. A. 

N. A. R 

N. A. R 

M 

N. A. 

N. A. 

N. A. 

N. A. 

R(3) 

N. A. 

N. A. 

R 

R 

ANALOG 

CHANNEL MODES FOR WHICH 

OPERATIONAL SURVEILLANCE 

TEST IS REQUIRED 

Q(2) 

N. A. 

N. A. 

* Q 

* Q. 

Q(2) 

N. A. 

N. A. 

Q 

Q 
TABLE 4.3-9 (Continued) 

TABLE NOTATIONS 

* At all times. 

(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic 

isolation of this pathway and control room alarm annunciation occurs if 

any of the following conditions exists: 

a. Instrument indicates neasured levels above the Alarm/lrip Setpoint, or 

b. Circuit failure, or 

c. Instrument indicates a downscale failure, or 

d. Instrument controls not set in operate mode. 

/ (2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control 

room alarm annunciation occurs if any of the following conditions exists: 

a. Instrument indicates measured levels above the Alarm Setpoint, or 

b. Circuit faflure, or 

c. Instrument indicates a downscale failure, or 

d. Instrument controls not set in operate mode. 

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of 

the reference standards certified by the National Bureau of Standards (NBS) 

or using standards that have been obtained from suppliers that participate 

fn measurement assurance activities with NBS. These standards shall permit 

calibrating the system over its intended range of energy and measurement 

range. for subsequent CHANNEL CALIBRATION, sources that have been related 

to the initial calibration shall be used. 

- W SREC c373 
3/4.11 RADIOACTIVE EFFLUENTS 

3/4.11.1 LIQUID EFFLUENTS 

CONCENTRATION 

CONTROLS 

3.11.3.1 In accordance with [plant name] TS 6.8.4.g.2) and 3), the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS 

(see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR 

Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved 

or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x lo-' microCurie/ml total activity. 

APPLICABILITY: 

ACTION: 

At all times. 

a. With the concentration of radioactive material released in liquid 

effluents to UNRESTRICTED AREAS exceeding the above limits, 

immediately restore the concentration to within the above limits. 

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

SURVEILLANCE REQUIREMENTS 

4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according 

to the sampling and analysis program of Table 4.11-1. 

4.11.1.1.2 The results of the radioactivity analyses shall be used In accordance 

with the methodology and parmeters In the ODCM to assure that the concentrations 

at the point of release are maintained within the limits of Control 3.11.1.1. 

- W SREC [383 
TABLE 4.11-1 

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 

MINIMUM 

~~ 

LOWER LIMIT 

OF DETECTION 

LIQUID RELEASE SAMP L I NG ANALYSIS TYPE OF ACTSVITY ( LLD 

TYPE FREQUENCY FREQUENCY AN ALY S I S (pC i /ml ) 

1. Batch Waste P P 

Release Each Batch Each Batch Principal Gamma 5~10-~ 

Tanks (2) Emitters (3) 

1-131 1x10-6 

a. 

P M Oi ssol ved and 1x10-5 

One Batch/M Entrained Gases 

(Gamma Emitters) 

- ~ ~ 

H-3 1x10-5 (4) P 

Each Batch Composite 

Gross Alpha 1x10-7 

C. 

sl-89, sl-90 5x10- 

Fe-55 1x10-6 

(4) P 

Each Batch Composite. 

~ ~ ~ 

2. Continuous W Principal Gama SxlO-’ 

1-131 1x10-6 

(5) Continuous (6) composite (6) Emitters (3) Releases 

a. 

M M Dissolved and 1x10- 

Grab Sample Entrained Gases 

(Gamma Emf tters) 

H- 3 1x10-s 

Gross Alpha 1x10-7 

Sr-83, Sr90 5x10-8 

Fe-55 1x10-6 

b* - 

Continuous(6) Composite (6) 

Conti nuous(6) composite (6) 

C. 

E391 

- W SREC 
TABLE NOTATIONS 

("The LLD is defined, for purposes of these controls, as the smallest 

concentration of radioactive material in a sample that will yield a net 

count, above system background, that will be detected with 95% probability 

with only 5% probability of falsely concluding that a blank observation 

represents a "real" signal. 

For a particular measurement system, which may include radiochemical 

separation: 

4.66 Sb 

LLD = 

E V 2.22 x lo6 Ye exp (-Mt) 

Where: 

LLD = the 'la priori" lower limit of detection (microcurie per unit 

mass or volume), 

= the standard devlation of the background counting rate or of 

the counting rate of a blank sample as appropriate (counts per 

minute) , 

E = the counting efficiency (counts per disintegration), 

V = the sample size (units of mass or volume), 

2.22 x lo6 = the number of disintegrations per minute per microcurie, 

Y = the fractional radiochemical yield, when applicable, 

A = the radioactive decay constant for the particular radionuclide 

(sec-I), and 

At = the elapsed time between the midpoint of sample collection and 

the time of counting (sec). 

Typical values of E, V, Y, and At should be used in the calculation. 

It should be recognized that the LLD is defined as an a priori (before 

the fact) limit representing the capability of a MeasuFement system and 

not as an - a posteriori (after the fact) limit for a particular measurement. 

(2)A batch release is the discharge of liquid wastes of a discrete volume. 

Prior to sampling for analyses, each batch shall be isolated, and then 

thoroughly mixed by a method described in the ODCM to assure 

representative sampling. 

W SREC 

C403 
TABLE 4.11-1 (Continued) 

TABLE NOTATIONS (Continuedl 

3)The principal gamma emmiters for which the LLD control applies include 

the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Ho-99, 

Cs-134, Cs-137 and Ce-141. Ce-344 shall also be measured, but with an 

LlD of 5 x 10- . be considered. Other gamma peaks that are identifiable, together with 

those of the above nuclides, shall also be analyzed and reported in the 

Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 

in the format outlined in Regulatory Guide 1.21, Appendix E, Revision 1, 

June 1974. 

4 This list does not mean that only these nuclides are to 

(41A composite sample is one in which the quantity of liquid sampled is 

proportional to the quantity of liquid waste discharged and in which the 

method of sampling employed results fn a spechnen that is representative 

of the liquids released. 

(')A continuous release is the discharge of liquid wastes of a nondiscrete 

volume, e.g., from a volume of a system that has an input flow during the 

continuous release. 

(6)To be representative of the quantities and concentrations of radioactive 

materials in liquid effluents, samples shall be collected continuously in 

proportion to the rate of flow of the effluent stream. Prior to analyses, 

all samples taken for the composite shall be thoroughly mixed In order 

for the composite sample to be representative of the effluent release. 

- W SREC c413 
RADIOACTIVE EFFLUENTS 

DOSE 

CONTROLS 

- 

3. 

3.11.1.2 In accordance with [plant name] TS 6.8.4.g.4) and 6.6.4.6.5). the 

dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials 

in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see 

Figure 5.1-3) shall be limited: 

a. During any calendar quarter to less than or equal to 1.5 mrems to 

the whole body and to less than or equal to 5 mrems to any organ, 

and 

b. During any calendar year to less than or equal to 3 mrems to the 

whole body and to less than or equal to 10 mrems to any organ. 

APPLICABILITY: At all times. 

ACTION: 

a. With the calculated dose from the release of radioactive materials 

in liquid effluents exceeding any of the above limits, prepare 

and submit to the Commission within 30 days, pursuant to Control 

6.9.2, a Special Report that identifies the ceuse(s) for exceeding 

the limit(s) and defines the corrective actions that have been taken 

to reduce the releases and the proposed corrective actions to be 

taken to assure that subsequent releases will be in compliance with 

the above limits. This Special Report shall also include: (1) the 

resu?ts of radiological analyses of the drinking water source, and 

(2) the radiological impact on finished drinking water supplies with 

regard to the requirements of 40 CFR Part 141, Safe Drinking Water 

Act. * 

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

SURVEILLANCE REQUXREHENTS 

4.11.1.2 Cumulative dose contributions from liquid effluents for the current 

calendar quarter and the current calendar year shall be determined in accordance 

with the methodology and parameters in the ODCM at least once per 31 days. 

*The requirements of ACTION a.(l) and (2) are applicable only if drinking water 

In the case of tiver-sited plants this is 3 miles downstream only. 

supply is taken from the receiving water body within 3 miles of the plant 

discharge. 

- W SREC [423 
RADIOACTIVE EFFLUENTS 

LIQUID RADWASTE TREATMENT SYSTEM 

3.11.1.3 In accordance with [plant name] TS 6.8.4.g.6), the liquid Radwaste 

Treatment System shall be OPERABLE and appropriate portions of the system shall 

be used to reduce releases of radioactivity when the projected doses due to the 

liquid effluent, from each unit, to UNRESTRICTED AREAS (see figure 5.1-3) would 

exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period. 

APPLICABILITY: At all times. 

- ACTION: 

a. With radioactive liqufd waste being discharged without treatment and 

5n excess of the above limits and any portion of the Liquid Radwaste 

Treatment System not in operation, prtpare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that 

includes the following information: 

1. Explanation of why ljquid ridwaste was being discharged without 

treatment, identification of any inoperable equipment or 

subsystems, and the reason for the inoperability, 

2. 

3. 

Action($) taken to restore the inoperable equipment to OPERABLE 

status, and 

Sumnaty description of actionis) taken to prevtnt a recurrence. 

e 

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

SURVEILLANCE REQUIREMENTS 

4.11.1.3.1 Doses due to liquid rtleascs from each unit to UNRESTRICTED AREAS 

shall be projected at least once per 31 days in accordance with the methodology 

and parameters fn the ODCM when Liquid Radwaste Treatment Systems are not being 

fully utilized. 

4.11.1.3.2 The i n s t a l l e d Liquid Radwaste Treatment System shall be 

considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2. 

W -SREC [431 
RADIOACTIVE EFFLUENTS 

3/4.11.1.4 (NOT USED) 

- W SREC C443 
RADIOACTIVE EFFLUENTS 

3/4.11.2 GASEOUS EFFLUENTS 

DOSE RATE 

3.11.2.1 In accordance with [plant name) TS 6.8.4.g.3) and 7), the dose rate 

due to radioactfve materials released in gaseous effluents from the site to 

areas at and beyond the SITE BOUNDARY (see figure 5.1-3) shall be limited to 

the following: 

a. For noble gases: 

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

Less than or equal to 500 mrems/yr to the whole 

b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: 

Less than or equal to 1500 mrems/yr to any organ. 

APPLICABILITY: 

- ACTION: 

At all times. 

a. With the dose rate(s) exceeding the above limits, immediately restore 

the release rate to within the above limit(s). 

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

SURVEILLANCE REQUIREMENTS 

4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be 

determined to be within the above limits in accordance with the methodology 

and parmters In the ODCM. 

4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all 

rrdfonuclides in particulate form with half-lives greater than 8 days in 

gaseous effluents shall be determined to be within the above limits in 

accordance with the methodology and parameters In the ODCM by obtaining 

representative samples and performing analyses in accordance with the sampling 

and analysis program specified in Table 4.11-2. 

- W SREC 

c453 
TABLE 4.11-2 

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 

IS 

a MINIMUM LOWER LIMIT OF (1) Cn 

m 

c) 5 AMP1 I NG ANALY S I S TYPE OF DETECTION (LLD) 

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCi /ml 1 

1. Waste Gas Storage P P 

2. Containment Purge P P 

(2) 1x10-4 

(2) 1x10-4 

lank Each lank Each Tank Principal Gama Emf tters 

or Vent Each PURGE(3) Each PURGE(3) Principal Gamma Emitters 

Grab Sample 

Grab Sample 

M H-3 (oxide) 1x10-6 

3. a. Plant Vent H(3) ,(4) M(3) Principal Gamma €mi tters (2) 1x10-4 

Grab Sample 

H-3 (oxide) 1x10-6 

b. Fuel Storage M(') Principal Gama Emitters' 2) 1x10-4 n 

4% 

m 

U 

Area Grab Sample M 

Ventilation H-3 (oxide) lxlo-6 

c. Auxiliary H Principal Gamma Emitters(') 1x10-4 

81dg, Rattwaste Grab Sample M. 

Area, SGB Vent, 

Others \. 

4. All Release Types Continuous (6) w(7) 1-131 1x10- ' * 

as listed in l., Charcoal 

2., and 3. above Sample 

w(7) Principal Gamma Emitters") 1x10- Continuous( 6) 

Particulate 

Sam1 e 

Composite Particulate Sample 

Composite ParContinuous(6) n Gross Alpha lxlo-" 

Q Sr-89, 9-90 1x10- * * Continuous( 6) 

#=, ticulate Sample 

Continuous'"' Noble Gas Noble Gases 1x10-" 

Beta or Gama 
TABLE 4.11-2 (Continued) 

TABLE NOTATIONS 

('"The LLD s def ned, for purposes of these controls, as the smallest 

concentration of radioactive material in a sample that will yield a net 

count, above system background, that will be detected with 95% probability 

with only 5% probability of falsely concluding that a blank observation 

represents a "real" signal. 

For a particular measurement system, which may include radiochemical 

separation: 

4.66 sb 

LLD = 

E V 2.22 x lo6 Y exp (-Mt) 

Where: 

LLD = the ''a priori" lower limit of detection (mlcroCurie per unit 

mass or volume), 

Sb = the standard deviation of the background counting rate or of 

the countfng rate of a blank sample as appropriate (counts per 

minute) , 

E = the counting efficiency (counts per disintegration), 

V = the sample size (units of mass or volume), 

2.22 x lo6 = the number of disintegrations per minute per microcurie, 

Y = the fractional radiochemical yield, when applicable, 

A = the radioactive decay constant for the particular radionuclide 

(see1), and 

At = the elapsed time between the midpoint of sample collection and 

the time of countfng (sec). 

Typical values of E, V, Y, and At should be used in the calculation. 

It should be recognized that the LLD is defined as an g priori (before 

the fact) limit representing the capability of a measurement system and 

not as an 5 posteriori (after the fact) limit for a particular measurement. 

y SREC 1471 
TABLE 4.11-2 (Continued) 

TABLE NOTATIONS (Continued) \ 

("The principal gamma emitters for which the LLD control applies include 

the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-l33m, Xe-135, and 

Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, CO-60, tn-65, Mo-99, 

1-131, Cs-134, Cs-137, Ce-141 and Ce-144 in Iodine and particulate 

releases. This list does not mean that only these nuclides are to be 

considered. 

of the above nuclides, shall also be analyzed and reported in the 

Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 

in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, 

June 1974. 

Other gamma peaks that are identifiable, together with those 

(3)Sampling and analysis shall also be performed following shutdown, startup, 

or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 

1-hour period. 

(4)Tritium grab samples shall be taken at least once per 24 hours when the 

refuel i ng canal i s f 1 ooded. 

("Tritium grab samples shall be taken at least once per 7 days from the 

ventilation exhaust from the spent fuel pool area, whenever spent fuel is 

in the spent fuel pool. 

