ML20092M512

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Submits NRC Requested Response from 921021-1025 Insp Per Generic Ltr 89-10 That Testing of Correct Switch Settings Be Implemented.Revision to Engineering Procedure ENP-17 Forseen by 920331.Appropriate Design Guide to Be Modified by 920630
ML20092M512
Person / Time
Site: Brunswick  
Issue date: 02/24/1992
From: Spencer J
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-10, NUDOCS 9202270337
Download: ML20092M512 (2)


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CP&L Carolina Power & Ught Company gmgp-m -

Brunswick Nuclear Project P. O. Box 10429 Southport, N.C.

28461 0429 FEB 2 4 1333 FILE:

B09 135100 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 & 2 DOCKET NO. 50 325 & 50 324 LICENSE NO, DPR-71 & DPR 62 Gentlemen:

During the week of October 21 25, 1991, inspection 91-31 of the Brunswick Generic Letter (G.L.) 89-10 program was conducted. In the ensuing Anspection report, a written response was requested regarding a concern that neither the Brunswick program nor its implementing procedures provided guidance for performance of the post-maintenance and post-modification testing needed to ensure that correct switch settings are maintained in accordance with the generic letter.

As noted in the inspection report, a Corporate level post-maintenance testing guidance matrix for valver that have received their G.L. 89-10 baseline testing has been draf ted but has not yet been formally implemented at the Brunswick facility.

Brunswick intends to incorporate the PMTR matrix into Engineering

-Procedure ENP-17, " Pump and Valve Inservice Testing." This procedure revision should be complete by March 31, 1992.

The inspectors also concluded that the " Nuclear Plant Modifications Program" (NPMP) does not provide procedural guidance for performance of post-modification testing of MOV's to ensure correct switch settings are maintained in accordance with G.L. 89-10.

CP&L will incorporate this guidance into Nuclear Engineering l

De r_&'nent (NED) design guido DG-VIII.41, " Design Guide for the Preparation of Plant Modification Acceptance Test (A.T.)."

This procedure will be revised by i

June 30,1992, which is well in advance of the next scheduled Brunswick Nuclear l

Plant refueling outage.

The enhancement of this procedure should provide the guidance necessary to alleviate the concerns raised in the inspection repcrt.

Very truly yours,

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.ral Manager

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