ML20210P182

From kanterella
Jump to navigation Jump to search
Forwards Addl Analysis That Demonstrates That VSW-3 Was Operable in Uninsulated Condition for Licensing Basis Accident Condition,In Response to NRC Request
ML20210P182
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 08/20/1997
From: Rang J
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20210P186 List:
References
NUDOCS 9708260466
Download: ML20210P182 (2)


Text

-

4 ConsumersEnergy A CAIS Ene'gy Conr*"Y

&$d Mt Mur TM Keanen 9, Peeners 10269l&3I hkvth Plant GeneralManaqet Da%t. M 49??O August 20, 1997 f

Nuclear Regulatory Commission Document Control Desk

-Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - REPLY TO A REQUEST FOR ADDITIONAL INFORNATION REGARDING RERATING OF PORTIONS OF THE POST-INCIDENT SYSTEM.

In support of the March 1997, Post Incident System (PIS) pressure rerate, conservative analyses were performed to determine the response of VSW-3, a cast iron body isolation valve between the PIS and the Service Water System (SWS), to a liaiting 0.63 ft* steam line break. With insulation, the valve temperature rise at the time of Containment Spray System (CSS) initiation was calculated to be 3*F. Without insulation, the valve temperature rise at the time of CSS initiation was calculated to be 39'F. During the review of this evaluation, the NRC Staff identified a concern regarding the operability of this valve, and requested that Consumers Energy Company provide the following information relative to VSW-3:

1. Provide an addltional analysis or other justification that demonstrated that the valve was operable in the uninsulated condition for the licensing-basis accident condition.
2. If applicable, provide the time frame in which the valve was determined to be inoperable.

Attached to this letter is an additional analysis that demonstrates that VSW-3

-was operable in.the uninsulated condition for the licensing-basis accident condition.

Respectfully,

%ttJk

. ames S Rang h

I A ting Plant Ma e

CC: Administrator, Region-III, USNRC NRC Resident Inspector - Big Rock Point lllllll llgl(llll ATTACHMENT

,,m y 4 n 9708260466 970820 PDR ADOCK 0500G155 P

PDR,.

l ATTACMDtf CONSUMERS ENERGY COMPANY BIG ROCK P0 INT PLANT DOCKET 50-155 D0CKET 50-155 - LICENSE DPR BIG ROCK POINT PLAKI

-REPLY TO A REQUEST FOR ADDITIONAL INFORMATION REGARDING RERATING 0F P0RTIONS OF THE POST-IRCIDENT SYSTDI..

ENGINEERING ANALYSIS WORKSHEET EA-AIR-BRP-97-027 12 PAGES

- _ _ _ _ _ _ _ _ - _ - _ - _ _ - _ _ _ _ _ _ _ _ - _ _ _