ML20096G678

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Forwards Rev 4 to Emergency Plan Implementing Procedure EPIP 1.7, Core Damage Estimation Procedure, in Response to Jr Miller 831103 Request.Submittal Fulfills Final Requirements in 831103 SER Re post-accident Sampling Sys
ML20096G678
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 09/04/1984
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Harold Denton, John Miller
Office of Nuclear Reactor Regulation
Shared Package
ML20096G681 List:
References
RTR-NUREG-0737, TASK-2.B.3, TASK-TM TAC-57058, TAC-57059, NUDOCS 8409110094
Download: ML20096G678 (1)


Text

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MSCORSin Electnc me coune 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 September 4, 1984 De' ton, Director Mr.

H. R.

n Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.

20555 Attention:

Mr.

J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKETS 50-266 AND 50-301 NUREG-0737, ITEM II.B.3 CORE DAMAGE ASSESSMENT METHODOLOGY POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In Mr.

J.

R. Miller's letter of November 3, 1983, which transmitted the Safety Evaluation for the Post-Accident Sampling System at our Point Beach. Nuclear Plant, we were requested to

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provide a plant-specific procedure which implements the Westinghouse Owners' Group (WOG) Post-Accident Core Damage Assessment Methodology.

Pleasel find-attached Emergency Plan Implementing Procedure (EPIP) 1.7, " Core Damage Estimation Procedure".

EPIP 1.7 will be used to implement the WOG methodology.

This fulfills the final require-ments for this item as. stated in the November 3 Safety Evaluation.

Should you have any questions concerning this matter, please do not hesitate to contact us.

Very truly yours, Vice-Presid nt-Nuclear Power C. -. W. Fay Attachment Copy to.NRC Resident Inspector 8409110094 840904 d(p PDR ADOCK 05000266 F

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