ML20154G064

Confirms That All Components Required to Trip Reactor Identified as safety-related on Relevant Documents,Per Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events

ML20154G064
Person / Time
Site:	Point Beach
Issue date:	05/11/1988
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Wagner D Office of Nuclear Reactor Regulation
References
CON-NRC-88-44 GL-83-28, VPNPD-88-263, NUDOCS 8805240204
Download: ML20154G064 (2)

Text

., . .

l '

Wisconsin Electnc eaara couv>e 231 W.M.CHIGAN P.O. BOX 2046, MILWAUKEE W153201 (414)221 2345 VPNPD-88-263 v NRC-88-44 May 11, 1988 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Washington, D.C. 20555 Attention: Mr. David Wagner, Project Manager Project Directorate III-3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 GENERIC LETTER 83-28, ITEM 2.1, PART 1 POINT BEACH NUCLEAR PLANT On April 21, 1988, Mr. Wagner contacted Wisconsin Electric requesting that we confirm the actions we have taken in response to Item 2.1, Part 1, "Equipment Classif. cation," of Generic Letter 83-28, "Required Actions Based on jeneric Implications of Salem ATWS Events." Specifically Mr. Wagner requested that we confirm that all components whose functioning is required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities including maintenance, work orders and parts replacement.

Wisconsin Electric initially responded to Generic Letter 83-28 in [

a letter dated November 7, 1983. In that letter we stated that an initial review had confirmed that those safety-related components necessary to assure a reactor trip are included within the quality assurance scope at Point Beach Nuclear Plant. We also committed to complete by February 29, 1984, a detailed intensive review of the drawings used to categorize the quality assurance scope. That review was to include all aspects of those safety-related systems and components necessary to provide a reactor trip function. We subsequently confirmed in our letter dated April 11, 1986, that this review had been completed. Accordingly, we can confirm that all components whose function is required to trip the reactor are identified as safety-related on relevant documents which control safety related activities.

We wish to note that on October 19-29, 1987, the NRC conducted an inspection and audit of activities and commitments made to satisfy the requirements of Generic Letter 83-28. Inspection Reports

~

8805240204 880511 l fDR ADOCK 05000266 DCD i

e Document Control Desk May 11, 1988 Page 2 DPR-24/87-021 dnd DPR-27/87-022 dated November 9, 1987, reported the results of that inspection. Equipment classification was included in this inspection. The report documents the inspector's review of QA scope lists, procedures controlling maintenance, modifications, procurement and inspection and testing, and modifi-cation reports for several selected reactor trip related compo-nents. The report concludes that these documents were clearly identified as safety-related. We therefore concur with your suggestion that Generic Letter 83-28, Item 2.1, Part 1, has been appropriately satisfied and may be closed.

Very tr'ily yours,

$$Uf /

/

C. W. Fay Vice President Nuclear Power Copies to NRC Regional Administrator, Region III NRC Resident Inspector i

+