(6)The ratio of the sample flow rate to the sampled stream flow rate shall be 

known for the time period covered by each dose or dose rate calculation 

(''Samples shall be changed at least once per 7 days and analyses shall be 

completed within 48 hours after changing, or after removal from sampler. 

Sampling shall also be performed at least once per 24 hours for at least 

7 days following each shutdown, startup, or THERMAL POWER change exceeding 

15% of RATED THERMAL QOUER within a l-hour period and analyses shall be 

completed within 48 hours of changing. 

are analyzed, the corresponding LLDs may be increased by a factor of 10. 

This requirement does not apply if: 

EQUIVALENT 1-131 concentration in the reactor coolant has not increased 

more than a factor of 3; and (2) the noble gas monitor shows that 

effluent activity has not increased more than a factor of 3. 

. made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3. 

When samples collected for 24 hours 

(1) analysis chows that the DOSE 

- W SREC [483 
RADIOACTIVE EFFLUENTS 

DOS€ - NOBLE GASES 

CONTROLS 

3.11.2.2 In accordance with [plant name] TS 6.8.4.9.5) and 8). the air dose 

due to noble gases released in gaseous effluents, from each unit, to areas at 

and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the 

following: 

a. During any calendar quarter: 

gamma radiation and less than or equal to 10 mrads for beta radiation, 

and 

Less than or equal to 5 mrads for 

b. During any calendar year: radiation and less than or equal to 20 nrads for beta radiation. Less than or equal to 10 nrads for gama 

APPLICABILITY: At all times. 

- ACTION 

a. With the calculated air dose from radioactive noble gases in gaseous 

effluents exceeding any of the above limits, prepare and submit to 

the Commission within 30 days, pursuant to Control 6.9.2, a Special 

Report that identifies the cause(s> for exceeding the limit(s) and 

defines the corrective actions that have been taken to reduce the 

releases and the proposed corrective actions to be taken to assure 

that subsequent releases will be in compliance with the above limits. 

The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

Y 

b. 

SURVEILLANCE REQUIREMENTS 

4.11.2.2 Cumulative dose contributions for the current calendar quarter and 

current calendar year for noble gases shall be determined in accordance with 

the methodology and parameters in the ODCM at least once per 31 days. 

W - SREC 1493 
RADIOACTIVE EFFLUENTS 

DOSE * IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN 

PARTICULATE FORM 

CONTROLS 

3.11.2.3 In accordance with [plant name] TS 6.8.4.9.5) and 9>, the dose to a 

MEMBER OF THE PUBLIC from Iodine-133, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 0 days In gaseous 

effluents released, from each unit, to areas at and beyond the SITE BOUNDARY 

(see figure 5.1-3) shall be limited to the following: 

a. During any calendar quarter: *Less than or equal to 7.5 mrems to any 

organ and, 

b. During any calendar year: Less than or equal to 15 mrems to any 

organ. 

APPLICABILITY: At all times. 

ACTION: 

a. With the calculated dose from the release of Iodine-131, Iodine-133, 

tritium, and radionuclides in particulate form with half-lives 

greater than 8 days, in gaseous effluents exceeding any of the above 

limits, prepare and submit to the Commission within 30 days, pursuant 

to Control 6.9.2, a Special Report that Identifies the cause(s) for 

exceeding the limit(s) and defines the corrective actions that have 

been taken to reduce the releases and the proposed corrective actions 

to be taken to assure that subsequent releases will be in compliance 

with the above limits. 

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

SURVEILLANCE REQUIREMENTS 

4.11.2.3 Cumulative dose contributions for the current calendar quarter and 

current calendar year for Iodine-131, Iodine-133, tritium and radionuclides 

in particulate form with half-lives greater than 8 days shall be determined 

in accordance with the methodology and parameters in the ODCM at least once 

per 31 days. 

E SREC [503 
RADIOACTIVE EFFLUENTS 

GASEOUS RAOWASTE TREATMENT SYSTEM 

3.11.2.4 In accordance with [plant name] TS 6.8.4.g.6), the VENTILATION 

EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and 

appropriate portions of these systems shall be used to reduce releases of 

radioactivity when the projected doses in 31 days due to gaseous effluent 

releases, from each unit, to areas at and beyond the SITE BOUNDARY (see 

Figure 5.1-3) would exceed: 

a. 0.2 mrad to air from gamma radiation, or 

b. 0.4 mrad to air from beta radiation, or 

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. 

APPLICABILITY: At all times. 

- ACTION: 

a. With radioactive gaseous waste being discharged without treatment 

and in excess of the above limits, prepare and submit to the 

Commission within 30 days, pursuant to Control 6.9.2, a Special 

Report that includes the following information: 

1. Identification of any inoperable equipment or subsystems, and 

the reason for the inoperabillty, 

2. Action(r) taken to restore the inoperable equipment to OPERABLE 

status, and 

3. 

The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

Sunmary description of action($) taken to prevent a recurrence. 

b. 

SURVEl LLANCE REQUIREMENTS 

4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and 

beyond the SITE BOUNDARY shall be projected at least once per 31 days in 

accordance with the methodology acld parameters In the ODCM when Gaseous 

Radwaste Treatment Systems are not being fully utilized. 

4.11.2.4.2 The i n s t a l l e d VENTlUITIUN €XHAUST TREATMENT SYSTEM and WASTE 

GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Controls 3.11.2.1 

and 3.11.2.2 or 3.11.2.3. 

W - SREC 
RAD1 OACT I VE EFFLUENTS 

3/4.11.2.5 (NOT USED1 

- W SREC C523 
RADIOACTIVE EFFLUENTS 

U4.11.2.6 (NOT USED) 

- W SREC I533 
RADIOACTIVE EFFLUENTS 

3/4.11.3 (NOT USED) 

- U SREC 
RADIOACTIVE EFFLUENTS 

3/4.11.4 TOTAL DOSE 

3.11.4 In accordance with [plant name] TS 6.8.4.g.11), the annual (calendar 

year) dose or dose commitment to any MEMBER OF THE PUBLIC due to =leases of 

radioactivity and to radiation from uranium fuel cycle sources shall be limited 

to less than or equal to 25 mrems to the whole body or any organ, except the 

thyroid, which shall be limited to less than or equal to 75 mrems. 

APPLICABILlTY: At all timer. 

ACTION: 

a. 

- 

With the calculated doses from the release of radioactSve materials 

in liquid or gaseous effluents exceeding twice the limits of Control 

3.11.1.2~., 3.11.1.2b.. 3.11.2.2a., 3.11.2.2b.. 3.11.2.3a., or 

3.11.2.3b.. calculations shall be made including direct radiation 

contributions from the units (including outside storage tanks etc.) to 

determine whether the above limits of Control 3.11.4 have been 

exceeded. 

within 30 days, pursuant to Control 6.9.2, a Special Report that 

defines the corrective action to be taken to reduce subsequent 

releases to prevent recurrence of exceeding the above limits and 

includes the schedule for achieving conformance with the above limits. 

This Special Report, as defined in 10 CFR 20.405(c), shall include an 

analysis that estimates the radiation exposure (dose) to a MEMBER OF 

THE PUBLIC from uranium fuel cycle sources, including all effluent 

pathways and direct radiation, for the calendar year that includes 

the release(r) covered by this report. It shall also describe levels 

of radiation and concentrations of radioactive material involved, and 

the cause of the exposure levels or concentrations. If the estimated 

dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, 

the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report 

is considered a timely request, and a variance is granted until staff 

action on the request 1s complete. 

The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

If such is the case, prepare and submit to the Commission 

b. 

SURVEILLANCE REQUIREMENTS ~ 

4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents 

shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 

4.11.2.3, and in accordance with the methodology and parmeters In the ODCM. 

4.11.4.2 Cumulative dose contributions from direct radiation from the units 

(including outside storage tanks etc.) shall be determined in accordance with 

the methodology and parameters in the ODCM. 

only under conditions set forth in ACTION a. of Control 3.11.4. 

This requirement is applicable 

SREC E551 
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 

3/4.12.1 MONITORING PROGRAM 

CONTROLS 

3.12.1 

Environmental Monitoring Program shall be conducted as specified in 

Table 3.12-1. 

In accordance with [plant name] TS 6.8.4.h.1), the Radiological 

APPLICABILITY: At all times. 

ACTION: 

a. With the Radiological Environmental Monitoring Program not being 

conducted as specified in Table 3.12-3, prepare and submit to 

the Commission, in the Annual Radiological Environmental Operating 

Report required by Control 6.9.1.3, a description of the reasons 

for not conducting the program as required and the plans for preventing 

a recurrence. 

b. With the level of radioactivity as the result of plant effluents in 

an environmental sampling medium at a specified location exceeding 

the reporting levels of Table 3.12-2 when averaged over any calendar 

quarter, prepare and submit to the Commission within 30 days, pursuant 

to Control 6.9.2, a Special Report that identifies the cause(s) 

for exceeding the ?irnit(s) and defines the corrective actions to be 

taken to reduce radioactive effluents so that the potential annual 

dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits 

of Controls 3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than 

one of the radionuclides in Table 3.12-2 are detected in the sampling 

medium, this report shall be submitted if: 

-' 

concentration (1) + concentration (2) + ..., l.o 

reporting level (1) reporting level (25 - 

When radionuclides other than those in Table 3.12-2 are detected and 

are the result of plant effluents, this report shall be submitted if 

the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclfdes is equal to or greater than the calendar year limits of 

Control 3.11.1.2, 3.11.2.2, or 3.11.2.3. 

required if the measured level of radioactivity was not the result 

of plant effluents; however, in such an event, the condition shall 

be reported and descri bed in the Annual Radi ol ogi cal Environmental 

Operating Report required by Control 6.9.1.3. 

This report is not 

*The methodology and parameters used to estimate the potential annual dose to 

a MEMBER OF THE PUBLIC shall be indicated in this report. 

- W SREC C563 
RADIOLOGICAL ENVIRONMENTAL MONITORING 

CONTROLS 

ACTION (Continued) 

c. With milk or fresh leafy vegetation samples unavailable from one or 

more of the sample locations required by fable 3.12-1, identify 

specific locations for obtaining replacement samples and add them 

within 30 days to the Radiological Environmental Monitoring Program 

given in the ODCM. 

unavailable nay then be deleted from the monitoring program. 

to Control 6.14, submit in the next Semiannual Radioactive Effluent 

Release Report documentation for a change in the ODCM including a 

revised figure(s) and table for the ODCM reflecting the new 

location(s) with supporting information identifying the cause of 

the unavailability of samples and justifying the selection of the 

new location(s) for obtaining samples. 

The specific locations from which samples were 

Pursuant 

d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

SURVEILLANCE REQUIREMENTS 

4.12.1 The radiological environmental monitoring samples shall be collected 

pursuant to Table 3.12-1 from the specific locations given in the table and 

figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of 

Table 3.12-1 and the detection capabjlities required by Table 4.12-1. 

- W SREC c573 

- 
EXPOSURE PATHWAY 

AND/OR SAMPLE 

1. Direct Radiation(*) 

NUMBER 

TABLE 3.12-1 

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM* 

OF 

RE PRE SENTAT IVE 

SAMPLES AND SAMPLING AND 

SAMPLE LOCAT IONS( l) COLLECTION FREQUENCY 

Forty routine monitoring stations Quarterly. 

(DR1-DRIO) either with two or more 

dosimeters or with one instrument 

for measuring and recording dose 

rate continuously, placed as 

follows: 

An inner ring of stations, one in 

each meteorological sector in the 

general area of the SITE BOUNDARY 

(DR1-DR16) ; 

An outer ring of stations, one in 

each meteorological sector in 

the 6- to 8-km range from the 

si te (DR17-DR32) ; and 

The balance of the stations 

(OR33-DR40) to be placed in 

special interest areas such 

as population centers, nearby 

residences, schools, and in one 

or two areas to serve as control 

stations. 

TYPE AND FREQUENCY 

OF ANALYSIS 

Gamma dose quarterly. 

*The number, media, frequency, and location of samples may vary from site to site. This table presents an 

acceptable minimum program for a site at which each entry is applicable. 

examined to determine if pathways not covered by this table may significantly contribute to an individual's 

dose and should be included in the sample program. 

one way of defining sample locations in this control that can be used to identify the specific locations 

in the map(s) and table in the ODCM. 

Local site characteristics must be 

The code letters in parentheses, e.g., DR1, Al, provjde 
TABLE 3.12-1 (Cant 1 nuedl 

ln 

XI 

I7 

m 

m 

ul 

W 

U 

RADIOLOGICAL ENVIRONMENTAL MOM ITORI NG PROGRAM 

NUMBER OF 

REPRESENTATIVE 

EXPOSURE PATHWAY SAMPLES AND 

2. Airborne 

AND/OR SAHPLE SAMPLE LOCATION^^) 

Radioiodine and Samples from five locations 

Particulates ( A1- As) : 

Three samples (Al-A3) from 

close to the three SITE 

BOUNDARY locations, in 

different sectors, of the 

highest calculated annual 

average ground-level WQ; 

One sample (A4) from the 

vicinity of a community 

having the highest calcu1 ated annual average groundlevel O/Q;' and 

One sample (AS) from a control 

location, as for example 15 to 

30 km distant and in the least 

prevalent wind direction. 

3. Waterborne 

SAMPLING AND 

COLLECTION FREQUENCY 

Continuous sampler operation with sample collection weekly, or more 

frequently if required by 

dust loading. 

a. Surface (5) One sample upstream (Ual). Composite sample over 

One sample downstream (Wa2). 1-nonth period. (6) 

b. Ground Samples from one or two sources Quarterly. 

(Wbl, Wb2), only if l i k e l y t o be 

affected('). 

TYPt AND FREQUENCY 

OF ANALYSIS 

Radioiodine Cannister: 

1-131 analysis weekly. 

Particulate Sampler: 

Gross beta radioactivity 

analysis following 

(4) f i 1 ter change;(3) and 

gamma isotopic analysis 

of composite (by 

1 ocat i on) quarterly. 

Gama isotopic analysis (4) 

monthly. Composite for 

tritium analysis quarterly. 

Gama isotopic(4) and 

tritium analysis quarterlv- 
IL 

m 

cn 

W 

c, 

TABLE 3.12-1 (Continued) 

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 

NUMBER OF 

REPRESENTATIVE 

EXPOSURE PATHWAY SAMPLES AND 

3. Waterborne (Continued) 

AND/OR SAMPLE SAMPLE LOCATIONS' 

c. Drinking One sample of each of one to 

three (Wcl - Wc3) of the nearest 

water supplies that could be 

affected by Its discharge. 

