ML20236X414

Requests Closeout of Action Items II.K.3.31 & II.K.3.30 Since Util Analysis of Record Performed W/Same Methodology & plant-specific Analysis No Longer Required for Plants Utilizing Approved C-E Methodology

ML20236X414
Person / Time
Site:	Maine Yankee
Issue date:	12/07/1987
From:	Whittier G Maine Yankee
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
TASK-2.K.3.30, TASK-2.K.3.31, TASK-TM GDW-87-275, MN-87-134, NUDOCS 8712090178
Download: ML20236X414 (2)

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I RELIABLE ELECTRICITY FOR MAINE SINCE 1972 N_

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i MN-87-134 GDH-87-275:

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Director o.f Nuclear. Reactor Regulation:.

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' United States Nuclear Regulatory Commission e,

7Hashington, D. C. r20555, F

-Attention:-

' Actin' g; Project Director I-3 Division of Reactor Projects'I/II

References:

.(a)' License : No'.. DPR-36 (Docket No. 50-309.').

'(b) _ Letter MYAPCo'to USNRC' dated: September 22, 1977 (HMY-77-87),

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(c)' MYAPCo Final 1 Safety Analysis; Report,:Section 14.14.3.:

sR (d)

CEN-1_14-P..? Amendment.1-P, " Review of Small Break Transients

~inLCombustion Engineering-Nuclear Steam Supply Systems'._

' August:3, 1979.

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'y c(e)r Letter MYAPCotto USNRC dated August 31, 1979 (HMY-79-86).

G L(f) CEN-203-P,ERevision'l-NP-A (Supplements 1-NP-A and 2-NP-A),

~.and' Revision 1-Pi(Su'pplements 3-A and_4-A), " Response to JNRC Action' Plan Item II.K.3.30:- Justification of Small. '

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. Break LOCA= Methods", 3/82-11/86,

1' 1(g).- NRC' Safety' Evaluation _ Report, "TMI Action: Item II.K 3.30 Wk

.for Combustion Engineering Plants",'May 23. 1985,' and NRC Safety Evaluation Supplement. -"THI-Action ' Item II.K.3.30 -

-for: Combustion Engineering Plants"~ : transmitted via Letter from D. M. Crutchfield (NRC) to' J. K. Gasper l(CEOG),

M February 11, 1987.

Subject:

THI Action Items II.K.3.30 and II.K.3.31-

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Gentlemen:

The'small' break loss of coolant accident (SBLOCA) analysis of record for-the Maine Yankee plant'was provided to the NRC as Reference (b).

The CE.

1 methodology and modelling logic used.in generating' that analysis is detailed

,V in both that submittal and.the Maine Yankee'FSAR', Reference (c).

This same methodology has been. utilized'by the_CEOG to provide a generic analysis, 6CEN-114-Pc Reference (d), to the NRC as the basis'for resolution of TMI Action

. Item II;K.3.30.

Reference:

(e), places this report on the Maine Yankee-A Edocket. -.-Subsequent CE0G analysis, CEN-203-P, Reference (f), has demonstrated m

-the.. appropriateness of this methodology to conservatively predict SBLOCA response q

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".x LMaineYankee United States Nucl. ear Regulatory Commission Page Two Attention:: Acting Director MN-87-134 i'

-In Reference (g), the NRC has accepted the.CE0G methodology as appropriate to' resolve Action Item II.K.3.30.

Since the Maine. Yankee analysis of record was performed..with the same methodology, Maine Yankee now requests the

. closeout of Action' Item II.K.3.30, 4

The submittal of plant specific analysis, per Action. Item II.K.3.31, is n'o longer required for those plants. utilizing the CE methodology as approved

.through the resolution of Action Item II.K.3.30.

Therefore, in_accordance with the directions given in. Reference (g), Maine Yankee additionally requests the closeout of Action Item II.K.3.31.

We trust you will. find this course of action acceptable.

Please feel. free.

to-contact me if you wish to discuss this matter further.

Very truly yours, MAINE YANKEE

.hL9)V G. D. Whittier, Manager.

Nuclear Engineering and Licensing GOW/bjp cc: Mr. Hilliam T. Russell

'Mr. Pat Sears Mr.'Cornelius F. Holden

.I 9352L-RPJ