ML20238C114: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| page count = 2
| project = TAC:65977
| stage = Other
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}}



Latest revision as of 11:13, 19 March 2021

Requests Authorization to Use 1983 Edition of ASME Section XI, Rules for Inservice Insp of Nuclear Power Plant Components, for ASME Section XI Repair & Replacement Program
ML20238C114
Person / Time
Site: Rancho Seco
Issue date: 08/26/1987
From: Andognini G
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Miraglia F
Office of Nuclear Reactor Regulation
References
GCA-87-475, TAC-65977, NUDOCS 8709090661
Download: ML20238C114 (2)


Text

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. SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT D P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA CCA 87-475 August 26, 1987 U. S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr.

Associate Director for Projects Philips Bldg.

l 7920 Norfolk Avenue Bethesda, MD 20014 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT #1 l

ASME SECTION XI REPAIR AND REPLACEMENT PROGRAM

Dear Mr. Miraglia:

l In accordance with the requirements of 10 CFR 50.55a (g)(4)(iv), the District is requesting Commission approval to use the 1983 Edition of ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components through Summer 1983 Addenda and all related requirements for the Rancho Seco ASME Section XI Repair and Replacement Program. The 1983 Edition through Summer 1983 Addenda of ASME Section XI will be used subject to the limitations and modifications of 10 CFR 50.55a (b)(2) for repair and replacement of pressure retaining components and their supports classified as ASME Code Class 1, Class 2 and Class 3 and for core support structures.

The current edition of ASME Section XI in effect at Rancho Seco is the 1974 l

Edition through Summer 1975 Addenda. The later editions of the Code are refinements of-earlier editions based on experience, development of more sophisticated analysis or techniques and tests and are aimed at providing more precise requirements. The 1983 Edition through Summer 1983 Addenda approved l for use by 10 CFR 50.55a (b) is also more comprehensive in the area of repair and replacement.

On this basis, pursuant to the requirements of 10 CFR 50.55a (g)(4)(iv), the District requests that the Commission approve the use of the 1983 Edition i

through Summer of 1983 Addenda of ASME Section XI for the Rancho Seco ASME Section XI Repair and Replacement Program.

Enclosed is a check for $150.00 pursuant to 10 CFR 170.21, for the application fee for NRC Review and Approval.

8709090661 070826 PDR y WW G ADOCK 05000312' PDR F

RANCHO SECO NUCLEAR GENERATING STATION U 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935 W'

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GCA 87-475 Frank J. Miraglia, Jr. August 26, 1987 If there are any questions concerning this submittal, please contact Mr. Karl Meyer of nty staff at extension 4721.

Sincerely, . -

Car do Chief Executive Officer, Nuclear cc: G. Kalman, NRC, Bethesda A. D'Angelo, NRC, Rancho Seco J.B. Martin, NRC, Region V

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