NRC Generic Letter 1989-01

NRC Generic Letter 1989-001, Supplement 1: NUREG-1302 - Offsite Dose Calculation Manual Gudiance: Standard Radiological Effluent Controls for Boiling Water Reactors

ML031290469
Person / Time
Issue date:	11/14/1990
From:	Partlow J Office of Nuclear Reactor Regulation
To:
References
NUREG-1302 GL-89-001, Suppl 1, NUDOCS 9012040345
Download: ML031290469 (9)

°sUNITED

0 STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555 November 14, 1990

TO ALL BWR LICENSEES

SUBJECT: NUREG-1302 - 'OFFSITE DOSE CALCULATION MANUAL GUIDANCE:

STANDARD RADIOLOGICAL EFFLUENT CONTROLS FOR BOILING WATER

REACTORS" (GENERIC LETTER 89-01, SUPPLEMENT NO. 1)

Enclosed, for your information, is a copy of the subject NUREG report. This NUREG report does not impose any new requirements or staft positions; its use is therefore totally voluntary.

The subject NUREG supersedes prior draft guidance for RETS (NUREG-0473) for those licensees who elect to implement Generic Letter 89-01. Licensees not electing to implement this Generic Letter should continue to follow the prior draft RETS guidance.

nmes G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure: As stated

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2. TITLE AND SUBTITLE NUREG-1 302 OFFSITE DOSE CALCULATION MANUAL GUIDANCE: STANDARD RADIOLOGICAL 3. DATE REPORT PUBL!SHED

EFFLUENT CONTROLS FOR BOILING WATER REACTORS MONTvi l ELA

Sept. 1990

Subtitle: Generic Letter 89-01, Supplement No. 1 4. FINORGRANTNUMBEF

N/A

6. TYPE OF REPORT

S. AUTHOR(Si W. Wayne Meinke and Thomas H. Essig Industry Guidance

7. PERIOD COVERED fmnci,.w^u Darec N/A

-ft .. A -- - A _ n... -~ u s ~~ N Co *irion *i^d m lr~a ddftis.

Artt~~~t oiftractr.rtDrw,,c rnomeand moilng addressJ

Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 provide NRC DOirion. Offse or Region. U.&NUClearRftujtorVCon.nMs*,on.

9. SPONSORING OR GAN IZATI ON-NAME AND ADDRESS (If NRC. trpe 'Samea, Baove-: if contracror and mailingeddress.)

Same as above

10. SUPPLEMENTARY NOTES

11.ABSTRACT 1200words or lrss'

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 Efflu- ent 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 environ- mental 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 0DCM. Also included for completeness are: (1) radiological environmental monitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, November

1979); (2) existing 00CM guidance; and (3) a reproduction of Generic Letter 89-01.

ttopr ) 13. AVAILABILITY ST AT EMENT

12. KEY WORDSIDESCR !PTORS {Lasg words eor hrows reat will MJirfa"earcher 0n jloaring the Unlimited SEURIT_ Y CLA__

Generic Letter 89-01 Licensee Guidance _

Effluent Controls Unclassified Effluent Monitoring UTls i ieeort Radiological Environmental Monitoring Unclassified

15. NUMBER OF PAGES

Boiling Water Reactors

120

16. PRICE

NRC FORM 33512491

NUREG-1302 Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors Generic Letter 89-01, Supplement No. 1 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation W.W. Meinke, T. H. Essig

ABSTRACT

licensees who This report contains guidance which may be voluntarily used by allows Raoio- choose to implement the provision of Generic Letter 89-01, which (RETS) to be removed from the main logical Effluent Technical Specifications Calculation and placed in the Offsite Dose body of the Technical Specifications definitions, Manual (OUCK). Guidance is provided for Standard Effluent Controls Controls for effluent releases, Controls for effluent monitoring instrumentation, basis for Controls.