One sample from a control 

location (Wc4). 

n 

m 

0 

U 

SAMPLING AND TYPE AN0 FREQUENCY 

COLLECTION FREQUENCY OF ANALYSIS 

Composite sample over 1-131 analysis on each . composite when the dose 

calculated for the consumption of the water 

is greater than 1 mrem 

2-week period(6) when 

1-131 analysis is performed; monthly CMposi te othewi se. I P\ 

per yeartgJ. Compos i te 

for gross beta and gamma 

monthly. Composite for 

tritium analysis quarterly. 

isotopic analyses (4) 

d. Sediment One sample from downstream area Semiannually. 

with existing or potential 

recreational value (Wdl). 

f rorn 

Shore1 i ne 

4. Ingestion 

a. Milk Samples from milking animals 

in three locations (la1 - Ia3) 

within 5 km distance having the 

highest dose potential. If 

there are none, then one 

sample from milking animals 

in each of three areas 

(Ial - Ia3) between 5 to 

8 km distant where doses 

are calculated to bf8cjre;j;fr 

than 1 nrem per yr. 

sample from milking animals 

at a control location (Ia4), 

15 to 30 km distant and in the 

least prevalent wind direction. 

Semimonthly when 

animals are on pasture; 

monthly at other times. 

Gama isotopic analysis (4 1 

semiannual ly. 

Gamma isotopic(4) and 

1-131 analysis sernimonthly when animals 

are on pasture; monthly 

at other tines. 
n 

b, 

-. 

U 

TABLE 3.12-1 (Cont i nued) 

RADIOlOCICAl ENVIRONMENTAL MONITORING PROGRAM 

IS 

cn r) 

m 

c) 

NUMBER OF 

REPRESENTATIVE 

EXPOSURE PATHWAY SAMPLES AND SAMPLING AND 

4. Ingestion (Continued) 

AND/OR SAMPLE SAMPLE LOCATIONS(~) COLLECTION FREQUENCY 

b. Fish and One sample of each comerdally Smle in season, or 

Inverte- and recreationally important semiannually if they 

brates species in vicinity of plant are not seasonal. 

discharge area. (Ibl - Ib-). 

One sample of same species in 

areas not fnfluenced by plant 

discharp (IblO - Ib-). 

c. Food One sqlc of each prlncipal 

class of food products from 

any ana that is irrigated 

by water In which liquid . plant wastes have been 

discharged (IC1 - IC-). 

Samples of three different 

kinds of broad leaf vegetation grown nearest each of 

two different offsite locatlons of highest predicted 

annual average ground level 

O/Q if milk sampling is not 

perforated (IclO - Icl3). 

Products 

One sample of each of the 

similar broad leaf vegetation grown 15 to 30 km distant in the least prevalent 

wind direction if milk sanpling is not performed (Ic20 - 

Ic23). 

TYPE AND FREQUENCY 

OF ANALYSIS 

Gamma isotopic analysis (4) 

on edible portions. 

Gama (4) isotopic analyses 

on edible portion. 

(9) At time of harvest . 

Monthly during 

growing season. 

Monthly during 

growing season. 

Gama isotopic(4) and 1-131 

analysi s. 

Gamma isotopic(4) and 1-131 

ana 1 y s i 5. 
TABLE 3,12-1 (Continued) 

TABLE NOTATIONS 

(1) Specific parameters of distance and direction sector from the centerline 

of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and 

figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological 

Effluent Technical Specifications for Nuclear Power Plants," October 1978, 

and to Radiological Assessment Branch Technical Position, Revision 1, 

November 1979. Deviations are permitted from the required sampling 

schedule if specimens are unobtainable due to circumstances such as 

hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. 

equipment malfunction, effort shall be made to complete corrective action 

prior to the end of the next sampling period. 

sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. 

that, at times, it may not be possible or practicable to continue to 

obtain samples of the media of choice at the most desired location or 

time. In these instances suitable alternative media and locations may be 

chosen for the particular pathway in question and appropriate substitutions 

made within 30 days in the Radiological Environmental Monitoring Program 

given in the ODCM. 

Semiannual Radioactive Effluent Release Report documentation for a change 

in the OOCM including a revised figure(s) and table for the ODCH reflecting the new location(s) with supporting information identifying the cause 

of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples. 

If specimens are unobtainable due to sampling 

All deviations from the 

It is recognized 

Pursuant to Control 6.14, submit in the next 

Y 

(2) One or more instruments, such us 8 pressurized Con chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. 

thermoluminescent dosimeter (TLD) is considered to be one phosphor; two 

or more phosphors in a packet are considered as two or more dosimeters. 

Film badges shall not be used as dosimeters for measuring direct radiation. 

(The 40 stations is not an absolute number. The number of direct r8diation 

monitoring stations may be reduced according to geographical limitations; 

e.g., at an ocean site, some sectors will be over water so that the number 

of dosimeters may be reduced accordingly. 

readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information 

with minimal fading. ) 

For the purposes of thfs table, a 

The frequency of analysis or 

(3) Airborne particulate sample filters shall be analyzed for gross beta 

radioactivity 24 hours or more after sampling to allow for radon and 

thoron daughter decay. 

is greater than 10 times the yearly mean of control samples, gama 

isotopic analysis shall be performed on the individual samples. 

If gross beta activity in air particulate samples 

W - SREC C623 
TABLE 3.12-1 (Continued) 

TABLE NOTATIONS (Continuedl 

(4) Gamma isotopic analysis means the identification and quantification of 

gamma-emitting radionuclides that may be attributable to the effluents 

from the facility. 

(5) The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. 

area beyond but near the mixing zone. 

must be taken far enough upstream to be beyond the plant influence. 

water shall be sampled only when the receiving water is u t i l i z e d f o r 

recreational activities. 

The "downstream" sample shall be taken in an 

Salt 

"Upstream" samples in an estuary 

:6) A composite sample is one In which the quantity (aliquot) of 1iQuid sampled 

is proportional to the quantity of flowing liquid and in which the method 

of sampling employed results in a specimen that is representative of the 

liquid flow. 

at time intervals that are very short (e.g., hourly) relative to the 

compositing period (e.g., monthly) In order to assure obtaining a 

representative ramp1 e. 

In this program composite sample aliquots shall be collected 

(7) Groundwater samples shall be taken when this source is tapped for drinking 

or irrigation purposes in areas where the hydraulic gradient or recharge 

properties are suitable for contamination. 

(8) The dose shall be calculated for the maximum organ and age group, using 

the methodology and parameters in the ODCM. 

(9) If harvest occurs more than once a year, sampling shall be performed 

during each discrete harvest. 

shall be monthly. 

tuberous and root food products. 

If harvest occurs continuously, sampling 

Attention shall be paid to including samples of 

W - SREC 1631 
TABLE 3.12-2 

m 

W 

0 

m 

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 

REPORTIMG LEVELS 

~ ~~- 

WATER AIRBORNE PART1 CULATE FISH MILK FOOD PRODUCTS 

ANALY S I S (PCi 11 1 OR GASES (pCi/m3) (pCi/kg, wet) (PCW 1 (PC 1 / kg , wet 1 

H- 3 

Mn- 54 

Fe-59 

Co-58 

CO-60 

01 Zn-65 n 

P 

U 

Z r-Nb- 95 

1-131 

Cs-134 

Cs-137 

Ba- La- 140 

20, ooo* 

1,000 

400 

1.000 

300 

300 

400 

2*" 0 

30 10 

50 20 

200 

9 

30,000 

10,000 

30,000 

10,000 

20,000 

1,000 

2,000 

3 100 

60 1,000 

70 2,000 

300 

*For drinking water samples. 

**If no drinking water pathway exists, a value of 20 pCi/l may be used. 

This is 40 CFR Part 141 value. If no drinking water pathway exists, a value 

of 30,000 pCVl may be used. 
TABLE 4.12-1 

DETECTION CAPABILITIES FOR ENVt RONHEHlAL SAMPLE ANALYSIS (1) (2) 

LOWER LIMIT OF DETECTION (LLO)(~) 

WATER AIRBORNE PART1 CULATE FISH MILK FOOO PROOUCTS SEDIMENT 

ANALYSIS (pCi/l] OR GASES (pCi/n3) (pCi/kg, wet) (pCi/l) (pCVkg, wet) (pCi/kg, dry) 

Gross Beta 

H-3 

Mn- 54 

Fe-59 

r) CO-W,6O 

- Zn-65 

ul 

v, 

zr-Nb-95 

1-131 

cs-134 

Cs-137 

Ea-La-140 

4 

2WOR 

15 

30 

15 

30 

1s 

1** 

15 

10 

15 

0.01 

130 

260 

130 

260 

'0.07 

0.05 

0.06 

1 

130 15 

150 10 

15 

60 

60 150 

80 180 

*If no drinking water pathway exists, a value of 3000 pCl/l may be used. 

If no drinking water pathway extists, a value of 15 pCi/l may be used. 

** 
TABLE 4.12-1 (Continued) 

TABLE NOTATIONS 

(1)This list does not mean that only these nuclides are to be considered. 

Other peaks that are identifiable, together with those of the above 

nuclides, shall also be analyzed and reported in the Annual Radiological 

Environmental Operating Report pursuant to Control 6.9.1.3. 

(2)Required detection capabilities for thermoluminescent dosimeters used 

for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. 

(3)The LLD is defined, for purposes of these controls, as the smallest 

concentration of radioactive material in a sample that will yield a net 

count, above system background, that will be detected with 95% probability 

with only 5% probability of falsely concluding that a blank observation 

represents a "real" signal. 

for a particular measurement system, which may include radiochemical 

separation: 

4.66 sb 

E V 2.22 Y exp(-Ut) 

LLD = 

Where: 

LLD = the "a priori" lower limit of detection (picocuries per unit 

mass or volume), 

= the standard deviation of the background counting rate or of the 

= the countf ng efficiency (counts per disintegratf on) , 

Sb 

E 

counting rate of a blank sample as appropriate (counts per minute), 

V = the sample sire (units of mass or volume), 

2.22 = the number of disintegrations per minute per picoCurie, 

V = the fractional radiochemical yield, when applicable, 

A = the radioactive decay constant for the particular radionuclide 

(sec-I), and 

At = the elapsed time between environmental collection, or end of 

the sample collection period, and time of counting (sec). 

Typical values of E, V, Y, and At should be used in the calculation. 

- W SREC [663 
TABLE 4.12-1 (Continued) 

TABLE NOTATIONS (Continued) 

It should be recognized that the LLD is defined as an priori (before the 

fact) limit representing the capability of a measurement system and not as 

an a osteriori (after the fact) limit for a particular measurement. 

achieved under routine conditions. Occasionally background fluctuations, 

unavoidable small sample sizes, the presence of interfering nuclides, or 

other uncontrollable circumstances may render these LLOs unachievable. 

In such cases, the contributing factors shall be identified and described 

in the Annual Radiological fnvf ronmental Operating Report pursuant to 

Control 6.9.1.3. 

AnaTyses + sha 1 be performed in such a manner that the stated LLDs will be 

- W SREC 
RADIOLOGICAL ENVIRONMENTAL MONITORING 

3/4.12.2 LAND USE CENSUS 

CONTROLS \ 

3.12.2 In accordance with [plant name] TS 6.8.4.h.2). a Land Use Census shall 

be conducted and shall identify within a distance of 8 km (5 miles) the 

location in each of the 16 meteorological sectors of the nearest milk animal, 

the nearest residence, and the nearest garden* of greater than 50 m2 (500 ft2) 

producing broad leaf vegetation. lFor elevated releases as defined in Regulatory Guide 1.111. Revjsion 1, July 1977, the Land Use Census shall also 

identify within a distance of 5 km (3 miles) the locations in each of the 

16 meteorological sectors of all milk animals and all gardens of greater than 

50 u? producing broad leaf vegetation. 3 

APPLICABILITY: At a11 times. 

ACTION: 

a. 

- 

With a Land Use Census identifying a location(s) that yields a 

calculated dose or dose commitment greater than the values currently 

being calculated in Control 4.31.2.3, pursuant to Control 6.9.1.4, 

identify the new location(s) in the next Semiannual Radioactive 

Effluent Release Report. 

b. With a land Use Census identifying a location(s) that yields a 

calculated dose or dose commitment (via the same exposure pathway) 

20% greater than at a location from which samples are currently 

being obtained in accordance with Control 3.12.1, add the new 

\ocation(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose 

or dose commitment(s), vfa the same exposure pathway, may be deleted 

from this monitoring program after [October 311 of the year in which 

this Land Use Census was conducted. Pursuant to Control 6.14, 

cubmft in the next Semiannual Radioactive Effluent Release Report 

documentation for a change in the ODCM including a revised figure(s) 

and table(s) for the ODCM reflecting the new location(s) with information supporting the change In sampling locations. 

- 

c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

"Broad leaf vegetation sampling of at least three different kinds of vegetation 

nay be performed at the SITE BOUNDARY in each of two different direction 

sectors with the highest predicted D/Qs In lieu of the garden census. 

Controls for broad leaf vegetation sampling in Table 3.12-1, Part 4.c.. shall 

be followed, including analysis of control samples. 

- W SREC C681 
RADIOLOGICAL ENVIRONMENTAL MONITORXNG 

SURVEILLANCE REQUIREMENTS 

4.12.2 The Land Use Census shall be conducted during the growing season at 

least once per 12 months using that information that will provide the best 

results, such as by a door-to-door survey, aerial survey, or by consulting 

local agriculture authorities. The results of the Land Use Census shall be 

included in the Annual Radiological Environmental Operating Report pursuant to 

Control 6.9.1.3. 

E SREC C693 
RADIOLOGICAL ENVIRONMENTAL MONITORING 

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 

CONTROL 5 

3.12.3 

performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to 

samples required by Table 3.12-1. 

In accordance with [plant name] TS 6.8.4.h.3), analyses shall be 

APPLlCABltIlY: At all times. 

ACTION: 

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission 

in the Annual Radiological Environmental Operating Report pursuant 

to Control 6.9.1.3. 

b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable. 

SURVEILLANCE REQUIREMENTS 

4.12.3 The Interlaboratory Cornparison Program shall be described in the ODCM. 

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental 

Operating Report pursuant to Control 6.9.1.3. 

W - SREC C701 
BASES FOR 

SECflONS 3.0 AND 4.0 

CONTROLS 

AND 

SURVEILLANCE REQUIREMENTS 

NOTE 

The BASES contained in succeeding pa es summarize 

and 4.0, but are not part of these Controls. 

- 

the reasms for the Controls in Sect P one 3.0 

C711 
INSTRUMENTATION 

BASES 

314.3.3. io RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 

The radioactive liquid effluent instrumentation is provided to monitor 

and control, as applicable, the releases of radioactive materials in liquid 

effluents during actual or potential releases of liquid effluents. 

Alarmnrip Setpoints for these instruments shall be calculated and adjusted in 

accordance with the methodology and parameters in the ODCM to ensure that the 

alarmhip will occur prior to exceeding the limits of 10 CFR Part 20. The 

OPERABILITY and use of this instrumentation is consistent with the requirements 

of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 

The 

3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 

The radioactive gaseous effluent instrumentation is provided to monitor and 

control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip 

Setpoints for these instruments shall be calculated and adjusted in accordance 

with the methodology and parameters in the ODCM to ensure that the alarmhip 

will occur prior to exceeding the limits of 10 CFR Part 20. 

and use of this instrumentation 5s consistent with the requirements of General 

Design Criteria 60, 63, snd 64 of Appendix A to 10 CFR Part 50. 

