ML19323C632

Forwards Review Re Applicability of post-TMI Action Plan Requirements Contained in Draft 3 of NUREG-0660 & Applicability of Item III.A.2-2 of NUREG-0654.Response to All Action Plan Items,Except Item II.B.8 Planned for

ML19323C632
Person / Time
Site:	Atlantic Nuclear Power Plant
Issue date:	05/06/1980
From:	Haga P OFFSHORE POWER SYSTEMS (SUBS. OF WESTINGHOUSE ELECTRI
To:	Baer R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0654, RTR-NUREG-0660, RTR-NUREG-654, RTR-NUREG-660 FNP-PAL-088, FNP-PAL-88, NUDOCS 8005160415
Download: ML19323C632 (13)

Text

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. - 8 00516 0 ^//5 FNP-PAL-088 5: era ::mr 3 f atoms May 6, 1980 Mr. Robert L. Baer, Chief Light Water Reactor Branch No. 2 Division of Project Management U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20852

,Re: Docket No. STN 50-437; Application of Post-TMI Action Plan Requirements to the Floating Nuclear Plant

Dear Mr. Baer:

In a meeting on April 30, 1980 Offshore Power Systems and the NRC Staff reviewed the post-TMI action plans contained in Draft 3 of NUREG-0660. During the meeting agreement was reached concerning the applicability of each action item to Offshore Power Systems and the extent to which applicable items need be addressed prior to initial issuance of the manufacturing license. These agreements are documented in the attached table. At the request of the Staff, Offshore Power Systems agreed to review NUREG-0654* to determine the extent to which its requirements (and hence action item III.A.2-2) apply to the manufacturing license. This review has been completed, and our assessment is also reported in the attached table, under item III.A.2-2.

Offshore Power Systems intends to respond to all action plan items, except item II.B.8, in early July. Our response to item II.B.8 will be provided as soon as possible following publication of the proposed new rules in July 1980. We trust that this schedule is compatible with issuance of the final l SER Supplement at the earliest possible date.

Si y i l

P. B. Haga l

• " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of .

Huclear Power Plants" l

/lel Attachment CC: V. W. Campbell A. R. Collier l

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APPLICATI0ft 0F TMI ACTION ITEMS TO

""* I THE FLOATIrlG flUCLEAR PLAf1T -

U APPLIES ADDITIONAL INFORMATION REQUIRED I

SUBJECT TO H.L.7 FOR INITIAL M.L. ISSUANCE 7 '

NO RM RS

} YES NO YES NO LOCATION OF EXISTING INFO.

1.A Operational Safety

• X 1.B.1 Management for Operations

• X Subitem 1.B.1-1 applies; see below 1.B.1-1 Organization and Management Combine with II.J.3 Improvements 5 X X Note 1 1.B.2 Inspection of Operating Reactors

• X 1.C.1 Short-Term Accident Analysis WCAP 9600/9601 and Procedure Rev. 4 X X WCAP 9691. Note 1 1.C.2 Shift Relief Turnover Ic X 1.C.3 Shift Supervisor Ic X Responsibilities 1.C.4 control Room Access Ic X 1.C.5 Feedback of Operating Note 2 Experience 4 X X 1.C.6 Verification of Operating Activities Ic X 1.C.7 NSSS Vendor Procedure Review Ic X 1.C.8 Pilot Program Ic X N.T.O.L.

1.C.9 Long-Term Ic X Program Plan 1.D.1 Control Room Design Review 4 X X Combine with I.D.4 Note 2

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$! APPLIES ADDITIONAL INFORMATION REQUIRED l

SUBJECT TO M.L.? FOR INITIAL M.L. ISSUANCE 7 NO REMARKS h YES NO YES NO LOCATION OF EXISTING INFO.

1.D.2 Safety Parameter Console 4 X X Partial: Ref. 1, p. D-14 Note 2 1.D.3 System Status Monitoring 4 X X Ref. 1, p. D-6 Note 2 1.D.4 Control Room Design Standard 4 X X Note 2 1.D.5 Control Room Research Ib X 1.D.6 Control Room Technology Ib X Transfer 1.E Analysis & Dissemination of Subitem 1.E.4 Operating Experience

• X applies; see below 1.E.4 Coordination of Programs 4 X X Note 2

1. F.1 Expanded QA List ,

4 X X Note 2 1.F.2 Detailed QA Criteria 4 X X Note 2 1.G Training During Low Power Testing IC X II.A Siting

• X II.B.1 RCS Vents 4 X X Ref. 1, p. C-3 Note 2, Include H2 Analyses under II.B. 8 II.B.2 Plant Shielding 4 X X Partial: Ref. 1, p. B-17 Note 2 II.B.3 Post-Accident Sampling 4 X X Partial: Ref. 1, p. 24 Note 2

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APPLIES ADDITIONAL INFORMATION REQUIRED ITEM SUBJECT TO M.L.? FOR INITIAL M.L. ISSUANCE 7 NO. El REMARXS YES NO YES NO LOCATION OF EXISTING INFO.

