ML20236X479

From kanterella
Jump to navigation Jump to search

Requests Reevaluation of ATWS Moderator Temp Coefficient Due to Proposed Westinghouse Owners Group Response Not Addressing NRC Concern for Unit Cycle 2 Reload
ML20236X479
Person / Time
Site: Millstone 
Issue date: 12/01/1987
From: Ferguson R
Office of Nuclear Reactor Regulation
To: Mroczka E
NORTHEAST NUCLEAR ENERGY CO.
References
TAC-66023, NUDOCS 8712090233
Download: ML20236X479 (3)


Text

_ _ _ _ _ _

December 1,1987 Pocket lio. 50-423

' DISTRIBUTION Docket #iTek RFerguson "NRCT f.ocal PDRs OGC-Beth Mr. Edward J. Mroczka PDI-4 Files EJordan Senior Vice Fresident SVarga JPartlow Nuclear Er;gineering and Operations BBoger

!!Hcdges Northeast !?uclear Energy Company SNorris ACRS(10) l Post Office Box 270 Hartford, Connecticut 06141-C270 i

Dear Mr. Mroczka:

j

SUBJECT:

itILLSTONE NUCLEAR STATION, UNIT NO. 3 CYCLE 2 RELOAD (TAC NO. 66023)

References:

1.

Letter from Ashck C. Thadani (NRC) to Roger Newton (Chairnian, UOG), dated June 12, 1987. This letter was also sent to the CE and B&U Cwners Groups. The Subject of the letter is "ATWS Mcderator Ter.!perature Coefficient".

1 I

2.

Letter from Roger Newton (Chairman, WCG) to Ashok C. Thadani (NRC), dated November 23, 1987.

3.

" Amendments to 10 CFR 50 Related to Anticipated Transient Withcut Scram (ATWS) Events," SECY-83-293, dated July 19, 1963.

l Your letter dated September 9, 1987, requested a charge to Technical Specification 3.1.1.3 to permit a n.cre positive roderator temperature coefficient (l'TC). The proposed least ncgative MTC would bc +5 pcm/*F between-zero and 70% p(Note that a pcm is equal to 10 4[F at 70% power to O pcm/*F at ower and ran.p down from +5 pcm/

100% power.

units of teactivity.)

A concern has been expressed by the staff in a 1Etter (Ref.1) to the three PWR Owners Grcups on this apparent trend to note positive MTCs than those that were used by the FUR vendors in perforr.ing anticipated transients withcut scram (ATWS) eralyses that preceded and formed part of the' underlying basis for the ATUS Rule, (10 CFR 50.62).

In reference 1 the staff specifically asked for a reevaluation of the MTC. The Westinghouse Cwners Group (V0G) indicated, by letter (Ref. 2) dated November 23, 1987, that its response, would be based on its interpretation of SECY-83-293 (Ref. 3).

Cased upon preliminary discussions with Westinghouse, the staff Lelieves the proposed UCG response will nct address the staff's concern fcr Millstone 3 cycle 2 reload because the WOG response will rct include a reevaluation of the MTC.

8712090233 871201 PDR ADOCM 05000423 P

PDR l

Mr. E. J. Mroczka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 3 cc:

Gerald Garfield, Esq.

Ms. Jane Spector Day, Berry & Howard Federal Energy Regulatory Comission City Place 825 H. Capitol Street, NE Hartford, Connecticut 06103-3499 Room 8608C Washington, D.C.

20426 Mr. Maurice R. Scully, Executive Director Mr. Kevin McCarthy, Director Connecticut Municipal Electric Radiation Control Unit Energy Cooperative Departnent of Environmental Protection 268 Thomas Road State Office Building Groton, Connecticut 06340 Hartford, Connecticut 06115 Robert W. Bishop, Esq.

Burlington Electric Department Corporate Secretary c/o Robert E. Fletcher, Esq.

Northeast Utilities 271 South Union Street Post Office Box 270 Burlington, Vennont 05402 Hartford, Connecticut 06141 Mr. William J. Raymond Senior Resident Inspector Office U. S. Nuclear Regulatory Commission Millstone III P. O. Box 811 Niantic, Connecticut 06357-08 Mr. Michael L. Jones, Manager Project Management Department

. Massachusetts Municipal Wholesale Electric Company Post Office Box 426 Ludlow, Massachusetts 01056 Regional Administrator U. S. NRC, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Karl Abraham Public Affairs Office, Region I U. S. Nuclear Regulatory Comission, King of Prussia, Pennsylvania 19406 l

l l[

J

Provide a corrperison of the initial FITC's used in the ATWS analyses applicable to liillstcne 3 with the coniparable ffTC values estinated for cycle 2.

Evaluate the effects of the proposed change to the IITC for cycle 2 on the ATl!S ar.alysis applicable to fii11 stone 3.. Provide a cornparison of the fiTC which was expected

~for cycle 1 with fiTC values calculated using actual cycle 1 data.

l!e require your tirely response to coniplete our evaluaticn of the liillstone 3 cycle 2 reload.

The reporting End/or recordkeeping requirert.ents coritained in this letter affect fa.cr than ten resperdents; therefore, Ct"B clearance is not required under-P.L.96-511.

Sincerely, M $reitB W Robert L. Ferguson, Project fianager Project Directorate I-4 Division of Reactor ProjectsI/II Office of Nuc1 car Reactor Reguletien cC:

See next,page J

l

  • Previcusly concurred PDL-4 Sk PDI-4 SRXB ff,M, Pferguson:bd
  • JStolz
  • WHodges IS,M /l /87 111' l /fs7 11/30/87 11/30/87 L_