The OPERABILITY 

- W SREC 1721 
3/4.11 RADIOACTIVE EFFLUENTS 

3/4.11.1 LXQUID EFFLUENTS 

3/4.11.1.1 CONCENTRATION 

This control is provided to ensure that the concentration of radioactive 

materials released in liquid waste effluents to UNRESTRICTED AREAS will be less 

than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 

11, Column 2. This limitation provides additional assurance that the levels of 

radioactive materials in bodies of water in UNRESTRICTED AREAS will result in 

exposures within: (I) the Section 1I.A design objectives of Appendix I, 10 CFR 

Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) 

to the population. 

gases is based upon the assumption that Ke-135 is the controlling radioisotope 

and its HPC in air (submersion) was converted to an equivalent concentration in 

water using the methods described jn International Commission on Radiological 

Protection (ICRP) Publication 2. 

The concentration limit for dissolved or entrained noble 

This control applies to the release of radioactive materials in liquid 

effluents from all units at the site. 

The required detection capabilities for radioactive materials in liquid 

waste samples are tabulated in terms of the lower limits of detection (LLDs). 

Detailed discussion of the LLD, and other detection limits can be found in 

Currie, 1. A,, "Lower Limit of Detection: Definition and Elaboration of a 

Proposed Position for Radiological Effluent and Environmental Measurements ,'I 

NUREG/CR-$007 (September 1984), and in the HAS1 Procedures Manual, HASL-300. 

3/4.11.1.2 DOSE 

This control is provided to tnplement the requirements of Sections II.A, 

IfI.A, and 1V.A of Appendix I, 10 CfR Part 50. 

guides set forth in Section I1.A of Appendix I. The ACTION statements provide 

the required operating flexibility and at the same time implement the guides 

set forth in Section 1V.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low 

as is reasonably achievable." Also, for fresh water sites with drinking water 

supplies that can be potentially affected by plant operations, there is 

reasonable assurance that the operation of the facility will not result in 

radionuclide concentrations in the finished drinking water that are in excess 

of the requirements of 40 CFR Part 141. The dose calculation methodology and 

parameters in the ODCM ilnplement the requirements in Section 1II.A of 

Appendix J that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of 

a MEMBER OF THE PUBLJC through approprfate pathways is unlikely to be substantially underestimated. 

doses due to the actual release rates of radioactive materials $n liquid 

effluents are consistent with the methodology provided in Regulatory Guide 

1.109, "Calculation of Annual Doses to Man from Routine Releases of 

The Control implements the 

The equations specified in the ODCM for calculating the 

- W SREC c733 
RADIOACTIVE EFFLUENTS 

~~ 

- DOSE (Continued) 

Reactor Effluents for the Purpose of Evaluating Comp'liance with 10 CFR Part 50, 

Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating 

Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases 

for the Purpose of Implementing Appendix I," April 1977. 

effluents from each unit at the site. 

the liquid effluents from the shared system are to be proportioned among the 

units sharing that system. 

This control applies to the release of radioactive materials in liquid 

For units with shared Radwaste Systems, 

3/4.11.1.3 LlQUID RADWASTE TREATMENT SYSTEM 

The OPERABILITY of the Liquid Radwaste Treatment System ensures that this 

system wi I1 be available for use whenever 1 iquid effluents require treatment 

of this system be used when specified provides assurance that the releases of 

radioactive materials in liquid effluents will be kept "as low as is reasonably 

achievable.'' This control implements the requirements of 10 CFR 50.36a, 

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design 

objective given in Section I1.D of Appendix I to 10 CFR Part 50. The specified 

limits governing the use of appropriate portions of the Liquid Radwaste Treatment 

System were specified as a suitable fraction of the dose design objectives set 

forth in Section 1I.A of Appendix I, 10 CFR Part 50 for liquid effluents. 

effluents from each unit at the site. 

the liquid effluents from the shared system are to be proportioned among the 

units sharing that system. 

.prior to release to the environment. The requirement that the appropriate portions 

This control applies to the release of radioactive materials in liquid 

For units with shared Radwaste Systems, 

- W SREC C743 
RADIOACTIVE EFFLUENTS 

~ 

3/4.11.2 GASEOUS EFFLUENTS 

3/4.11.2.1 DOSE RATE 

This control is provided to ensure that the dose at any time at and 

beyond the SIT€ BOUNDARY from gaseous effluents from all units on the site 

will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. 

The annual dose limits are the doses associated with the concentrations of 

10 CFR Part 20, Appendix 8, Table 11, Column I. 

assurance that radioactive materia? discharged in gaseous effluents will not 

result in the exposure of a MEMBER OF THE PUBLIC In an UNRESTRICTED AREA, 

either within or outside the SITE BOUNDARY, to annual average concentrations 

exceeding the limits specified in Appendix B, Table I1 of 10 CFR Part 20 

(10 CFR Part 20.106(b)). 

the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be 

sufficiently low to compensate for any increase in the atmospheric diffusion 

factor above that for the SITE BOUNDARY. Examples of calculations for such 

UEM3ERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given 

in the OOCM. The specified release rate limits restrict, at all times, the 

corresponding gamma and beta dose rates above background to a MEMBER OF THE 

PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mremdyear 

to the whole body or to less than or equal to 3000 mremdyear to the skin. 

These release rate limits also restrict, at all times, the corresponding 

thyroid dose rate above background to a child via the jnhalation pathway to 

less than or equal to 1500 mremdyear. 

This control applies to the release of radioactive materials in gaseous 

effluents from all units at the sfte. 

The required detection capabilities for radioactive material in gaseous 

waste samples are tabulated in terms of the lower limits of detection (LLDs). 

Detailed discussion of the LLD, and other detection limits can be found in 

Currie, L. A., "Lower Limft of Detection: Definition and Elaboration of a 

Proposed Position for Radiological Effluent and Environmental Measurements ,'I 

NUREG/CR-4007 (September 1984). and in the HASL- Procedures Manual, HASL-300. 

3/4.11.2.2 DOSE - NOBLE GASES 

This control is provided to implement the requirements of Sections 1I.B. 

1II.A and 1V.A of Appendix I, 10 CFR Part 50. 

guides set forth in Section 1.8 of Appendix 1. The ACTION statements provide 

the required operating flexibility and at the same time implement the guides 

ret forth in Section 1V.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low 

as is reasonably achievable. I' The Surveil lance Requfremnts implement the 

requirements in Section 1IE.A of AppendSx f that conformance with the guides Of 

Appendix I be shown by calculational procedures based on models and data such 

that the actual exporuve of a HLMBER OF THE PUBLIC through appropriate pathways 

is unlikely to be substantially underestimated. 

These limits provide reasonable 

For HEWERS OF THE PUBLIC who may at times be within 

The control implements the 

The dose calculation 

3 SREC c751 
RAD I OACT I VE EF F LUENTS 

DOSE-NOBLE GASES (Continued) 

methodology and parameters established in the ODCM for calculating the doses 

due to the actual release rates of radioactive noble gases in gaseous effluents 

are consistent with the methodology provided in Regulatory Guide 1.109, 

"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents 

for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," 

Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating 

Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases 

from Light-Uater Cooled Reactors," Revision 1, July 1977. The ODCM equations 

provided for determining the air doses at and beyond the SITE BOUNDARY are 

based upon the historical average atmospheric conditions. 

This control applies to the release of radioactive materials in gaseous 

effluents from each unit at the site. For units with shared Radwaste Treatment 

Systems, the gaseous effluents from the shared system are proportioned among 

the units sharing that system. 

3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL 

IN PARTICULATE FOR M 

This control is provided to implement the requirements of Sections II.C, 

fl1.A and 1V.A of Appendix I, 10 CFR Part 50. The Controls are the guides set 

forth in Section 1I.C of Appendix 1. 

required operating flexibility and at the same time implement the guides set 

forth in Section 1V.A of Appendix I to assure that the releases of radioactive 

materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is 

reasonably achievable." The ODCM calculational methods specified in the 

Surveil lance Requirements implement the requirements in Section lII.A of 

Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a 

MEMBER OF THE PUIILIC through appropriate pathways is unlikely to be rubstantially underestimated. The ODCH calculational methodology and parameters for 

calculating the doses due to the actual release rates of the subject materials 

are consistent with the methodology provided fn Regulatory Guide 1.109, 

"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents 

for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," 

Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating 

Atmospheric Transport and Di spetsion of Gaseous Ef f 1 uents i n Routi ne Re1 eases 

from Light-Water-Cooled Reactors," Revision 1, July 1977. 

provide for determining the actual doses based upon the historical average 

atmospheric conditions. The release rate controls for Iodine-131 Iodine-133, 

tritium, and radionuclides in particulate form with half-lives greater than 

8 days are dependent upon the existing radionuclide pathways to man in the 

The ACTION statements provide the 

These equations also 

- W SREC [763 
RAD IOACTIVf EFFLUENTS 

DOSE - 30PINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE 

FORM -(Continued) 

areas at and beyond the SITE BOUNDARY. 

development of the calculations were: (1) individual inhalation of airborne 

radionuclides, (2) deposition of radionuclides onto green leafy vegetation 

with subsequent consumption by man, (3) deposition onto grassy areas where milk 

animals and meat producing animals graze with consumption of the milk and meat 

by man, and (4) deposition on the ground with subsequent exposure of man. 

This control applies to the release of radioactive materials in gaseous 

effluents from each unft at the site. 

Systems, the gaseous effluents from the shared system are proportioned among 

the units sharing that system. 

The pathways that were examined in the 

For units with shared Radwaste Treatment 

3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM 

The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST 

TREATMENT SYSTEM ensures that the systems will be available for use whenever 

gaseous effluents require treatment prior to release to the environment. 

requirement that the appropriate portions of these systems be used, when specified, 

provides relsonable assurance that the releases of radioactive materials in 

gaseous effluents will be kept "as low as is reasonably achievable." 7his 

control implements the requirements of 10 CFR 50.36a, General Design 

Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given 

in Section 1I.D of Appendix I to 10 CFR Part 50. 

the use of appropriate portions of the systems were specified as a suitable 

fraction of the dose design objectives set forth in Sections I1.B and 1I.C of 

Appendix I, 10 CFR Part 50, for gaseous effluents. 

The 

The specified limits governing 

This control applies to the release of radioactive materials in gaseous 

effluents from each unit at the site. 

Systems, the gaseous effluents from the shared system are proportioned among 

the units sharing that system. 

For units with shared Radwaste Treatment 

- w SREC 1771 
RADIOACTIVE EFFLUENTS 

BASES 

W4.11.2.5 NOT USED 

3/4 11.2.6 NOT USED 

3/4.1;.3 NOT USED 

314.11.4 TOTAL DOSE 

This control is provided to meet the dose limitations of 10 CFR Part 190 

that have been incorporated into 10 CFR Part 20 by 46 FR 18525. 

requires the preparation and submittal of a Special Report whenever the 

calculated doses due to releases of radioactivity and to radiation from 

uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, 

except the thyroid, which shall be limited to less than or equal to 75 mrems. 

for sites containing up to four reactors, it is highly unlikely that the 

resultant dose to a MEMBER Of THE PUBLIC will exceed the dose ljmits of 40 CFR 

Part 190 if the individual reactors remain within twice the dose design 

objectives of Appendix I, and if direct radiation doses from the units 

The control 

c W SREC C781 
RADIOACTIVE EFFLUENTS 

TOTAL DOSE (Continued) 

(including outside storage tanks, etc.) are kept small, The Special Report 

will describe a course of action that should result in the limitation of the 

annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. 

For the purposes of the Special Report, it may be assumed that the dose 

commitment to the MEMBER of the PUBLIC from other uranium fuel cycle sources is 

negligible, wl’th the exception that dose contributions from other nuclear fuel 

cycle facilities at the same site or within a radius of 8 km must be 

considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the 

requirements of 40 CFR Part 190, the Special Report with a request for a 

variance (provided the release conditions resulting in violation of 40 CFR Part 

190 have not already been corrected), in accordance with the provfoions of 40 

CFR 190.11 and 10 CfR 20.405c, Is considered to be a timely request and 

fulfills the requirements of 40 CFR Part 190 until NRC staff action is tompleted. The variance only relates to the limits of 40 CFR Part 190, and does 

not apply In any way to the other requirements for dose limitation of 10 CFR 

Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not 

considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged 

In carrying out any operation that is part of the nuclear fuel cycle. 

- w SREC 
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 

BASES 

3/4.12.1 MONITORING PROGRAM 

The Radiological Environmental Monitoring Program required by this 

control provides representative measurements of radiation and of radioactive 

materials in those exposure pathways and for those radionuclides that lead to 

the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting 

from the plant operation. This monitoring program implements Section IV. 8.2 

of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological 

Effluent Monitoring Program by verifying that the measurable concentrations of 

radioactive materials and levels of radt'ation are not higher than expected on 

the basis of the effluent measurements and the modeling of the environmental 

exposure pathways. 

Radiological Assessment Branch Technical Position on Environmental Monitoring, 

Revision 1, November 1979. The initially specified monitoring program will be 

effective for at least the first 3 years of commercial operation. 

this period, program changes may be initiated based on operational experience. 

Guidance for this monitoring program is provided by the 

Following 

The required detection capabilities for environmental sample analyses are 

tabulated in terms of the lower limits of detection (LLOs). The LLOs required 

by Table 4.12-1 are considered optimum for routine environmental measurements 

in industrial laboratories. 

as an a priori (before the fact) limit representing the capability of a measurement system and not as an 5 posteriori (after the fact) limit for a particular 

measurement. 

It should be recognized that the LLD is defined 

Detailed discussion of the LLD, and other detection limits, can be found 

in Currie, L. A., "Lower Limit of Detection: . Definition and Elaboration of a 

Proposed Position for Radiological Effluent and Environmental Measurements,'' 

NUREGKR-4007 (September 1984). and in the HASL Procedures Manual, HASL-300. 

3/4.12.2 LAND USE CENSUS 

This control is provided to ensure that changes in the use of areas at and 

beyond the SITE BOUNDARY are identified and that'modifications to the 

Radiological Environmental Monitoring Program gicen in the ODCM are made if 

required by the results of this census. The best information from the 

doorto-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements 

of Section XV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to 

gardens of greater than 50 m2 provides assurance that significant exposure 

pathways via leafy vegetables will be identified and monitored since a garden 

of this sire i5 the minimul required to produce the quantity (26 kg/year) of 

leafy vegetables assmed in Regulatory Guide 1.109 for consumption by a child. 

To determine this minimum garden size, the following assumptions were made: 

(1) 20% of the garden was used for growing broad leaf vegetation (f.e., similar 

to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2. 