II.B.4 Training Ic X II.B.5 Research Ib X II.B.6 High Population Density Sites Ic X II.B.7 Containment Inerting Id X Refer to Item II.B.8 II.B.8 Rulemaking in Degraded Core 5 X x Note 2, Interim Rult Accidents due July 1980 II.C Reliability Engineering & Item II.C.4 applies Risk Assessment

• X See below II.C.4 Reliability Engineering 3 X X Note 2 II.D.1 RCS Safety Valve Test 4 X X Partial: Ref. 1, p. B-4 Note 2 Requirements II.D.2 Demonstrate Valve Research 3 X X Note 2 Applies to FNP II.D.3 Safety Valve Position 4 X X Partial: Ref. 1, p. B-5 Note 2 Indication II.E.1-1 Auxiliary Feeduater Evaluation 3 X X Note 2 I I . E.1-2 Auxiliary Feedwater Auto-Start 4 X X Ref. 1, p. B-21 Note 2

& Flow Ind.

II . E.1-3 SRP and Reg. Guide on Aux. Feedwater Ib X II.E.2-1 Reliance on ECCS 2 X X

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gg SUBJECT TO M.L.?

YES YES FOR INITIAL M.L. ISSUANCE 7 NO LOCATION OF EXISTING INFO.

NO II.E.2-2 ECCS Research Ib X II.E.2-3 Uncertainties in LOCA 3 X Note 2 Predictions II.E.3-1 Decay lleat Removal - Natural 4 X X Ref. 1, p. B-2 Note 2 Circulation II.E.3-2 Decay liest Removal Systems Ib ,

X Reliability II.E.3-3 Studies of Feed & Bleed Id X Ref. to Item II.C.4 Decay lleat Removal II.E.3-4 Alternate Concepts Ib X II.E.3-5 Decay lleat Removal Reg. Guide Ib X II . E.4-1 Dedicated Ctmt. Penetrations 5 X X Ref. 1, p. B-12 Note 2 II.E.4-2 Containment Isol. Depend- 4 X X Ref. 1, p. B-8 Note 2 ability PDR Sect. 12.2 (Table 12.2.1)

II . E.4-3 Containment Integrity Check Ib X II . E.4-4 Containment Purging 4 X X Note 2 II.E.5 Sensitivity of B&W Reactors Ic X l

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$2 APPLIES ADDITIONAL INFORMATION REQUIRED I

SUBJECT TO M.L.? FOR INITIAL H.L. ISSUANCE 7 NO REMARKS y YES NO YES NO LOCATION OF EXISTING INFO.

II.E.6 In-Situ Valve Testing lb x Additional Accident II.F.1 Monitoring Instr. 4 x x Ref. 1, p. B-26, p. C-1 Detection of Inadequate II.F.2 Core Cooling 4 x x Ref. 1, p. B-6 Note 2 II.F.3 Regulatory Guide 1.97 4 x x Note 2 II.F.4 Control & Protection Actions Ib x Power for PORV, 1801.

II.G Viv., and PZR Level 4 x x Ref. 1, p. B-2 Note 2 Subitem 11.11.3 1 1 . 11 TMI Cleanup

• x Applies; See Below I 1 . 11 . 3 Evaluation and Feedback 4 x x II.J.1 Vendor Inspection Program Ib x II.J.2 Consttuction Insp. Program Ib x Management for Design II.J.3 and Construction 5 x x (Note 3) 11.K.1 I&E Bulletins in 1 Sa 6 Related Valve Positions 2 Part x Ref. ', p. A-9 Rene,a1 of Safety 2 Equipment from Service IC x Ref. 1, p. A-12

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$! APPLIES ADDITIONAL INFORMATION REQUIRED IE TO M.L.? FOR INITIAL H.L. ISSUANCE 7 NO SUBJECT h , 3

} YES NO YES NO LOCATION OF EXISTING INFO.

3 PRZR Level Trip Ic x Ref. 1, p. A-4 Note 2 4, 5 Applies to B&W only x 6, 7 Applies to BWR only x II.K.2 Applies to B&W only x II.K.3 Bulletins & Orders T.F.

(Note 4) Recommendations 1 PORV Isolation System Id x Refer to Item 2 Analyze Safety of PORV 2 Isolation System 3 x x  !!ote 2 Reporting of S.V. and 3 PORV Failures 2 x x Review of Non-Safety Equip- Refer to items 4 ment for LOCAs Id x II.C.1, 2, 3 Automatic RCP Trip 5 on LOCA Id x

! Instrumentation to Verify 6 Natural Cire. 2 x x Partial: Ref. 1, p. B-6 7, 8 Applies to B&W only x 9 PID Controller Modification 2 x x Reply will state Rx Trip on Turb. Trip

' at issue is 10 Above 50% Power 2 x x out of scope.

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NO SUBJECT h REMARKS

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Use of PORVs Supplied by 11 Control Components, Inc. 4 x x Note 2 Confirm Reactor Trip on 12 Turbine Trip 2 x x PDR Section 7.2 13-29 Applies only to BWRs x Review Small LOCA Cales.

