ML20072K841

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

ML20072K841
Person / Time
Site:	FitzPatrick
Issue date:	03/02/1983
From:	Held J ENERGY, INC., LAWRENCE LIVERMORE NATIONAL LABORATORY
To:	Alberthal G NRC
Shared Package
ML20072K846	List: ML20072K841
References
CON-FIN-A-0250, CON-FIN-A-250, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM B14-TER-B-7, TAC-44373, NUDOCS 8303310020
Download: ML20072K841 (4)

Text

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LAWRENCE LiVERMORE LABORATORY

\g-ha 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 FOR JAMfS A. FITZPATRICK Docket Number 50-333 NRC TAC Number 44373 Prepared by J. T. Held of Energy Incorporated - 3eattle (Subcontract '

4324401) for Lawrence Livermore National Laboratory under contract to the NfC Office of Nuclear Reactor Regulation, Division of Licensing. -

l l NRC Lead Engineer - Gus Alberthal i

NOTICE "This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Departnient o'f Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legai liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, i

product or process disclosed, or represents that its use would not infringe privately-owned right's."

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March 2, 1983

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Docket Numbar 50-333 - -

NRC TAC Numbcr 44373 TECHNICAL EVALUATION REL90RT ON REACTOR COOLANT SYSTEM VENTS - -

FOR JAMES A. FITZPATRICK INTRODUCTION The requirements' for reactor coolont system high point vents' are stated in paragraph (cX3Xiii) of 10 CFR S0.44, " 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.I of NUREG-0737," Clarification of TMl Action Plan ReqM ments, in response to these and previous requirements, the Power Authority of the State of New York has submitted information in References I and 2 in support of the vent system at the James A.

Fitzpatrick Nuclear Power Plant. -

EVALUATION The function of the reactor coolont 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 irhibited. The Boiling Water Reoctor (BWR) Owners' Group hos submitted documentation (References 3 through 6)'on how the RCS venting requirements are met in General Electric (GE) BWRs. The BWR Owners' Group position has been endorsed by the licensee.

In occordance with the BWR Owners' Group position, the primary means of venting noncondensible gases from the reactor pressure vessel at James A. Fitzpatrick are six power-operated, safety-grade automatic depressurization system (ADS) safety / relief valves which alone provide adequate venting.

We have reviewed design information on the volves associated with thiabove' system that will serve os RCS vents and confirmed that they are operable from the main contro!

room. We have also determined that the valves are provided with emergency power and -

that a degree of redundancy in the RCS vent ' system is provided by powering different bl4/TER-B-7 Enclosure

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vent ocths from different emergency buses. NRC has previously verified that the safety / relief valves are provided with positive position indication in the main control room (Reference 7). Addit'lonel RCS venting occurs at the high pressure coolont injection (HPCI) and reactor core isolation cooling (RCIC) system turbine exhousts. - -

'Ehe licensee has further identified the need to vent the residual heat removal (RHR) heat exchangers using existing RHR vent valves. The RHR vent volves are used to vent noncondensible gases from the RHR heat exchangers to the suppression pool whenever the plarit is taken to cold shutdown. The two safety-related motor-operated valves on eoch heat exchanger we aranged in series, are provided wilh emergency power, are l

operable from the control room, and are provided with positive position indication via stem-mounted switches. We therefore find the existing RHR system venting provisions acceptoble.

The licensee has verified that no other protection systems that are necessary to maintain adequate core cooling require remote venting since none are susceptible to the buildup of l o (c ge amount of noncondensible gas that could cause a loss of function of these systems.

CONCLUSION We conclude, based on the opplicobility of the BWR Owners' Group position to James A.

Fitzpatrick and our specific review of the James A. Fitzpatrick design, that the existing systems at James A. Fitzpatrick are sufficient to effectively vent noncondensible gases from the RCS and the RHR system and meet the requirements of NUREG-0737 Item 11.B.1 and paragraph (cX3Xiii) of 10 CFR 50.44. We therefore recommend that the James A. Fitzpatrick RCS and RHR system venting capability be found acceptcble by NRC. It i

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 recuired modifications to the plant technical specifications and in-service inspection program for use of existing systems as RCS and RHR system vents.

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REFERENCES l

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1. Letter, P.J. Early (Power Authority of the State of 'New York) to D.G Eisenhut .

(NRC), " James A. Fitzpatrick Nuclear Power Plant, Docket No. 50-333, Response to

, NRC Requirements Based on Studies of TMI," dated October 22,1979.

2. Letter, J.P. Boyne (Power Authority of the State of New York) to D.B. Vassallo (NRC), " James A Fitzpatrick Nuclear Power Plant, Docket No. 50-333, Reactor Coolant System Vents,,NUREG-0737 Item II.B.I," dated March 19, 1982.

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

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

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

S. General Electric Report NEDO-74708A, Revision I, " Additional Information Required for NRC Staff Generic Report on Boiling Water Reactors," dated December 1980.

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

"NUREG-0660/0737 Requirement II.B.1: Reactor Coolant System Vents," dated April 24,1081.

7. NUREG-0737, " Clarification of TMI Action Plan Requirements," item II.D.3, " Direct Indication of Relief- and Safety-Valve Position," dated November 1980.

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