- W SREC 
RAD I OLOGI C AL ENVI RONMENTAL MONITOR1 NG 

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 

The requirement for participation in an approved Interlaboratory Comparison 

Program is provided to ensure that independent checks on the precision and 

accuracy of the measurements of radioactive materials in environmental sample 

matrices are performed as part of the qual i ty assurance program for environmental 

monitoring in order to demonstrate that the results are valid for the purposes 

of Section IV.B.2 of Appendix I to 10 CFR Part 50. 

- W SREC 181 3 
APPENDIX A 

Radiological Assessment Branch Technical Position, 

Revision 1, November 1979 

C821 
Revisfon 3 

Wovembcr 1979 

Branch Tcchnfcal Posltion 

8rc kuround 

Regulatory Guide 4.8, Envlromentrl Technical Speclflcrtfons for Nucterr Power 

Plrntr, Issued for cement in December 1975, 1s belng nvlsed based on coaments 

recefued. The Radiologlcrl Assessment CIr8nch issued r Branch Posltlon on the 

rrdiologicrl portfon of the enviromentrl monitoring program in March, 1978. 

The posltfon was tormulrted by an NRC working group whlch considered coamnts 

received after the Issuance of the Regulatory Guide 4.8. This Is Revision 1 

the right Mrgln. 

rrdirtfon meisurement strtlons. 

of thrt Brrnch PoSltion paper. The ChngeS 8lV marked by 8 v@?tfC81 line in 

The most 8ignlfICwit chinge 1s the Increrse in direct 

10 CFR Parts 20 rnd 50 regufn thrt rrdiologicrt envlromtntrl monitoring 

progrunr be establfrhed to provlde drtr On wrsutrble five18 Of rrdirtfon rnd 

t8diO8CtiVe materlrls in the site environs. 

Part SO requires thrt the nlrtlonship between qurntltles of rrdiOrCtfV8 

arterfrl released in effluents durfng nornrt operrtlon, including mticiprted 

opetrtlonrl occurrences, and rerulfrnt trdlrtion doses to indivldurls from 

prlnclprls pathways of exposure be evaluated. These progruns should be conducted to verl fy the effectlveness of In-plrnt measures used for control ling 

the release of rrd$orctfve rrtrrirlr. Survelllrnce should be estrblished to 

identffy changer fn the use of unrestricted alters (8.9.. for rgricultrurt 

purposes) to provide I basis for modificrtions In t)re monitoring programs for 

evrluatinq doses to individuals fm ptlnclprl pathways of exposure. NRC 

Regulatory Gujde 4.1, Rev. 1, WProgr8ms for Monitoring Rrdiorctfvity In the 

'Envlrons of Nuclear Power Plmtr," provfdes an acceptable b88fS for the deslgn 

of programs to aonitor Iwelr of radiation and rrdforctivlty in the statIon 

envi rons . 

In rddltfon, Appendix I to 10 CfR 

This potftqon sets forth rn example of rn rcceptrble ainirm rrdlologfcrl 

aonftoring program. 

If pathwry8 not covered by thls guide rry slgniflcrntly contrlbute to an 

Individual's dose and should be Included 4n the srmpllng program. 

local sfte charrcterfstict must be examined to determine 

1833 
2 

AN ACCEPTABLE RADIOLOGICAL 

ENVIRONMENTAL CIONITORINC PROGRAM 

Ptoqram Reouirtmcnts 

Environmental sampler shall be collected and analyzed according to fable 1 at 

locations shown in figure 1. Ana1ytlcal techniques used shall be such that 

the detection capabilltles in Table 2 are achieved. 

The results of the radio?ogicr~ envimnmental aonftorfng we Intended to 

supy'-ment the results o? the r8diologicrl effluent monitoring by verifying 

thrt-ttw MASUr8b1e concentrations of radioactive rattrials rnd levels of 

radiation are not higher than expected on the basis of the effluent measurements and modeling of the enviroruncntal exposure prthW8yS. Thus, the specified 

environmental monitoring program provldes measurements of rrdiatlon and of rrdioactjve materials in those exposure prthwrys and for those radlonuclldes which 

lead to the highest potential radiation exposurus of indivldurls resulting from 

the station operation. The initial radio~ogfca~ environmental monf taring program 

should be conducted for the first three years of comrci81 operation (or other 

period corresponding to a naximum burnup in the Initial core cycle). following 

this period, program changes nay be proposed based on operatjonal experitnee. 

The specified detection crpabllitits are state-of-tht-rrt for routine tnvlronaental ncarureacnts in Industrial Irboratorirs. 

Deviations ars permitttd from tht tequfred sampling schedule 4f specimens are 

unobtainable due to hazardous conditions, seasona~ Un8V8il8bility, malfunction 

of rutomatic sampling equipment rnd other legltimatt reasons. 

8re unobtainrblt due to ramp?ing equipment malfunction, every effort shall be 

aade to complete corrective action prior to the end of the next sampling 

period. All deviations from the $-ling schedule shall be documented In the 

annual report. 

The laboratories of the licensee and l4censee's contractors which perform 

rnalyres shall participate In the Invironmental Protectfon Agency's (EPA' s) 

Environmental Rad1 oactivity Laboratory Intercomparisons Studies (Crosscheck) 

Program or equivalent program. This participation shall inctude all of the 

detennfnationr (sample medium-radionuclide combfnrtfon) that are offered by 

€PA and that also are included in the mnltodng program. The results of 

ana1ysis of there crosscheck sarnglar shalt be included fn the rnnua? report. 

The par:icipants in the €PA crosscheck program may provide their EPA program 

code so that the NRC can nufew the EPA's participant data directly In lieu of 

submSssion in the annual rtport. 

1 

If specimens 

I 

3 

It may be necessary to require special studies on a case-by-case rnd 

site specific basis to establish the'relatlonship between quantities of 

radioactive material released In effluents, the concentrations In 

environmental media, and the resultant doses for faportant pathways. 
3 

If the-results of a deteminrtion In the EPA crossch8ck progru (or equlvrtent progtcrn) are outsf de the spec4 f led control 1 lai ts , the 18bOr8tOQ shall fnvw 

tigate the cruse of the problem and take steps to correct It. 

this investigrtion and corrective rctfon shall be Included In the annual 

report. 

The requirement tor the partlclpation In the EPA crosscheck program, or simllaz 

program, Is brsed on the med for independent checks on the precisfon 8nd 

rccutrcy of the mtrsurementr of radioactive arterlal In envlronanntal sample rattices as part of the qmlity assurInce program for envfroment81 aonitoring 

In order to demansttrta that the reSdtS 8- nrsoQably valld. 

A census shall bt conducted rnnurtly during tht grwfng season to deteralne 

the location of the nearest milk rniarl and nearest garden greater than 

50 squrre meters (500 rq. ft. ) producing brord leaf vegetation fn erch of the 

16 meteorological sectors wlthin a dlstance of 8 kn (5 alles).s For elevattd 

relersrs as defined In Regulatoy Guide Llll, Rev. 1.. the census shall also 

,identify the locrtions of all dlk rnIar18, and gardens greater than 50 square 

meters producing broad lrr~egetation out to a distance of 5 km. (3 milts) 

for each radial sector. 

The results cf 

. 

- 

If 4t is teamed from this census that the allk anlnrls or gardens are present 

at 8 location which yields a crlculrted thyroid dose grerter than those ptevfOCSly sampled, or if the census results In changes In the locatlon used In the 

radZorctive effluent technical specltlcrtions for dose calculrtlonr , a wrltten 

report shall be submitted to the Director of Operating Reactors, NRR (wlth a 

copy to the DInctor of the WRC Reglonil Offlce) wlthln 30 drys identifyfng 

the new locition (diSt8Me and dlnctfon). Milk anfaat or garden locations 

.resulting in hlgher C8kulat.d doses shall be rddrd to the survelllrnce program 

8S SOOn IS pract~cabfe. 

The srmpllng locrtfon (rxcludlng the cbntrol sample locatlon) having the 

lowest crltulrted dose may then be dropped from the survelllance program at 

the end of the graz4ng or growing reason durlng which the census was conducted. Any location from whlcn allk can no longer be obtained nay be dropped 

from the surve~llance program rfter notlfyjng the WRC In wrltfng that they are 

no longer obtrinrblt at that location. 

shall be reported fn the annual =port. 

the census of milk animals and gardens produclng broad leaf vegetation is 

basad on the requirement in Appendix I of 10 CFR Part 50 to "Identify changes 

In the use of unrtstrfcted areas (e.9.. for rgriculturrl purposes) to permit aodifications in rronitorlng progwns for evaluating doses to ~ndlvldu8lS from 

principrl pathways of exposure." 

on contamfnrtcd pasture uw of b-iy vegetatfon contupfnrtrd by rlrbotne 

The results of the land-use census 

The consumptfon of .ilk from mluls grating 

Broad leaf vegetation saInptfng r.sy be performed at the site boundary in I 

sector with the highest D/Q In of the grrden census. 

I851 
4 

radioiodine is 8 major potcntfrl source of exposure. 

rre considered 8 better indicrtor of rrdioiodint fn the environment then 

vegetation. If the census reveals nllk rnimrls rre not prestnt or rre 

unavai1able for rrmpling, then vtgetrtion must be sunpled. 

The SO rquarc anter garden, considering 20% used for growing broad leaf vegetation 

(i.e., slmilrt to lettuce and cabbage), and 8 vegetrtion yield of 2 kg/m2, 

will produce the 26 kg/yr assumed in Rtgulrtory Guide 1.109, Rev 1.. for chlld 

consumption of leafy vtgetrtion. 

brord leaf vegetation rt tht rlte boundrry In I sector wlth the hightst O/Q 

should be conservative 8nd thrt locrtfon may be used to crlculrte doses due to 

+8diOrCtive effluent relerses In plrtc of the rcturt tocations which would be 

determined by the census. This option does not apply to plants with elevated 

telerses AS defined In Regulrtoty Guidt 1.111, Rev. 1. 

The fncrease fn the number of direct rrdfrtton strtlons 1s to better chrrrcterfre 

the individual exposure (mrem) rnd pop~18tfOn exposure (man-rem) In rccordrnce 

with Criterion 64 - Nonitoring rrdiorctivity releases, of 10 CFR Part SO, 

Appendix A. 

between the two rings designated in fable 1. 

Srmples from nllk rnimalr 

The option to consider the garden to be 

Tht NRC will place 8 slnllrr mount of stations In the area 

- NOTE 

Guidance on the subjects contained on pages 4 through 16 of the Radiolosical 

Assessment Branch Technical Position (RAB-BTP) has been mdif ied and upgraded 

based on opetatins experience sirtce Revision 1 was published in 1979. The 

current staff guidance for the follouing Itenis has been incorporated in the 

Section 3/4-12 and Section 6 Controls of NUREG-1301 and 1302. 

O Repotting Requirement 

Table 1: Opetationtl Radiological Environmental Monitoring Report 

' Table 2: Detection Capabf lities for Environmental Sample Analysis 

Table 4: Reporting Levels for Radioactivity Concentrations in Envfronmental Samples 

The following items remain unchanged: 

footnote to Table f on page 10 

O Table 3 of page '14 

O Figure 1 of page 16 

1863 
Pages 5, 6, 7, 8, 9, 11, 12, 13, 15 

The above pages have been superceded by text and tables 

in NURE6-1301 and 1302. 

C873 
- tAOLE 1 (Contitwed) 

Note: In addltlon to the above guidance for operational midloring, the follming materlal Is supplied for guidance 

on preoperational progrars. 

Prcopera t 1 ona I Env i ronmeii t a 1 Surve i 1 1 ance Program 

A Preoperational Environmental Stirvelllance Program should be instituted two years prior to the institution of station 

plant operation. 

TIN purposes of this program are: 

1. 70 measure background levels and their variations along the anticipated critical pathways in the area 

surrounding the statlon. 

2. To train personnel 

3. 

The elements (rampllng aedlr and type of analysis) of both preoperational and operational program should be cssenTo evaluate procedOr8s, equipment and techniques 

n tislly the saw. 

dD should IC followed: 

The durrtion of the pnoperaltonal program, for specific media, presented In the follming table 

U 

Otirrlfon of Preoperationrl Sapling Progran for Specific Media 

6 months 1 year 

. airborne iodine 

. iodine in ailk (while 

anlrals are in pasture) 

. airborne particulates 

. nllk (remaining analyses) 

. surface water 

. groundwater 

. drinking water 

2 years 

. direct radiation 

. flsh and invertebrates 

. food products 

. sediment from shoreline 
EMVI ROMNfAL RADIOLOGICAL MOMlTORtffi PROGRAM ANNUAL SMRY 

Name of Facility Docket No. - 

location of Facility - Reporting Pm -- t 

(County, Stale) 

Hedim or fYPe and Lower Limit All lndi cator Locatlon with Highest Control lacatdons Number of * 

(Unit of of Analyses Detection’ Mean (f) Nm *an (rib Rangt Repor ted 

Measurement) Performed (110) Raw bistancc & flange tleasunrcnts 

Pathway Sampled Total Nuder of locat ion8 Annual Mean Mean (f) Nonrout i M 

Di rec t i on 

n l3’CS 

W 

ko 

U 131 

Fish pCi/kg 

(mtweight) y-spec. 8 

137cs 

134c, 

“CO 

0.01 0.08(200/312) 

(0.05-2.0) 

0.01 0.05 (4/24) 

(0.03-0.13) 

0.07 0.12 (2/24) 

(0.09-0.18) . 

130 <llO 

130 <llO 

1 30 180 W4) 

(150-225) 

Hi ddl e town 0.10 (S/S2) 0.08 (8/104) 1 

5 riles 340° (0.08-2.0) (0. OS- 1.40) 

ai thvll le 0.08 (2/4) 

2.5 miles 160° (0.03-2.0) 

CLlO 4 

CI Podmk 0.20 (2/1) 0.02 (2/4) 1 0 

4.0 riles 270. (0.10-0.31) 

<llO CLLO 0 

River Mile 35 See Column I <llO 0 

See fable 2, note b. 

is indicated fn parentheses. (f) 

a 

bMean and range based won detectable measurements only. 

Mote: The example data are provided for Illustrative purposes only. 

Frrction of detectable measurements at specified locstlont 
FIgure 1 

(Thls figure shall be If a ruftable scale to show the distance rnd direction 

of each monitoring station. 

sampled 8t each location.) 

A kty shall be provided to indicate what Is 

c903 
APPENDIX B 

"Appendix B - General Contents of the Offsite Dose Calculatfon 

Hanua? (ODCM) (Revision 1, February 1979)" to the paper authored by 

C. A. Willis and F. 3. Congel, "Status of NRC Radiological Effluent Technical 

Specification Activities" presented at the Atomic Industrial Forum Conference 

on NEPA and Nuclear Regulation, October 4-7, 1981, Washington, D.C. 