30 to Comply W/ Appendix K 3 x x Note 2 Revise FNP LOCA Cales.

31 to Comply W/Part 50.46 3 x x Note 2 Experimental Verification of 32 Two Phase Flow Models Ic x 33 Eliminate PORVs? lb x

. RELAP-4 Model 34 Development Ib x 35-43 Applies to B&W Only x 44-48 Applies to BWRs only x NRC Review of 49 Procedures Ib x NSSS Vendor Review 50 of Procedures Ic x Symptom-Based 51 Emergency Procedures Ib x 52,53 Applies to BWRs only x

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54 Simulator Upgrading Ic x Operator Monitoring of 55 Control Board Ic x 56 Simulator Training Rcquirsente Ic x 57 Applies to BWRs only Ic x III.A.1-1 Upgrade Emergency Prepared 3ess Ic x In III.A.1-2 Upgrade Support Facilities 4 Part x Ref. 1, p. B-39, p. B-41.

III.A.1-3 Thyroid Blocking Agent Ic x Emergency Preparedness III.A.2-1 Rule Changes Ic x III.A.2-2 Cofdar.ce and Criteria (Note 4) for Em. Preparedness Emergency Response A Organization and Control Ib x Onsite Emergency B Organization Ib x Emergency Response C Support and Resources Ib x D Classification of Emergencies lh x

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Notification Methods E and Procedures Ib x

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E APPLIES ADDITIONAL INFORMATION REQUIRED IT TO M.L.7 FOR INITIAL M.L. ISSUANCE 7 NO SUBJECT (( REMARKS Ic YES NO YES NO LOCATION OF EXISTING INFO.

to F Emergency Communications Ib x i

C Public Information Ib x Emergency Facilities Except for the sub-H and Equipment Ib items below, iten H i is out of scope, nsite Technical Duplicated by item H.1 Support Center Id x III.A.1-2 Duplicated by items H.5 Onsite Monitoring Systems Id x f.2, _

.3-3 Onsite Operational Duplicated by H.9 Support Center ld x item III.A.1-2 Except for the sub-

, 1 Accident Assessment Ib items below. This item in nut-nf-cenn.i

. Parameters Indicative of I.1 Various Conditions Ib x t

Radiation Monitoring and Duplicated by items l

I-2 Sampling Id II.B.3, II.D.3-3,

{ II.F.1 and II.F.3 j

! J Protective Response Ib x i

K Radiological Exposure Control Ib x L Medical Support Ib x Recovery and Reentry j M Planning lb x

- N Exercises and Drills, Ib x l

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I U APPLIES ADDITIONAL INFORMATION REQUIRED SURJECT TO M.L.? FOR INITIAL M.L. ISSUANCE 7 NO REMARKS

} YES NO YES NO LOCATION OF EXISTING INFO.

Radiological Emergency 0 Response Training Ib x Responsibility for P Planning Effort Ib x Improve NRC Emergency Except for subitems III.A.3 Preparedness Ib x below, this item is ni,e-n f-ne nn, _

III.A.3-4 Nuclear Data Link 4 x x Note 2 Emergency Preparedness State III.B and Local Covernments

• x III.C Public Information Ib x Radiation Source Control III.D.1-1 Outside Containment 4 x x . Partial: Ref. 1, p. B-15 Note 2 III.D.1-2 Radioactive Gas Management 4 x x Note 2 Ventilation System and III.D.1-3 Filter Criteria 4 x x Note 2 III.D.1-4 Radwaste Design Features Ib x Public Radiation Except for the sub-III.D.2 Protection Improvement Ib x item (s) below, this item is out-of-scope Liquid Pathways OPS Report No. 22A60, III.D.2-3 Dose Analysis 4 x x NUREG-0440 Worker Radiation In Plant Design Report III.D.3-1 Protection 4 Part x Section 11.6 and Chapter 12 Note 2 III.D.3-2 llealth Physic Improvements Ib x

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Note 2* need to III.D.3-3 In-Plant Radiation Monitoring 4 x x Partial: Ref. 1, p. B-28 obtain Draft 4 (NURFC-0660)

III.D.3-4 Control Room liabitability 4 x x Note 2 Radiation Worker Exposure III.D.3-5 Data Base la x IV NRC Practices & Procedures

• x NRC Policy, Organization V and Management

• x

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i NOTES

(*) Several subitems exist in various :ategories; however, no subitem is applicable to the M.L. application.

(1) Additional information describing this item is contained in Attachment 1. " Criteria for Utility Management and Technical Competence",

draft dated 2/25/80.

(2) Additional information describing this item is contained in the paper labelled Attachment 2.

(3) Item numbering within item II.K.1 corresponds to that used on p. II.K-2 of NUREG-0660.

(4) Item r.umbering within item III.A.2-2 corresponds to that used in Section Ilof NUREG-0654. Item descriptions are contained in Attachment 3, which is extracted from NUREG-0654.

REFERENCES (1) Offshore Power Systems Topical Report 36A93, " Offshore Power Systems Responses to Post-TMI NRC Requirements" December 1979.

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