ML20079P523

Selected Operating Reactor Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept

ML20079P523
Person / Time
Site:	Quad Cities
Issue date:	02/07/1983
From:	Held J ENERGY, INC., LAWRENCE LIVERMORE NATIONAL LABORATORY
To:	Butcher E, Donohew J Office of Nuclear Reactor Regulation
Shared Package
ML20079P527	List: ML20079P523
References
CON-FIN-A-0250, CON-FIN-A-250, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM TAC-44400, TAC-44401, TF-328-0799A, TF-328-799A, NUDOCS 8303090357
Download: ML20079P523 (4)

Text

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Lawrence Uvermore National Laboratory M .

Selected Operating Reactor Issues Program II Reactor Coolant System Vents (NUREG-00737, Item II.B.1.)

NRC FIN A0250 - Project 9 FINAL TECHNICAL EVALUATION REPORT F0R QUAD CITIES 1 AND 2 Docket Numbers 50-254 and 50-265

. NRC TAC Numbers 44400 and 44401 Prepared by J. T. Held of Energy Incorporated - Seattle (Subcontract 4324401) for Lawr'ence Livermore National Laboratory under contract to the NRC Office of Nuclear Reactor Regulation, Division of Licensing.

DL Cognizant Manager - Ed Butcher DL Project Manager - Jack Dononew NOTICE

• • This report was prepared as an account of work sponsored by the United States Governmen Neither the United States not the United States Department of Energy,nor any of their employees, nor any of their contractors, subcontranors, or their employces, makes any warranty, express or

/ implied, or assumes any legal liabihty cr respon-sibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately-owned rights."

XA Copy Has Been Sent to PDRx TF-328/0799a ggh A February 7,1983 (P

mmmm-- . __,___.,,_

. Dock 2t Numbers 50-254 and 50-265

1. NRC TAC Numbnrs 44400 cnd 44401 TECHNICAL EVALUATION REPORT ON REACTOR COOLANT SYSTEM VENTS FOR OUAD CITIES I AND 2 INTRODUCTION The requirements for reactor coolant system high point vents are.strated in paragraph (cX3Xiii) of 10 CFR 50.44, " Standards for Combustible Gas Control System in Light Water Cooled Power Reactors," and are further described in Standard Review Plan (SRP)

Section 5.4.12, " Reactor Coolant System High : Point Vents," and Item II.B.1 of -

NUREG-0737," Clarification of TMI Action Plan Requirements." In response to these and previous requirements, Commonwealth Edison has submitted information.in References 1 through 4 in support of the vent system at Units 1 and 2 of the Ouad Cities Station.

EVALUATION The function of the reactor coolant system (RCS) vent system is to vent noncondensible -

gases from the high points of the RCS to assure that core cooling during natural circulation will not be inhibited. The Boiling Water Reactor (BWR) Owners' Group has submitted documentation (References 5 through 8) on how the RCS venting requirements i

are met in General Electric (GE) BWRs. The BWR Owners' Group position has been

! endorsed by the licensee.

l In accordance with the BWR Owners' Croup position, the primary means of venting noncondensible gases from the reactor pressure vessel at Quad Cities I and 2 are four .

safety-grade Electromatic relief valves and one safety-grade Target Rock safety / relief valve that are part of the automatic depressurization system (ADS) and which alone provide adequate. venting.

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o We have reviewed design'information on the valves associated with the above system ,

that will serve as RCS vents and confirmed that they are operable from the main control room. We have also determined that the valves are provided with emergency power and f

j that a degree of redundancy in the RCS vent system is provided by powering differe'nt vent paths from different emergency buses. Positive valve position indication in the main control room is provided by two acoustic flow monitors for each relief and safety / relief valve. Additional RCS venting occurs via the high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) system turbine exhausts. Also, based on the similarity of the Quad Cities design to other General Electric BTRs, we find that no protection system that is necessary to maintain adequate core cooling requires remote venting since none are susceptible to the buildup of a large amount of noncondensible gas that could cause a loss of function of these systems.

CONCLUSION -

We conclude, based on the applicability of the BWR Owners' Group position to Quad Cities 1 and 2 and our specific review of the Ouad Cities I and 2 design, that the existing systems at Ouad Cities I and 2 are sufficient to effectively vent noncondensible gase-from the RCS and meet the requirements of NUREG-0737 Item II.B.1 and paragraph (cK3Xiii) of 10 CFR 50.44 We therefore r.ecommend that the Ouad Cities 1 and 2 RCS venting capability be found acceptable by NRC. It should be noted, however, that the following items were excluded from the scope of our review: seismic and environmental qualification, operating guidelines and procedures, and required modifications to the plant technical specifications and in-service inspection program for use of existing systems as RCS vents. ..

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REFERENCES -

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1. Letter, C. Reed (Commonwealth Edison) to D.G. Eisenhut (NRC), " Commitments to Meet Near Term Requirements of the Lessons Learned and Emergency Preparedness Task Force," dated October 18,1979.

2. -Letter, R.F. Janecek (Commonwealth Edison) to Director o'f Nuclear Reactor Regulation (NRC), " Proposed Amendments to Technical Specifications, Appendix A to Operating Licenses DPR-19,25,29, and 30," dated September 18,1980.

3. Letter, L.O. DelGeorge (Commonwealth Edison) to D.G. Eisenhut (NRC), " Responses to NUREG-0737 Items Requiring July 1,1981 Submittal," dated July 1,1981.

4. Letter, E.D. Swartz (Commonwealth Edison) to D.G. Eisenhut (NRC), "NUREG 0737 Item II.B.1, Additional Information," dated April 20,1982.

5. Letter, T.D. Keenan (BWR Owners' Group) to D.G. Eisenhut (NRC), "BWR Owners' Group Positions on NUREG-0578," dated October 17,1979. -

6. Letter, D.B. Waters (BWR Owners' Group) to NRC (Attn: D.G. Eisenhut), -

" Preliminary Clarification of TMI Action Plan Requirements - BWR Owners' Group Comments," dated October 8,1980.

7. General Electric Report -N EDO-24708 A, Revision 1, " Additional Information Required for NRC Staff Generic Report on Boiling Water Reactors," dated December 1980.

L 8. Letter, D.B. Waters (BWR Owners' Group) to NRC (Attn: D.G. Eisenhut),

"NUREG-0660/0737 Requirement II.B.1: Reactor Coolant System Vents," dated April 24,1981.

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