1913 
APPENDIX B 

GENEiiAL CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (ODCM*) 

(Rev. 1, February 1979) 

Section 1 - Set Points 

Prwide the equations and methodology to be used at the station or unit for 

each alarm and trip set point on each effluent release point according to the 

Specifications 3.3.3.8 and 3.3.3.9. The Instrumentation for each alarm and 

trip set pofnt, including radiation monitoring and sampling systems and 

effluent control features, should be identified by reference to the FSAR 

(or Final Hazard SummaryL This Information should be consistent with the 

recommendations of Section X of Standard Review Plan 11.5, NUREG-75/087, 

(Revision 1). 

the equation to detennlne the set point value to be used, based on actual 

release conditions, that will assure that the Specification Is met at each 

release point; and provide the value to be used when releases are not in 

progress. If dilution or dispersion 1s used, state the onsite equipment 

and measurement method used during release, the slte related parameters and 

the set pofnts used to assure that the Specification is met at each release 

point. The fixed and variable set points should consider the radioactive 

effluent to have a radionuclide distribution represented by noma1 and 

antic I pa ted opera tional occurrences. 

If the alarm and/or trip set point value Is variable. provide 

Section 2 - Liquid Effluent Concentration 

Prwide the equations and methodology to be used at the station or unit 

for each liquid release point according to the Specification 3.11.1.1. for 

systems with continuous or batch releaset, and for systems designed to 

monitor and control both continuous and batch releases, prwide the assumptlons and parameters to be used to compare the output of the monitor with 

the 1 lqui d concentration Specified. State the 1 iml tations for comblned 

discharges to the same release point. In addition, describe the method and 

assumptions for obtsinlng tepresentatlve samples fran each batch and use of 

previous post-release analyses or canposlte sample analyses to meet the 

Spec4 f 4 cat io n . Section 3 - Gaseous Effluent Dose Rate 

Prwtde the equatlons and methodology to be used at the statlon or unit for 

each gaseous re1 ease point according to Speciffcation 3.11.2.1. Consider 

the varlous pathways, release point elevations, stte related parameters and 

radionuclide contributlon to the dose dmpact limitation. Provide the 

. 

The format for the ODCM Is left up to the licensee and may be slmpllfied by 

tables and grid printout. Each page should be numbered and indicate the 

facility approval and effective date. 

[921 
-2- 

dose factors to be used for the identified radionucltdes released. Provide 

the annual average dispersion values (X/Q and D/Q), the site speciffc parameters and release point elevations. 

Section 4 - Liquid Effluent Dose 

Provide the equations and methodology to be used at the statlon or unit for 

each liquid release point according to the dose objectives given in Specf- fication 3.11.1.2. The section should describe how the dose contributions 

are to be calculated for the various pathways and release points, the equa- tions and assumptions to be used, the site speclfic parameters to be measured 

and used, the receptor location by dlrutlon and distance, and the method of 

estimating and updating cumulative doses due to liquid releases. The dose 

factors, pathway transfer factors, pathway usage factors, and dilution factors for the pofnts of pathway origin, etc., should be given, as well as 

receptor age group, water and food consumption rate and other factors 

assumed or measured, Prwide the method of determining the dilution factor 

at the discharge during any liquid effluent release and any site speclfic 

parameters used in these deteminatlons. 

Section 5 - Gaseous Effluent Dose 

Prwjde the equations and methodology to be used at the statlon or unit for 

each gaseous release point according to the dose objectives given In 

Specificatfons 3.11.2.2 and 3.11.2.3. The sectfon should describe how the 

dose contributions are to be calculated forthe various pathways and release 

polnts, the equations and assumptions to be used, the t4te specific parameters 

to be measured and used, the receptor location by dlrection and distance, and 

the method to be used for estimating and updating cumulative doses due to 

gaseous releases. The location, dlrection and dlstanct to the nearest residence, cow, goat, meat animal, garden, ttc. , should be given, as we1 1 as 

receptor age group, crop yleld, grazlng time and other factors.assmed or 

measured. Provide the method of dctennlnlng dispersion values (X/Q and D/Q) 

for releases and any rite specific parameters and release point elevatlons 

used In these determinations. 

kctlon 6 - Projected Doses 

For liqutd and gaseous radwastt treatment systems, prwide the method of 

projecting Qur due to effluent releases for the nonnal and alternate 

pathways of treatment according to the tpecificatlons, describlng the components 8nd subsystems to be used. 

c933 
-3- 

Section 7 - Operability of Equipment 

Provide a flow diagtads) defining the treatment paths and the components of 

the radtoactive liquid, gaseous and solid waste management systems that are 

to be maintained and used, pursuant to 10 CFR 50.36a, to meet Technical 

Specifications 3.11.S.3, 3.11.2.4 and 3.11.3.1. Subcomponents of packaged 

equipment can be identified by a llst. For operating reactors whose construction pennit applications were flltd prior to January 2, 1971, the flow 

diagrm(s) shall be conslstent wlth the infonnation provided in conformance 

with Sectton Y.B.1 of Appendix I to 10 CFR Part 50. For OL applications 

whose construction permits were filed after January 2, 1971, the flow 

diagrarn(s1 shall be consistent wlth the infomation provided in Chapter 11 

of the Final Safety Analysis Report (TSAR) or amendments thereto. 

Section 8 - Sample Locations 

Prwfde a map of the Radiological Envirormental Manitotlng Sample Locations 

indicating the numbered sampling locations given in Table 3.12-1. Further 

clatificatfon on these numbered sampling locatfom can be prwlded by a list, 

lndlcating the direction and distance from the center of the bui1,ding complex of the unit or station, and may Include a discriptive name for identification purposes. 

. 

C943 
APPENDIX C 

GENERIC LEnER 89-01 

lHPLEHENfA7lON OF PROGRAMMATIC CONTROLS FOR RADIOLOGICAL EFFLUENT 

TECHNICAL SPECIF ICA'JIOIJS IN THE ADMINISTRATIVE CONTROLS SECTION OF 

THE TECHNICAL SPEClFICATIONS AND THE RELOCATION OF PROCEDURAL DETAILS 

OF RETS 70 IHE OFFSITE DOSE CALCULAlfOl4 MANUAL OR TO THE PROCESS 

CONTROL PROGRAM 
UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASMIIYOTON. 0. C. 20551 

January 31 , 1989 . 

TO ALL POHER REACTOR llCENSfLS AIID #.PPLICANTS 

SUBJECT: IMP1 EMEPTATION OF PROGRAMMATIC COtiTROLS FOR RADIOLOGICAL EFFLUENT 

TECHNICAL SPEClf ICATlOM IN THE ADMINISTRATfVt CONTROLS SECTION OF 

THE TEChNlCAL SPEClFICAfIONS AND THE RELOCATION OF PROCEDURAL DETAILS 

Of RETS 70 THE OFFSITE DOSE CALCUlAfION YANUAL OR TO THE PROCESS 

COhfROL PROGRAH (GENERIC LETTER 89-01 1 

the RRC staff has examlned the contents of the Padiologicrl Effluent Technical 

Speciftcations (RETS) in relation to the Cosmission's Interim Pollcy Statement 

on Technical Specification In rovments. The staff has detemined that prothe Technical Specifications (TS) to satisfy cxlstlng ngulrtorv nauirmcnts 

for RETS. At the same time, the procedural details of the current 7s on rrdloactive eff luents and trdiological tnvtronnrcntal aonltotlng can be relocated to 

the Offsite Dose Calculation Manual (ODCM). Likewise, the procedural details 

of the current TS OR mtfd rrdjoactfve wastes can be relocated to the Process 

Contrcl Program (PCP). fhesc rctlons simp1if.v the RETS, meet the re ulatom 

teouirements for radioactive eff luents and radiological envfronolcnta 0 mnttorfng. rnd are provjded as 8 IfndteJR fa~proveorent of the TS, consistent with the 

goats of the Policv Strtement. 

New programat ic controls for radioactive eff luents and radiologlul anvfronwntal aonitoring are incorporated in the TS to tonfom to the rcQulrtorv rcauitements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, rnd Appendix f 

to 10 CFR Part 50. Existing programtic mouirments for the PCP are being tetrined In the TS. The procedural detrttt Included In Ilcenteer' present TS 

on rrdloactive eff luents, solid radioactive wastes, environmental monltorlng, and rssocfated reporting reaufranents will be relocated to the ODCH or PCP 8s 

appropriate. IIcenseer will handle future changes to these procedural details 

in the ODCR and the PCP under the rdmfnlstrrtivc controls for changes to the 

ODW or PCP. Finallv, the definitions of the OOCg and PCP ate updated to 

reflect these changes. 

Enclosure 1 rovides guidance for the preparatlon of a lfcanse rntndnnt retng of existing RETS and 8 dcscrfptton of haw each Is addressed. Enclosure 3 

provides model TS for proprarmatlt controb for REIS rnd tts rssociated reportIn9 reouirementr. Fhrlfv, Enclosure 4 provides model spaclficrtions for 

retaining txirtlng rtaulrtmclnts for erploslve gas monitoring lnstnmntation 

reculrewnts tbrt rpplv on a ptant-specific basis. Llctnsaes we encouraged to 

propose changes to TS that are consistent with the guidance provlded In the 

en~l~r~tes. Conformlng auendlnent mutStS will bt expeditfoustv luvlcred bv 

graunatic controls can be imp 0 mented In the AdPrinistrrtive Controls sectton of 

ouest to Imp P colent these rlternativet for RETS. Enclosure 2 pmvldes 1 1SstC961 
Generfc letter 69-01 2 January 31, 1989 

the NRC Project Manager for the facility. 

from this guidance will require a longer, mort detailed review. 

the appropriate Project Manager If you have questions on this matter. 

Proposed amendments that dedate 

Please contact 

Si ncerely, 

Off4ce of Nuclear Reactor Regulatjon 

E nc 1 os ure s : 

1 through 4 8s stated 

C973 
Generic Letter 89-01 ENCLOSURE 1 

GUIDANCE FOR THE IMPLEMENTATION OF PROGRAMMATIC CONTROLS FOR RETS 

IN THE ADMINISTRATIVE CONTROLS SECTION OF TECHNICAL SPECIFICATIONS 

AND THE RELOCATION OF PROCEDURAL DETAILS OF CURRENT RETS TO THE 

OFFSITE DOSE CALCULATION WUAL OR PROCESS CONTROL PROGRAM 

lNTRODUCTION 

This enclosure provides guidance for the preparation of a licehse amendment 

request to implement programmatic controls in Technical Specificrtfons (TS) 

for radioactive effluents and for radiological environmental monitoring conforming to the applicable regulrtory requirements. 

tion of existing procedural details of the current Radiological Effluent 

Technical Specifications (RnS) to the Offrite Dose Calculation Manual (ODCM). 

Procedural details for solid rrdioacttve wastes will be relocated to the 

Process Control Program (PCP). A proposed amendment will (1) incorporrte progrrnmatic controls in the Administrative Controls section of the TS that satlsfy the requirements of 10 CFR 20.106, 40 CfR Part 190, 10 CfR 50.36a. and 

Appendix I to 10 CFR Part 50, (2) relocate the existing procedurrl details in 

current specifications involving radioactive effluent monitoring instrunentation, the control of liquid rnd gaseous effluents, equipment requirements for 

liquid and gaseous effluents, radiological environmental monitoring, and radiological reporting details from the TS to the ODCW, (3) relocate the definftion 

of solidification rnd existing procedural details In the current specification 

on solid radioactive wastes to the PCP, (4) simplify the rssociated reporting 

requirements, (5) sirnplify the administrative controls for chrnges to the ODCM 

rnd PCP, (6) add record retention requirements for changes to the ODCM rnd PCP, 

rnd (7) update the definitions of the ODCM and PCP consistent with these 

changes. 

The NAC staff's Intent in recanmending these changes to the TS and the relocation of procedural details of the current RETS to the ODCH rnd PCP is to fulfill the goal of the Commission Policy Statement for Technical Specification 

!mprovements. It 4s not the staff's intent to reduce the level of rrdiological 

effluent control. Rather, this mndment will provide progrumnatlc controls 

for RETS consistent with regulatory requinments rnd allow relocation of the 

procedural details of current RETS to the ODCM or PCP. Therefore, future 

changes to these procedural details will be controlled by the controls for 

changes to the ODCH or PCP Included in the Administrative Controls section of 

the TS. These procedural details rre not required to be Included In TS by 

10 CFR 50.36a. 

This will allow the relocaDISCUSSION 

€nclosure 2 to Generic letter 89- 

tions that are included under the heading of RETS in the Standard Technlcal 

Speciffcattons (STS) and their disposition. Most of these specifications will 

be rddrersed by programmatic controls %n the Mministrativs Controls section of 

the TS. Some rpecifieatSons under tk kcrding of RETS are not covered by the 

new programmatic controls and wll1 be retained as requirements in the existing 

plant TS. Examples Include requfremcnts for explosive gas rronltorlng Instrumentation, limitattons on the quantity of radioactivity in liquid or gaseous 

holdup or storage tanks or in the condenser exhaust for BURS, or Ifaftations on 

explosive gar mixtures in offgas treataent systems and storage tanks. 

provider a sugmary listing of specifica- 
Cenetfc Letter 89- 01 -2- Enclosure 1 

,Licensees with nonstandard TS should follow the guidance provided in Enclosure 2 for the disposition of similar requirements in the format of their TS. 

Because solid radioactive wastes rrc addressed under existing programmatic controls for the Process Control Program, which is a separate progrrm from the 

new programmatic controls for liquid and gaseous radioactive effluents, the 

requfrements for solid radioactive wastes and associated solid waste reporting requirements in current TS are included as procedural details that dl1 be 

relocated to the PCP as part of this line-item improvement of TS. Also, the 

staff has concluded that records of licensee reviews perforated for changes made 

to the ODCM and PCP should be documented and retained for the duration of the 

unit operating license. This approach is in lieu of the current requirements 

that the reasons for changes to the ODCM 8nd PCP be rddressed in the Semiannual 

Effluent Release Report. 

The following ftems art tu be included 4n a license amendment request to implement these changes. First, the model specifications in Enclosure 3 to Generic 

letter 89- should be fncorporrted into the IS to satisfy the requirements of 

10 CfR 20.106, 40 CFR Part 190, 10 CFR 50.36a. 8nd Appendix I to 10 CFR Part 50. 

The definitions of the ODCH and PCP should be updated to reflect these changes. The programmatic and reporting requirements are general In nature and do not 

contain plant-specific details. Therefore, these changes to the Administrative 

Controls section of the TS are to replace corresponding requirements in plant TS that address these items. They should be proposed for incorporation into 

the plant's TS without change in substance to replace existing requirements. If necessary, only changes in format should be proposed. If the current TS 

include requirements for explosive gas monitoring instrumentation as part of 

the gaseous effluent monitoring instrumentation requirements, these requirements should be retained. provides model 

Second, the procedural detalls covered in the 'licensee's current RETS, consisting of the limiting conditions for operation, their applicability, remedial 

rctlons, survtlllance nqufrtaents, rnd the Baser section of the TS for these 

requirements, are to be relocated to the ODCH or PCP 8s appropriate and In 8 

manner that ensures that these detafls are incorporrtcd In plant operating pro- cedures. The HRC staff does not Intend to repeat technical reviews of the relocated procedural details because their consistency with the applicrble regulatory requirements Is a matter of record from past NRC reviews of RETS. 

licensees make other than editorial changes in the procedural details being transferred to the ODCM, each change should be identified by markings in the 

margin and the requirements of new Specification 6.14a.(l) and (2) followed. 

