ML20080L517

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Documents 830830 Telcon Re Clarification of Commitments to Reg Guides & QA Program as Applicable to Facility Steam Generator Replacement Program.Addl Discrepancies Discussed
ML20080L517
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 09/26/1983
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Harold Denton, John Miller
Office of Nuclear Reactor Regulation
References
NUDOCS 8309300348
Download: ML20080L517 (2)


Text

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l lMsconsin Bectnc men couraur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 Septembar 26, 1983 bir. 11.

R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY C0hDIISSION Washington, D. C.

20555 Attention:

Mr. J. R. hiiller, Chief Operating Reactors Branch 3 Gentlemen:

DOCKET NO. 50-266 1

STEAM GENERATOR REPLACEMENT POINT BEACH NUCLEAR PLANT, UNIT 1 This letter provides documentation of the telephone conversation between Messrs. Colburn and Spraul of the NRC staff and Messrs. Seizert, Stevens, and Keily of Wisconsin Electric Power Company (Licensee) on August 30, 1983.

The purpose of the telephone conversation was to clarify commitments to regula-tory guides and the Quality Assurance Program as applicable to the Unit 1 steam generator replacement program.

Section 4.2 of the NRC's Safety Evaluation Report does not reflect the commitments outlined in the Steam Generator Repair Report (Repair Report), Revision 1, dated March 1983 in which our letters dated October 27, 1982 and December 22, 1982 are incorporated.

The commitments to regulatory guides and the Quality Assurance Program applicable to the design, fabrication and installation phases of the replacement project are outlined in Sections 2.4.1, 2.1.4, and 3.6 of the Repair Report, respec-tively.

In contrast, Section 4.2 and Table 1 of the NRC's Safety Evaluation Report do not segregate commitments according to phases of the project and therefore could be misicading to the reader.

Additionally, two other discrepancies were noted in Section 4.2 of the Safety Evaluation Report:

1.

References to Appendix 11 of the Point Beach FSAR should be changed to Section 1.8 to reflect the 1982 update of that document.

(M AO M

O 0309300348 830926 PDR ADOCK 05000266 P

PDR

Mr.11. R. Denton September 26, 1983 2.

In accordance with our QA procedures, as outlined in Section 1.8 of the Point Beach FSAR, and as stated in Section 3.6 of the Repair Report, we will review and approve the Westinghouse Quality Assurance Program.

Review and approval of the quality assurance programs of the Westinghouse on-site contractors is not accomplished directly by Nisconsin Electric as stated on page 8 of the Safety Evaluation Report.

Should you have any questions regarding this information please contact us.

Very truly yours, Vice President - Nuclear Power C. W.

Fay Copy to NRC Resident Inspector

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