B13783, Responds to Generic Ltr 89-19, Request for Action Related to Resolution of USI A-47

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Responds to Generic Ltr 89-19, Request for Action Related to Resolution of USI A-47
ML20070U181
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/01/1991
From: Mroczka E
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR B13783, GL-89-19, NUDOCS 9104080214
Download: ML20070U181 (2)


Text

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NDRTHEAST UTILITIES o.n.,.i on c.. . soiaen sire.i. e.,nn. Conn.cucui  !

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HARTFORD. CONNECTICUT 061410270 k C J [ C l(( E S C E (203) 665-5000 l

April 1, 1991 Docket No. 50-336 {

i lLL3161 Re: GL 89-10 ,

USI A-47 i U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 '

Gentlemen:

Millstone Nuclear. Power Station, Unit No. 2 Response to Generic Letter 89-19 Request for Action Related to Resolution i of Unresolved Safety Issue A-47 I l

in a letter dated September ?0, lh1,II) the NRC Staff " ire'Jed Generic Let-ter 89-19, " Request for Action Rela.sd to Resolution of unresolved Safety Issue A-47." Northeast Nuclear Energy Company (NNECO) and Connecticut Yankee Atomic Power- letter (GL) oa-W ch 27,1990,ganyfor(CYAPC0) responded Millstone Unit Nos.1, to 2, the andgent:,

3 ano, the Haddam Neck Hant, respectively. In our March 27, 1990 letter, NNECO committed to respond to items (4)(a) and (4)(b) fcr Millstone Unit No. 2 by March 31, 1991.

Items (4)(al- and (4)(b) of the GL concernea autci Wc steam generator overfill protection Or Combustion Engineering (CE) plants and changes to plant procedures: and technical. specifications for CE plants, aspectively. In a meeting with the Combustion Engineering Owners Group (CEOG) in Rockville, l

Maryland, on - November 20, 1990, the NRC Staff heard the CE0G's request to consider.the C.EOG analysir of overfill protection as a basis for not imple-

, menting the GL ' recommendations and - accept the -analysis as the justification for resolution of GL 89-19. The NRC Staff concluded at the time that it would (1) J. G. : Partlow letter to All 1.icensees v.- Operating Reactors, Applicants for' Operating Licenses, and Holders of Construction permits for Light Water Reactor : Nuclear Power Plants, " Request for Action Re ated to Resolution of Unresolved- Safety Issue A-47, ' Safety implication of

' Control; Systems in LWR Nuclear Power Plants' Pursuant to 10CFR50.54(f) -

Generic Letter 69-19," dated September 20, 1989.

(2) E. J. Mroczka letter -to U.S. Nuclear Reguiatory Commission, " Response to #0 Generir letter 89-19--Request for Action R.'ated to Resolution of Unresolved Safe +y issue A-47," dated Ma.ch 27, 1990.

9!, nf *ee , O M 6

r U.S. Nuclear Regulatory Commission B13783/Page 2 April 1, 1991 review and evaluate the information presented by the CEOG. The Staff further concluded that plant-specific responses to the GL regarding overfill protec-tion should be provided to the Staff 30 days af ter the issuance of the NRC evaluation of the CE0G analysis, in light of the foregoing, NNEC0 hnreby states the intention of submitting our response for Millstone Unit No. 2 to items (4)(a) and (%(b) of GL 89-19, 30 days af ter the NRC Staff evaluation of the CE0G analysis of overfill protection is issued. We respectfully request the Staff to inform NNEC0 directly upon completion of this esaluation.

Please contact us if you have any questions.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY E. J. roczka__. /. ...d W Senior Vice President cc: T. T. Martin, Region 1 Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 1