Enclosure 4 to Generic Letter 89- 

rpecif icationr for retaining such requirements. I 

If 

Finally, licensees should confirm in the rmendment request that changes for 

relocating the procedural details of current RETS to either the ODCM or PCP 

have been prepared in accordance wfth the proposed changes to the Administrative Controls section of the 75 so that they my be Impleaentad imedirtely 

upon issuance of the proposed amendment. A complete and legible copy of the 

revised ODCM should be forwarded With the amendment request for NRC use as I 

reference. The NRC staff wfll not concur in or approve the revised ODCH. 
Cenerfc tetter 89-01 -s- Enclosure 1 

Licensees should refer to '6eneric letter 89- in the Subject line of llcente 

amendment reauestr inplcmentlng the guldrnce of thlr Generic letter. This will 

frcilltate the staff's tracking of licensees' responses to this Cencric letter. 

SUMMARY 

the license amenmcnt rcouest for the line-item lnprovements of the TS talstivc 

to the RETS will entail (1) the incor oratlon of progrumtic controls for 

istrative Controls section of the TS, (2) tncorporatation of the procedural details of the current RETS in the ODCH or PCP as appropriate, 8nd (3) confirmation thrt the guidance of thls Generic letter has been follwed. 

- 

rrdfoactive eff lucnts and trdfo1oglcr P envtronrrrentrl aonftoting 4n the AdminClOO3 
DISPOSITIMI OF SPECtFICATtOWS AW- AbnIMISTRATIVt CONTROLS 

IMClUDED UhDER HEADm RE 1s 1w TlrL STAHDARD TL CHRICAL SP m IChf 101s 

TITLE SPECIF ICATIM - 

1.17 OFFSITE DOSE CALCULATION MANUAL 

1.22 PROCESS CONTROL PR06M 

1.32 SOL IDlFICAT1OW 

3/4,3,3.10 RADlOACTlVE LIQUID EFFLUERT 

~nITORIN6 IWSTRUMEMATIOII 

3/4 03 03 0 11 RAOIOAMIVE 6ASEbUS EFFLUENT 

ROlrltoRIW6 IIISTR~RTATlOll 

n 

0 

d 

-. 

3/4.110101 LIQUID EFFLUENTS: COMCERTRATIOl U 

3/40 11 01 02 LIQUID EFFLUENTS: DOSE 

3/1.11.1.3 LIQUID EFFLUEMS: LIQUID 

RAMIASTE TREAfnlEMT STSTEW 

3/4.11.1 04 LIQUID HI)LDUP TAWS 

trISPOSITIMl OF EXISTIN6 SPEClFfCAtlO1 

Definltlon is updated to reflect the change In scope of the ODC% 

btfinltion is updated to reflect the change in scope of the PCP, 

beflnltion 1s relocated to the PCP. 

Prograratlc controls are included In 6.8.4 g. Item 1). 

Exlrtlng speclflwtlon procedural details are relocated 

to the OOCN. 

Pmgraamtlc controls an Included in 6.8.4 g. Item 1)- 

Lrlsting speclflcatlon procedural details an relocated 

to the Oocn. Existing reaalnwntr for explosive gas 

amitoriq Inttrumentrtlon should be totalned. Me1 

spedflcrtions for these reaulmments are prorlded In 

Enclosure 40 

Progrmrtlc controls are Included In 6.8.4 9. Item 2) 

and 3). Erlstlng tpecif4ution procedural deklls 8re 

relocited to the Oocn. 

Progrmnrtlc controls are Included In 6.8.4 go It- 4) 

and 5). Exlrtlnp spcclflcatlon procedural detrlls are 

relmbd to tk Oacno 

Pmgramtlc controls are Included in 6.8.4 9. Item 6). 

Exlttlmq speclflcatlon procedural detsllt are relocated 

to the Oaar. 

Existing speclf lcrtlon rmlnncnts to be trtilnedO 

m 

¶ 

c) 

0 

H 

c 

9 

m 

d 
SPEC IF 1 CAT I ON 

3/4 11 020 1 

3/4 11 a2 2 

3/4e 11 a2 3 

3/4 11 a2 4 

n 

0 

ru 

--. 

U 3/1 11 e2.5 

3/4m 11 2 6 

3/4mllm2.7 

314.11 2m0 

0 I SPOS IT ION OF SPEC 1 F !CAT IONS CI NO ADMI N 1 STRAT I VF CONTROLS 

INCLUDEO UNDER-PHE HERD~KKRTS 1N TH mPD TECHNICAL SPmTIONS (Cont.1 

- TITLE 

GASEOUS EFFLUENTS: DOSE RATE 

GASEOUS EFFLUENTS : DOSE-WBLE 

GASES 

GASEOUS EFFLUENTS: b(lSE--lM)lIE131, IODIWE-133, TRlTfUM, AND 

RADIOACTlVE MATERIAL 11 PARTICULNL FOM 

GASEOUS EFFLUENTS: GASEOUS 

RAOWASTL TREATMERT or 

VENTfLATIOl EXHAUST TREATNE'llt 

SYSTEM 

EXPLOSIVE 6AS MIlttURf 

6AS STORME TANKS 

WIN CONOENSER (IW) 

PURGtllG AlrO VENT1116 (BUR Mark I1 

con ta 1 men t s 1 

SOLID RMIOACTIVE UASTES 

RADIOACTlVE EFFLUENTS: TOTAL 

MISE 

0 I SPOS ITION OF EX1 STING SPEC IFICATlON 

Progrmmstle controls are included In 6.8.4 g. Item 3) 

and 7)m Cxlstlng rpeciflcation procedural details are 

relocated to the OOCdm 

Prograrmrstle controls ate Included In 608.4 9. Item 51 

and 8). Existing speciflcrtlon procedural detai 1s are 

relocated to the ODm, 

Programtic controls are Included In 6m8m4 g* Items 5) 

and 9). Lxlstlng speciflcrtlon procedural dctalls are 

relocated to the OOCMm 

Programtlc controls Ineluded in 6m8m4 9m Item 6)m 

Existing speclf lcrtltm procedural detallr are relocated 

to the ODCHm 

Existing speclflc~tfon ?eouImmnts should be -trimdm 

Erlstlng spedflcatlon noulmnts should be retained, 

Exlstlng speclf lcatbn noulrmcntt should be retalned, 

Prograamtlc controls are fncluded in 6m8.4 em Item 10). Exlsting speclflcrtion procedural dctalls are relocated 

to the Oocn. 

Eilstlng tpeclflcrtlan procedural detalls are relocated 

to the PCP. 

Programrtlc controls are Included In 6m0.4 g. Item 11). Lrlstlng rpeclfiwtlon procedural detalls are relocated , 

to the ODCH. 
r) 

?PEC1 F I CAT ION - TITLE 

3/4 12.1 

3/4m12m3 

-. 

0 6.9 a 1 a3 

w 

U 

6m9m1.4 

6*13 

6.14 

6.15 

RAD1OLOGlCAL ENVIRONHEMTAL 

FtONITORlNG: WONllORIN6 PR06RAM 

RADIOLOGICAL ERVIROMM€1CTAL 

))OWITORIIG: LAND USE CENSUS 

RAbIOLO6IeAL ENVIRONN€MTAl 

MONITORING: lNTERLABORATORT 

COMPARISON PROGRAH 

DESIGM FEATURES: SITE - NAP 

DLFIWlW UlcR€STRlCTfD AREAS AM0 

SITE BOUNDARY FOR RADIOACTIVE 

GASEOUS AND LIQUID EFFLUENTS 

REPORTING REQUIREMRTS: AWUAL 

RAD 1OLO6 ICAL LNV IRONHEllt A1 

OPERATIHG REPORT 

REPORTIN6 REQUIREMENTS: SEMIANNUAL RADIOACTIVE EFFLUEIT 

RELEASE REPORT 

PROCESS COCrtROL PROGRM 

OFFSITE DOSE CALCULATION NAIUAL 

MAJOR CHANGES TO LIQUID, GASEOUS, 

AND SOLID RADWASTL TREAIMENT 

$1 STENS 

VE- COMThOL S 

1 SP€ClFrn TIONS (Cont 1 m 

cb 

5 

rn 

c) 

0 I SPOS If ION OF EX I STING SPEC IF KAT Io11 1 

P 

(. 

rg 

Progranmatic controls are Included In 6.8.1 ha Itm 1). 

Exlstlng speclflcatlon procedural details are relocated =$ 

to the 0E)CN. 1 

Ptogramstlc controls rre Included In 6.8.4 ha Item 2). 

Extstlng speclf Icatlon procedural dctalls are relocated 0, 

to the ODCnm 

I 

Progta~tlc controls are included In 608.4 ha Item 3). 

Exlstlng speclflcatlon procedural dctalls are relocated 

to the ODCHm 

Exlstlng speclflcatlor, ~lmncnts should be ntalncd. 

8 

w 

8 

Speclf Icrtlon simpllfled and cxlstlng reporting details 

are relocated to the WCM, 

Specltlcrtlon slmpllfled rnd e!tlstlng reporting dctalls 

an relocated to the ODCR or PCP as approprlate. 

Spcclficrtlon rmulrements are slnrpllf led. 

Speclflcrtlon narlnnents are slmpllfled. 

Exfstlng pmcedurrl 

PCP as approprlrtc. 

details rre relocated to the ODCR or 

m 

3 

0 

d 

c 

'I 

0 

(u 

I 
Generic Letter 8901 Enclosure 3 

1.17 

1.22 

6.8.4 g. 

6.8.4 h. 

6.9.1.3 

6.9.1.4 

6.10 

6.13 

6.14 

TECHNICAL SPECIFICATIONS TO BE REVISED 

DEFINITIONS: OFFSITE DOSE CALCULATION MANUAL 

DEFINITIONS: PROCESS CONTROL PROGRAM 

PROCEDURES AND PROGRAMS: RADIOACTIVE EFFLUENT COHTROLS 

PROCEDURES AND PROGRAMS: RADIOLOGICAL EWIRDWENTAL WNITORING 

REPORTING REQUIREHENTS: ANNUAL RADIOLOGICAL ENVIRONMENTAL 

OPERATING REPORT 

REPORTING REQUIREMENTS: SEMIANNUAL RADIOACTIVE EFFLUENT 

RELEASE REPORT 

RECORD RETENTION 

PROCESS CONTROL PROGRAM (PCP) 

OFFftTE DOSE CALCULATION MANUAL (ODCM) 

HODEL TECHNICAL SPECIFICATION RNISIONS 

(To supplement or replace existing specifications) 

1.0 DEFINITIONS 

OFFSITE DOSE CALCULATION MANUAL 

1.17 The OFFSITE DOSE CALCULATION WUAL (ODCH) shall contain the methodology 

and parameters used in the calculation of offsltt doses resulting frola r8dioactive gaseous and liquid effluents, in the crlculrtion of gaseous and liquid 

effluent monitoring AlaMrfp Setpoints, rnd in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the 

R8dioactive Effluent Controls md Radiological fnvironmntal Monltortng Programs required by Section 6.8.4 and (2) descriptions of the Infomat’ion that 

should be fncluded in tht Annual Radlological fnv$ronmtnta\ Operating md Semiannual Uad3oattive Effluent Release Reports required by Specifications 6.9.1.3 

rnd 6.9.1.4. 

1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the curnnt formulas, 

sampling, analyses, test, and dcteminations to be made to ensurt that processing and packaging of sol id radioactive wastes based on dernonstrattd proctssing 

of actual or simulated wet solid wastes will be accumplishtd in such 8 way as 

to assure compliance with 10 CFR Parts 20, 61, and 71, State ngulrtfons, 

burial ground requirements, rnd other requirements governing the disposal of 

solid radioactive waste. 
Generic Letter 89- 01 -2- Enclosure 3 

6.0 ADMINISTRATIVE CONTROLS 

6.8 PROCEDURES AND PROGRAMS 

6.8.4 The following programs shall be established, inplementad, and maintained: 

g. Radioactive Effluent Controls Program 

A program shall be provided conforming with 10 CFR 50.368 for the 

control of trdioactive effluents and for maintaining the doses to 

MEMBERS OF ?HE QUBLIC froa radioactive effluents as low as reasonably achievable. The program (1) tha?? be contained in the ODCH, 

(2) shall be bptemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are 

exceeded. The program shall include the following elements: 

Limitations on the operability of rrdioactive liquid and gaseous monitoring instrumentation including surveillance tests rnd setpoint determination In accordance with the methodology in the 

ODCH, . 

Lirnitatjons on the concentrations of rrdioactive oaterial 

mleased in liquid effluents to UNRESTRICTED AREAS conforming to 

10 CFR Part 20, Appendfx B, Table If, Column 2, . 

Honltoring, sampling, and analysis of radioactfve liquid rnd 

gaseous effluents In rccordance with 10 CFR 20.106 and with the 

methodology and parameters in the ODCH, 

timit8tions on the rnnual rnd quarterly doses or dose comitment 

to a HEHBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix 1 to 10 CFR Part 50, 

Dctemination of cmulrti ve and projected dose contributions 

from radioactive effluents for the current calendar quarter and 

current calendar year in accordance with the methodoloQy and 

parameters In the ODCH at least every 31 days, 

LInitations on the operability rnd use of the liquid rnd gaseous effluent tnetrnent systems to ensure that the appropriate portiohr of these systems are.usrd to reduce releases of radioactivfty when the projected doses in a 31-day period would 

exceed 2 percent of the guidelines for the annual dose or dose 

commitment conforming to Appendix I to 10 CFR Part 50, 

Limitations on the dose rate resulting from radioactive material 

released in gaseous effluents to areas beyond the SITE BOUNDARY 

conforming to the doses rssociated with 10 CFR Part 20, 

Appendix 8, fable IX, Column 1, 

t1053 
Generic Letter 89ql -3- Enclosure 3 

ADMINXSTRATIVE CONTROLS 

6.8.4 0. Radioactive Effluent Controls Proqram (Cont. 1 b 

0) limitations on the annual and quarterly air doses resulting from 

noble gases released in gaseous effluents from each unft to 

areas beyond the SIT€ BOUNDARY conforming to' Appendix I to 

10 CFR Part 50, 

9) limitations on the annual and quarterly doses to a MEMBER OF 

THE PUBLIC fm lodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the 

SITE BOUNDARY confoming to Appendix I to 10 CFR Part SO, 

'_ 10) Limitations on venting and purging of the Hark I1 containment 

through the Standby Gas freatracnt System to maintain releases 

as low as reasonably achievable (BURS w/Hark I1 containments), and 

11) Limitations on the annual dose or dose commitntnt to any MEMBER 

OF THE PUBLIC due to releases of radioactivity and to radiation 

from uranium fuel cycle sources conforming to 40 CFR Part 190. 

h. Radiological Environmental Moni toting Program 

A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide 

(1) representative aeasureatents of radioactivity in the highest potential exposure pathways, and (2). verification of the accuracy of 

the eff luent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, 

(2) conform to the guidance of Appendix I to 10 CFR Part SO, and 

(3) include the following: 

1) Honitorhg, sampling, malysir, rnd reporting of radiation and 

radionuclides in the environment 4n accordance with the methodology and parameters In the ODCM, 

2) A Land Use Census to entun that changes in the use of areas at 

and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the 

results of this census, and 

ParticfpatCon in a Interlaboratory Comparison Program to ensure 

that fndepcndent checks on the precision and accuracy of the 

aeasurcmentr of radioactive materials in environmental sample 

matrices are performed as part of the quality rssuranct program for environmental monitoring. 

