ML20065R245

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Operating Reactors - TMI Lessons Learned,NUREG-0737 Response Evaluations (Program Ii);Project 1,RCS Vents for Brunswick 1 & 2, Final Technical Evaluation Rept
ML20065R245
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 07/15/1982
From:
LAWRENCE LIVERMORE NATIONAL LABORATORY
To: Barnhart B, Butcher E
Office of Nuclear Reactor Regulation
Shared Package
ML20065R244 List:
References
CON-FIN-A-0246-2, CON-FIN-A-246-2, RTR-NUREG-0737, RTR-NUREG-737 TAC-44358, TAC-44359, NUDOCS 8210290113
Download: ML20065R245 (4)


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Operating React 0rs - TMI Lessons Learned NL' REG-9737 Response Evaluations (?ragram II) '

Project 1 - Reactor Coolant System Ve.nts (Item II.B.1) tiRC FIN A3246-2 .

FINAL TECH'fICAL EVALUATION REPORT FOR BRUNSWICK 1 and 2 Prepared by Energy Incorporated - Seattle for Lawrence Livermore National Laboratory under contract to the NRC Office of NJelear Reactor Regulation, Division of, Licensing.

DL Cognizant Manager - Ed Butcher DL Project l'.5 nager - Beverly Earnhart NOTICE "This report was pic72::d ts an account of work .I.

spor.sored :he Cni:ed 5:stes Governrnent. I Neith:r the 'r.ited 5:stes nei che Uni:ed 5: :es l .

Depar:rne .t of Energy n:,:any of their empicyets. i r ci any cf their centra:: rs, subeentra:: ors, er their ernpley::!. rnakes a .y w r.tranty, exp;ess or imp!isd. or asr.m:s any ::pt liabili:v or resp n-sihility for the accu: cy. cornpleteness er I

us:fu!ncss of r.y informa: ion, appsratus, produ::

or pro:ess cis:.csed. c: r:prcstr.:s that its use sculd nct infri se prisa::!y-cwned rights."  ;

Jaly 15,1982 8210290113 821001 PDR ADOCK 05000324 -

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_o D::cket Numbers 50-325 and 50-324 NRC 1 AC Number 4435S cnd 4435o

' TECHNICAL EVALUATION REPORT ON REACTOR COOLANT SYSTEM VENTS

. FOR BRUNSWICK l AND 2 INTRODUCTION The requirements for Reactor Coolant System High Point Vents are stated in paragraph (C)(3)(iii) of 10 CFR 50.44, " Standards for Combustible Cos Contro'I System in Light Water Cooled Power Reactors," cnd cre 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, "Clerification of TMil Action Plan Requirements." In response to these and previous requirements, the Carolina Power and Light Company hos submitted information in References I through 4 in support of the vent system on Brunswick Steam Electric

.' Plant Units I and 2. .

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

In cecordance with the BWR Owners' Group position, the primary meo.'s ch venting noncondensible gcses from the reccior pressure vessel at Brunswick I and 2 ore seven power-operated, sciety-grede automctic depressurization system (ADS) safety / relief valves which alone provide adequcte venting.

We bove reviewed. design infennotion on the vc!ves cssocicted with the chove system thet will serve cs RCS vents cnd confirmed thct they cre opercble frem the m:in control room. We have c'so determined that the vcives cre provided with emergency pc'wer cnd a

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that c degree of redundancy in the RCS vent system is providsd by powering different vent ' pcths from different emergency buses. NRC- hast previc0 sly: ve.-ified that the safetv/ relief volves cre provided with pesitive position indicction in th mein contrc,!

roem (Reference 9). %dditional RCS venting occurs at the high' pressure coolant injection (H?Cl) cnd recctor core isciation cooling (RCIC) system turbine exhcests. The licensee hcs clso verified that no protection system that is necesscry. to maintain cdequcte core cooling requires remote venting since none are susceptible to the buildup of e Ic.ge cmount of noncendensible ges that could cause o loss of function of these systems.

i CONCLUSION We conclude, based , on the cpplicobility of the BWR Owners' Group position to Brunswick I cnd 2 cnd pur specific review of the Brunswick I and 2 design, that the existing systems at Brunswick I cnd 2 cre sufficient to effectively vent noncondensible gases from the RCS cnd meet the requirements of NUREG-0737 Item 11.B.1 cnd peregrcph (e)(3)(iii) of 10 CFR 50.44. We therefore recommend that the Brunswick I cnd 2 RCS venting ecpobility be found ceceptable by NRC with the following confirmatory items. NRC must review cnd cpprove the existing operating procedures cad technical specifications for use of the existing systems as RCS vents.

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NEFERENCES

1. Letter, E.E. Utley (Ccrolino Power and Light Company) to D.G. Eisenhut (NRC),

" Followup to Review Regarding the Three Mile Isicnd Unit 2 Accident," dated October 18,1979.

2. Letter, E.E. Utley (Carolino Power and Light Company) to H.R. Denten (NRC),

" Lessons Learned Short Term Requirements," dated December 31,1979.

3'. Letter, E.E. Utley (Carolino Power and Light Company) to D.G. Eisenhut (NRC),

"NUREG-0737: July 1,1981 Items," dated June 30,1981. .

4. Letter, S.R. Zirrimerman (Corolino Power and Light Company) to D.B. Vossallo (NRC), "NUREG-0737, item ll.B.I, Reacter Coolant System High Point Vents," dated June 25,1982.
5. Letter, T.D. Keenen (BWR Owners' Groep) 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),

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

7. General Electric Report NEDQ-24708A, Revision I, " Additional . information Required for NRC Stcff Generic Report on Boiling Water Reactors," dated December 1980.
8. Letter, D.B. Wcters (BWR Owr.ers' Group) to NRC (Attn: D.C. Eisenhut),

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

9. NUREG-0737, "Clarificction of TM! Action Pica Requirements," liem li.D.3, " Direct Indication of Relief- cr.d Scfety-Vc've Pcsition," dated November 1980.

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