ML051010056

NRC Audit Question 51

ML051010056
Person / Time
Site:	Hatch
Issue date:	07/10/2003
From:	Schin B - No Known Affiliation
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2004-0277
Download: ML051010056 (2)

Text

Control Number:

ARurdft Question Processing Form (For Staf use only)

AQ-51 Question Initiated By: Schin, Bob Date: 7/10/2003 Regulatory Basis for Qucstion:

Question:

If al,,pven SRV's opened simultaneously while reactor power is at 100%, would all RCS pressure variables be maintained within those predictable for a loss of normal AC Power?

Response

As previously documented in the response to AQ-6, the plant is designed to withstand the containment loads that result from operation all 1 SRVs. As part of extended power uprate, additional containment loads analysis was performed that demonstrated that adequate design margins continued to exist for operation at current rated power, 2763 MWt. A copy of the GE Proprietary report documenting the containment

-evaluation (GE-NE-AI13-00402-04-RI) is attached for review (but Abe returned in view of its proprietary nature). ,

(Fc Staff use on:y) -

I Re ~ r ul 'o Reviewed by Luker, Ira Safmt

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NRC si e§ir6oeieedom of Information ___\

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FOJA- >74 oV-S7-

Control Number.

Andit Question Processing Form (For Stanf use only)

AQ-51 Cxy' It should be noted however, that SNC believes that this question falls into the category of associated circuits, inspection of which was temporarily suspended as of 11/29/2000 (ML0037733142). This inspection scope reduction is referenced in NRC Inspection Procedure 71111.05. This suspension recognizes the ongoing industry and NRC activities to complete NEI (NEI 00-01) and NRC guidance to address issues associated with associated circuits analysis. Once these activities are completed, currently scheduled for this fall, SNC wxill review the applicable guidance and detennine if any additional actions are appropriate. Given that the cu5rrengjkg.nisin2g basis of Plant Hatch does-not incrhie hot shorts in associated Y L

circuits, and given the NRC guidance provided by NRC Inspection Procedure 71111.05, SNC believes this topic most appropriately could be deferred pending further resolution of the NRC's generic actions to clarify the regulatory basis of multiple hot shorts.

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towi£.4 '7z-(For Staff use onty)

Response by: Tully, Cin4_ Reviewed by-Luker, Ira Staff init:

NRC Status: In Progress _ ____- _