Controls for radiological environmental monitoring, and the fore (NUREG-0472 Guidance on the formulation of RETS has been available in craft recasts those RETS

anc -C473) for a number of years; the current effort simply the ODCN. Also into Standard Radiological Effluent Controls for application to monitoring program included for completeness are: (1) radiological environmental Position guidance previously which had been available as a Branch Technical of ODCM guidance; and (3) a reproduction (Rev. 1, November 1979); (2) existing Generic Letter 89-01.

iii

PREFACE

contains all This compilation of Standard Radiological Effluent Controls (SREC) into a of the controls addressed in Generic Letter 89-01, to be incorporated time the procedural licensee's Offsite Dose Calculation Manual (ODCH) at the (RETS)

details of the current Radiological Effluent Technical Specifications (TS). It has are transferred out of the licensee's Technical Specifications Standard Technical been developed by recasting the RETS of the most current of an ODCM

Specifications from the LCO" format into the "Controls formatW-SREC. The entry. Note that these GE-SREC have been patterned after the of the most recent SREC,

following text guidance incorporates the wording W-SREC

however, no attempt has been made to translate REC numbering of the into that of the BWR numbering system.

and docu- The following GE-SREC provide the latest version of staff guidance,

10 CFR 20.106, ment current practice in the operating procedures required by

10 CFR Part 50. This

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

V

TABLE OF CONTENTS

Page iii ABSTRACT ............................. *.... *............

PREFACE ................................................

FOREWARD. *................... ................. [1]

1 DEFINITIONS.............. 9.99...-.. -9 ... I.....9.

9*9 - [5)

[15i

3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS................. [163

3/4.0 Applicability1................................ ........

[18]

3/4.3 Instrumentation.o.o.....................................9

.. [39)

3/4.11 Radioactive Effluents............................. [59)

3/4.12 Radiological Environmental Monitoring.................

[74]

3/4 BASES ..................................... ............

[85]

APPENDIX A: Radiological Assessment Branch Technical Position, Revision 1, November 1979

[94;

APPENDIX B: General Contents of the Offsite Dose Calculation Manual

[98]

APPENDIX C: Generic Letter 89-01 GE-SREC vii

11 FOREWORD

RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS

requests for incorporation of Licensee Technical Specification (TS) amendment (RETS) pursuant to 10 CFR 50.36a Radiological Effluent Technical Specifications in the mid-1980s for most and Appendix I to 10 CFR Part 50 were approved Plants licensed after 1979 operating reactors licensed before 1979 (ORs).

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

all licensees of operating power By November 1987, the RETS were implemented documented the accept- reactors. Detailed Safety Evaluation Reports (SERs) the acceptance of the RETS

ability of the plant-specific RETS of the ORs, while Standard Technical Specifi- for the NTOLs followed the regular pattern of the compliance of the licensee cations (STS). Thus, for all operating plants, the 50 is a matter of record.

with 10 CFR 50.36a and Appendix I to 10 CFR Part to licensees in mid-1978, Early draft revisions of model RETS, distributed determinations and meteoro- contained equations for dose calculations, setpoint details for complying logical dispersion factors, as well as the procedural including Revision 2 with Appendix I to 10 CFR Part 50. In later revisions,of OR RETS, the equations used as the bench mark for the NRC staff's acceptance Dose Calculation Manual (ODCM)

were removed and incorporated into an Offsite for review along with the proposed prepared by the licensee and provided to NRC

RETS.

Effluent Technical Specifi- Early guidance for preparation of the Radiological (ODCM) was published in cations (RETS) and Offsite Dose Calculation Manual Technical Specifications for HUREG-0133, Preparation of Radiological Effluentof model RETS, however, have been Nuclear Power Plants," October 1978. Copies Revision 2, "Radiological Effluent available only in draft form as NUREG-0472, NUREG-0473, Revision 2, Technical Specifications for PWRs," February 1, 1980; BWRs,: February 1, 1980;

Radiological Effluent Technical Specifications for for the Radiological and succeeding draft revisions. Staff guidance the Radiological Assessment in Environmental Monitoring Program is contained issued in March i978 and Branch Technical Position (RAB-STP), originally of the accident at Three upgraded by Revision 1 in November 1979 as a result forwarded to all operating Mile Island. This Revision 1 to the RAB-BTP wasin effect at the present time.

reactor licensees in November 1979 and remains Regulatory Guide System, a copy Since this UIP was never incorporated into the Even though it has been used is reproduced in this document as Appendix A. contents of the ODCM is found extensively in reviewing ODCMs, guidance for theAtomic Industrial Forum confer- only in an appendix to a paper presented at an since that time.

ence in 1981, and has had only informal distribution OFFSITE DOSE CALCULATION MANUAL

ODCM through transfer of the The potential for augmentation of a licensee'sguidance of Generic Letter 89-01, procedural details of the RETS following the documents the staff guidance provides an opportunity to assemble in one set of for the ODCM.

