ML20127H314

Forwards Info Required for NRC Review of Inservice Insp & Testing Program & Requests for Relief from ASME Code Section XI Requirements

ML20127H314
Person / Time
Site:	Monticello
Issue date:	03/15/1978
From:	Mayer L NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20127H318	List: ML20127H314 ML20127H340
References
NUDOCS 9211180482
Download: ML20127H314 (2)

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NORTHERN STATES POWER COMPANY M I N N E A pe o u s

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March 15, 1978

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fl ps Director of Nuclear Reactor Regulation g

U S Nuclear Regulatory Commission i2 pu, u m Washington, DC 20555 ^

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MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR 22 Infomation Required for NRC Review of Inservice Inspection and Testing Program and Requests for Relief from ASME Code Section XI Requirements Attached you will find 40 copies of a report entitled, "ASME Code Section XI Inservice Inspection and Testing Program and Infomation Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements." This report is a revision of our inservice inspection and testing program descrip-tion and requests for relief submitted to Mr Victor Stello, Director, Division of Operating Reactors, USNRC, on December 14, 1977. The purpose of this revised report is to:

a. Include Quality Group boundary drawings to identify com-ponents subject to leakage, hydrostatic, and pressure ' .

tests. These drawings also serve to identify Quality Group C components requiring visual inspection,

b. Correct a number of errors in the December 14, 1977 report,

c. Submit a number of additional requests for relief for NRC Staff consideration.

The content of the report confoms to the recorraendations contained in Mr D L Ziemann's letter of November 24, 1976 and in Mr D R Davis's letter of January 16, 1978.

The program description will be periodically updated. Inservice inspection re-quirements will be updated at 40-month intervals to conform to the latest edition and addenda of Section XI of the ASME Code referenced in paragraph (b) of 10 CFR 50, Section 50.55a. Pump and valve testing requirements will be up-dated at 20-month intervals. All program updates will be supplied as revised O

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NOR1 r4ERN CTATED POWER. COMPANY.

. Jirector of Nuclear Reactor Regulation

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• March 15,1978 pages of this report. All pages are punched for use with a standard three-ring binder. An updated " Record of Revisions" page will accompany all report revisions.

License Amendment Requests were submitted on August 30, 1977 to revise the Monticello Technical Specifications to conform to 10 CFR 50, Section 50.55a(s).

These changes have not .yet .been issued by the Comnission. . We ask that these-changes be reviewed and issued without further delay. Current conflicts-between the Technical Specifications and 10 CFR 50 Section 50.55a(g) require-ments have renulted in needless ambiguity in the conduct of our. surveillance program-e L 0 Mayer,.PE Manager of Nuclear Support Services LQ4/DMM/deh cc: J G Keppler G Charnoff Attachment

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