3) 

C1061 
Generic letter 8931 -4- Enclosure 3 

ADMINX STRAT IVE CONTROLS 

6.9 REFORTING REQUIREMENTS 

ANNUAL RADIOLOGICAL EWIROWNTAL OPERATING REPORT* 

6.9.1.3 The Annual RadfQIDgkal fnv<ronmtntal Operating Report covering the 

operation of the unft during the previous calendar year shall be submitted 

before Hay 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental 

Monitoring Program for the reporting period. 

consistent with the objectives outlined io (1) the ODCM and (2) Sections 

IV.B.2, IV.B.3, and lV.C of Appendix I to 10 CFR Part 50. 

The material provided shall be 

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT** 

6.9.1.4 The Semiannual Radioactive Effluent Release Report covedng the operation of the unit during the previous 6 months of operation shall be submitted 

within 60 days after January 1 rnd July 1 of each year. The report shall include a summary of the quantities of radioactive liqufd and gaseous effluents 

and solid waste released from the unit. The aaterial provided shall be 

(1) consistent wfth the objectives outlined in the ODCH and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. 

6.10 RECORD RETENTION 

6.10.3 ?he following records shall be retained for the duration of the unit 

Operating license: 

o. Records of revieus performed for changes made to the OFFSITE DOSE 

CALCULATION WAL and the PROCESS CONTROL PROGRAM. 

6.13 PROCESS CONTROL PROGRAM (PCP) 

Changes to the PCP: 

I. Shall be documented ad retords of reviews performed shall be retained as required by Sptctfication 6.30.30. This docurnentation shall 

conta i n: 

1) Suffjclent fnforutfon to ruapott the change together with the 

approprtate analyses or avaluatjonr justifying the change( s) and 

*A tingle tubmittat ray $e made for 8 multi-unit station. 

**A single rubnrtttal may be made for a multi-unit station. The submittal 

should codFne those sections that are common to all units at the station; 

t)owever, for units with separate radwaste systems, the submittal shall specify 

the releases of radioactive material from each unit. 
'Generic Letter 89-01 -5- Enclosure 3 

ADMXNI STRAT IVE CONTROLS 

6.13 PROCESS CONTROL PROGRAM (PCP) (Cont. 1 

2) A determination that the change will maintain the overrll conformance of the solidified waste product to existing require- 

=nents of Federal , State, or other appl i cab1 e regul rtf ons . b. Shall become effective after review and acceptance by the [URG] and 

the approval of tht Plant hnrger. 

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 

Changes to the DDCM: 

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.30. This documentation shall 

contain: 

1) Suffjcitnt 4nformation to support the change together with the 

rpp~oprirte analyses or evaluations justifying the change($) rnd 

2) A detemination thrt the change will maintain the level of 

radioactive effluent control required by 10 CFR 20,106, 40 CFR 

Part 190, 10 CfR S0.36a. and Appendix I to 10 CFR Part 50 and 

not adversely impact the accuracy or re1 i ab1 1 ity of eff 1 uent , dose, or setpoint calculations. 

bo 

c. 

Shall become effective after review and acceptance by the [URG] and 

the approval of the Plant Uanager. 

Shall be submitted to the Cornissfon fn the forn of a complete, legible copy of the entire ODCM as 8 part of or concurrent wlth the 

Stmiannual Ridfoactjue Effluent Release Report for the period of the 

report in which any change to the ODCM was made. Each change shall 

be identified by markings in the margin of the rffected pages, clearly fndicatlng the area of tht page that was changed, md shall 

indicate the date (e.&, aonth/year) the change was iaplemented. 

. 
Generic Letter 89- 01 Enclosure 4 

MODIFICATION OF THE SPECIFICATION FOR RADIOACTIVE GASEOUS 

EFFLUENT MONITORING INSTRUMENTATION TO RETAIN REQUIREMENTS 

FOR EXPLOSIVE GAS MONITORING INSTRUMENTATION 

’ 

INSTRUMENTATION 

mVE GASEOUS-f f f WENT MONITORING INSTRUMENTATION 

ExPLosrvE 

LIMITING CONDITION FOR OPERATION 

exp!osivt 

3.3.3.11 The tadtoatttre gaseous-effqatnt monitoring instrumentation channels 

shown in Table 3.3-13 shall be OP€RABLE wfth thefr Alarmnrip Setpoints set to 

ensure that the 1 imits of Specif fcation~3A3~~3-and 3.11.2.5 are not 

exceeded. 

3rf~t~t~-shs~~-be-dete~m~ned-and-ad~asted-~n-a~ea~danee-u~th-the-~et~odo

~nd-paramctcrs-~n-t~e-eB€~~ 

The- Af armfTrip-Se tpai ntr-of -the~e-ehannets-meeti ng-bpeci f 4 eati an 

APPLICABILITY: As shown in Table 3.3-13 

ACT1 ON: 

a. 

- 

txp! os i V$ 

With an tadteatttvt gaseous-tfftuent monitoring instrumentation 

thanner AlatnTTrip Setpoint less conservative than required by the 

above spec 1 f i cat i on;-inmtdiatcfy-rarptnd-the-ret care-of-+ad+ oatti ve 

gartoas-ef fSaentr-men4 toTed-by-the-af feettd-ehannd;-o+ declare the 

channel inoperable and take the ACTION shown in Table 3.3-13. 

With less than the minimum number of w ra taacttre gaseous-effhnt 

monitoring instrumentation channels OPERABLE, take the ACTION shown 

in Table 3.3-13. Restore the $noperable instrumentation to OPERABLE 

status within 30 days and, If unsuccessful axptain-in-t~c-next-Samiannas3-Radiaatth-f ff~scnt-Rt3tare-Rcpa+t prepare and tubmi t a 

Special Report to the Commission pursuant to Specification 6r9rPt4 

3.9.2 to explaln why this inoperability was not corrected in a timely 

manner. 

b. 

c. The provisions of Specification 3.0.3 and 3.0.4 are not appltcablc. 

SURVEILLANCE REQUIREMENTS 

exp! os f ve 

4.3.3.11 Each vadtaacttrc gascaar-effhent mnftmfng instrumentation channel 

shall be demonstrated OPERABLI by performance of the CHANNEL CHECK, 5WR€E 

€HECK; CHANNEL CALIBRATIOW and UI(IL0G CHANNEL OPERATIONAL TEST at the 

frequencies shown in Tale 4.3-9. 

Sample STS 3/4 3-(n) 

C1091 
I 

TABLE 3.3013 

INSTRUHENT 

1. (Not used) 

2A. WASTE 6AS HOLDUP SYSTEH Explosive 61s 

Ronltorlng Srstea (for systems daslgned 

to wlthstand the effects of 8 hvdragtn explos Ion ) 

8. hdrogen Honltor (Autmtlc Control) 

b. Hrdrogen or Oxygen Uonltor (Pracess) n w -. + b 2B. UASTE 6AS HtKOUP StStUl Errploslre 68s 

0 (9 Monftorlng Systcm (for systems not designed L-l # to wlthstand the effects of 1 hvdrogcn 

--. 

T cxploslon) w 

a. Hydrogen knltors (Autorrstlt Control, redundant) 

b. Hrdrogen or Olrygen Manltors (Process, dual ) 

1 

1 

2 

2 

+* 

*. 

++ 

t* 

8 

0, 

19 

19 

t 

w 

t 

50, 52 

50 
_- 

..:A - 

TABE'3.3-13 -(thfinue'a- 

* (Not used) 

** During WASTE GAS HOLDUP SYSTEM operation. 

ACTION STATEMENTS 

ACTION 45 - 

ACTION 46 - 

ACTION 47 - 

ACTION 48 - 

ACTION 49 - 

ACTION 50 - 

ACTION 51 - 

ACTION 52 - 

Sample STS 

Enchrurr 4 

- 

(Not used) 

(Not used) 

(Not used) 

(Not used) 

With the number of channels OPERABLE less than required by the 

Minimum Channels OPER4BLL requirement, operation of this UASTE 

GAS HOLDUP SYSTEM may continue provided grab smplas 8M 

collected at least once per 4 hours and analyzed within the 

following 4 hours. 

With the number of channels OPERABLE one less than required by 

the Hinimuea Channels OPERABLE requi rcment, operation of this 

system ray continue provided grab samples are taken rnd analyzed 

at least once per 24 hours. 

operatfon may continue provided grab samples are taken and 

analyzed at least once per 4 hours during degassing operations and at least once per 24 hours during other operations. 

With both channels inoperable, 

(Not used) 

With the number of channels OPERABLE one less than required by 

the Minimum Channels OPERABLE requirement, suspend oxygen 

supply to the recombiner. 

314 3-(n+2) 

c1113 
TABLE 4.3-9 

EXPLOSIVE 

mVE GASEOUS FfFkUEMS ?WMITORIlG INSTR~lTATIOl SURVElIJANCE PEQUIREMENTS 

I, (lot used) 

2A. WASTE @AS HOLDUP SYSTEM Exploslra 

~ar flonltoring Srttem (for srstms 

designed to ul thstand the effects 

of a hydrogen erplosion) 

a, hdmgm Monltor 

w (Autmtfc Control) 

\ 

nb 

4 b. Hrdrogcn or Orsgen Monitor 

(?meets 1 A” 1 

-3 

hJn 

U W 28. WASTE 6AS HOLDUP SYSTEM Eaplotlrc 6as Honl torlng Srstm (for system 

not deslgned to withstand the effects 

of a hydrogen ctploslon) 

a, Mydrogcn bnltott 

b. Hrdmgan or Oxygen Wanltars 

(Autmtlc Control redundant) 

(Process, dual) 

CHANNEL MODES FOR WHICH 

- CHARNEL 68URSE CMANREL OPERATIOHA1 SURVL ILLANCL CHECK -c CMESK CALIBRAtIOIl TEST IS REQUIRED 

4+ 

++ 

m 

3 

c) 

d 

on 

1’ 

c 
Generic Letter 89- 01 -5- Enclosure 4 

TABLE 4.3-9 (Contlnuedl 

TABLE NOTATIONS 

* (Mot used) 

** 

(1) (Not used) 

(2) (Not used) 

During WASTE 6AS HOLDUP SYSTEM operation. 

(3) (Not used) 

(4) The CHANNEL CALIBRATION shall Include the use of standard gas samples contai ni ng a nod nal : 

a. 

c. 

(5) The CHANNEL CALIBRATION shall Include the use of standard gas samples contai ni ng a nod nal : 

a. 

b. 

One volume percent hydopn, brtrnce nitrogen, and 

Four volume percent hydrogen, brlrnce nitrogen. 

One volume ptrcent oxygenr balance nitrogen, rnd 

Four volume percent oxygen, balance nitrogen. 

Sample STS 314 3-(n+4) 

C1131 
NRC CGRV 335 

NPCN llC? 

3101 3202 

US NUCLEAR REGULATORV COMMISSION 

12 a9 

BIBLIOGRAPHIC DATA SHEET 

instructtons on the reverse! 

2 TITLE AND S'JBTITLE 

Offsite Dose Calculation Manual Guidance: Standard 

Radiological Effluent Controls for Pressurized Water 

Reactors 

Generic Letter 89-01, Supplement No. 1 

5 AUTHOR[SI 

W. Wayne Meinke and Thomas H. Essig 

12. KEY WORDS/DESCR!PTORS kist lrordr WM~S th.1 rrili&t nrmh.n In hating th*wn.) 

Generic tetter 89-01 

Licensee Guidance 

Effluent Controls 

Radiological Environmental Monitoring 

Effluent Monitoring 

Pressurized Water Reactors 

8. PERFORMING ORGANIZATION - NAME AND ADDRESS 111 NRC. morde Divrrmn, Olficeor Rwion. US Nuclear Rupulatory Co 

-e Urd Nllhp .domSk.l 

13. AVAILABILITY STATEMENT 

Unlimited 

ir. tECU01TY CLASSIF)C*TI@J 

flNr rrrl 

Unclassified 

Unclassified 

IThb Il.pOnl 

15. NUMBER OF PAGES 

1 REPORT NU?aBEh 

(Awnid bv NRC Add Vol.. SUI~P, Rev. end Mdondnrn Nvmbrr, It anv I 

NUREG1301 

I. DATE REPORT PUBLISHED 

MOklH VC46 

Apr i 1 ' 1991 

I. FIN OR GRANT NUMBER 

N/A 

5. TYPE OF REPORT 

Industry Guidance 

7, PERIOD COVERED rmc1urr.e Oat.., 

Division of Radiation Protection and Emergency Preparedness 

Office of Nuclear Reactor Regulation 

U.S. Nuclear Regulatory Comission 

Washington, D.C. 20555 

g SPONSORING ORGANIZATION - NAME AND ADDRESS 111 NRC type "'Samearaborr rf cantrutor prorrdeNRC Owwon Offhwor Rmmn US Nuck~ Rrpu&rorv Commrwon 

end nmilmp .ddnrr.l 

Same as above 

10 SUPPLEMENTARY NOTES 

11 ABSTRACT 1200 wowh or &sl 

This report contains guidance which may be voluntarily used by licensees who choose 

to implement the provision of Generic Letter 89-01, which allows Radiological 

Effluent Technical Specifications (RETS) to be removed from the main bcdy of the 

Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). 

Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. 

Guidance on the formulation of RETS has been available in draft form (NUREG0472 and 

-0473) for a number of years: the current effort simply recasts those RETS into 

Standard Radiological Effluent Controls for application to the ODCM. 

for coapleteness are: 

previously which had been available as a Branch Technical Position (Rev. 1, November 

1979); (2) existing ODCM guidance: and (3) a reproduction of Generic Letter 89-01. 

Also included 

(1) radiological environmental monitoring program guidance 

16, PRICE I----