GE-SREC t1

of the ODCM was prepared origi- The current overview guidance for development 1979 after discussions with commit- nally in July 1978 and revised in February guidance was made generally This tees of the Atomic Industrial Forum.Contents of the Offsite Dose Calculation available as "Appendix B - General to the paper authored by Manual (ODCM) (Revision 1, February 1979)" NRC Radiological Effluent Technical of C. A. Willis and F. J. Congel, "Status Specification Activities" presented at the Atomic Industrial Forum Conferenceof

4-7, 1981, Washington, D.C. -A copy on NEPA and Nuclear Regulation, October to date, is reproduced in this document this guidance that continues in effect as Appendix B.

the implementation of the RETS by the ORs, During the discussions leading up ato"living" document certain interpretations it became important to record in The ODCM thus became a and understandings reached in these discussions.

well as for other information requested repository for such interpretations, as of licensee's commitments and by the staff in connection with its evaluation I to 10 CFR Part 50.

performance under 10 CFR 50.36a and Appendix TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM

contents of the RETS in relation to Recently, the NRC staff has examined the on Technical Specification Improve- the Commission's Interim Policy Statementprogrammatic controls can be implemented ments. The staff has determined that of the Technical Specifications (TS) to in the Administrative Controls section for RETS. At the same time, the satisfy existing regulatory requirements radioactive effluents and radiological procedural details of the current TS on to the Offsite Dose Calculation environmental monitoring can be relocated Manual (ODCM).

controls for radioactive effluents and To initiate the change, new programmatic are incorporated in the TS to conform to radiological environmental monitoring

20.106, 40 CFR Part 190, 10 CFR 50.36a, the regulatory requirements of 10 CFR procedural details included in and Appendix I to 10 CFR Part 50. The environmental monitoring, and licensees' present TS on radioactive effluents, be relocated to the ODCM. Licensees associated reporting requirements will details in the ODCM under the will handle future changes to these procedural the ODCM. Detailed guidance to effect administrative controls for changes tois given in Generic Letter 89-01, repro- the transfer of the RETS to the ODCM

duced in Its entirety as Appendix C.

GUIDANCE FOR THE TRANSFER OF RETS TO ODCM

89-01 of Appendix B provides detailed the Enclosure 1 of Generic Letter (GL) license amendment request to implement guidance for the preparation of a enclosure states:

transfer of RETS to ODCM. Page 1 of the

--- the relocation of procedural OThe NRC staff's intent in recommending is to fulfill the goal of the details of the current RETS to the ODCM Specification Improvements. It Commission Policy Statement for Technical level of radiological effluent is not the staff's intent to reduce theprovide programmatic controls for control. Rather, this amendment will and allow relocation of the RETS consistent with regulatory requirements ODCM."

procedural details of current RETS to the GE-SREC [2]

Page 2 of Enclosure 1 states:

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

consisting of the limiting conditions for operation, their applica- bility, remedial actions, surveillance requirements, and the Bases 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 NRC staff does not intend to repeat technical reviews of the relocated procedural details because their consistency with thE applicable regulatory requirements is a matter of record from past NRC reviews of RETS."

DISCUSSION

the RETS

For the purpose of the transfer described in GL 89-01 of Appendix B, of Appen- will consist of the specifications from the STS listed in Enclosure 2 analogous dix B of GL 89-01. Licensees with nonstandard TS should consider the TS in their format.

It is suggested that the most straightforward method of transferringtoa recast licensee's commitments in the RETS to the ODCM in accordance with GL 98-01 is Opera- the RETS in the licensee's present TS from the uLimiting Condition for The tion (LCO)u format of the TS into the 'Controls' format of the ODCM entry.

Radio- accompanying package provides an example of this recasting into StandardReactors logical Effluent Controls (SREC) from the model RETS for Boiling Water (BWRs). This recasting is in format only. The TS pages have been transferred'LCO. 3 to the ODCM without change except for the substitution of 'Controls' for use Plants that have RETS that closely follow the STS format will be able to the accompanying examples directly as guidance. For plants with nonstandard page RETS, the transfer of TS commitments to the ODCM should be made similarly by page, again with the substitution of 'Controls' for ULCO.U

This NUREG report contains no new requirements; licensee implementation of this guidance is completely voluntary.

SUMMARY

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

89-01 has RETS, a licensee confirms that the guidance of Generic Letter followed. This guidance includes the following:

The procedural details covered in the licensee's current RETS, con- sisting 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 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 required10byCFR

10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36(a), and Appendix I to Part SO. 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.

GE-SREC [3]