ML20070V123

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Discusses ASME Section XI Repair & Replacement Program, Repairs & Replacements Program Currently Under 10CFR50, App B QA Program.Plant Not Covered Under 1986 Section XI Code,Articles Iwx 4000 & 7000
ML20070V123
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/26/1991
From: Zach J
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-91-034, CON-NRC-91-34 DIRNP-91-035, DIRNP-91-35, NUDOCS 9104100322
Download: ML20070V123 (2)


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Wisconsin Electnc POWER COMPANY 231 W Mictuocn PO; Box 2046. MAome WI 53201 (414) 221-7345 DIRNP-91 035 NRC-91-034 March 26, 1991 Document Control Desk U.

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Nuclear Regulatory Commission Mail Station P1-137 Washington, DC 20S55 Gentleman:

DOCKETS 50-266 AND 50-301 ASME SECTION XI REPAIR AND REPLACEMENT PROGRAM POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 On December 20, 1990, Wisconsin Electric submitted its Inservice Inspection (ISI) Plan for the third-10-year interval for our Point Beach Nuclear Plant Units 1 and 2.

The third interval began on December 18, 1990, and in accordance with the requirements of 10 CFR 50.5Sa, the-ISI Plan utilizes the 1986 edition'of the ASME Section XI code.

During recent discussions with representatives of Hartford Steam Boiler Company, the contracted Authorized Nuclear Inservice Inspector (ANII) for the Point Beach Nuclear Plant, it was brought to our attention'that Wisconsin Electric:does not have a-formally documentea repair and replacement program which fully meets the program requirements described in the 1986 Section XI-Code, Articles IWX 4000 and 7000.

Repairs and_ replacements 1of ASME Section XI-scope, Class 1,-2, and 3 piping systems are currently conducted under-Wisconsin Electric's approved 10-CFR 50-Appendix B Quality Assurance Program.

This Quality Assurance Program meets the intent of ANSI N18.7-1976, " Administrative Controls and QA for the Operational Phase of Nuclear Power. Plants."

i Although we are confident that: the control of repairs and replacements under our existing QA program provides allevel of quality and safety equivalent to that required under the ASME.

Section XI Code, we'have committed to develop a formal:ASME Section XI repair and replacement program.

We have initiated'an in-depth review of our current repair and replacements procedures for.

compatibility with the requirements-of'the 1986 edition of the ASME Section XI.

Procedures will be revised or developed as-appropriate so that repair and replacement of Class 1, 2,

and 3 piping systems are conducted in a manner which-satisfies the requirements of the Section XI Code.

A formal program description _will_also be-8 0

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March 26, 1991 Page 2 developed that delineates ~how' repairs and replatoments of.these-4 piping systems are performed at Point Beach.- We expect to complete-these activities and have the formal program implemented by February-28, 1993.

This approach and schedule has been accepted by-our ANII.

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As mentioned previcusly, we believe the repair and replacement activities at our Point Beach Nuclear Plant provide a degree off quality and safety equivalent-to the requirementsqunder ASME-Section XI.

The activities we have begun will provide the-formal documentation for this process.

If you have any questions concerning our activities in this regard, please contact us.

Very truly yours, w /fu wq e

J.

Zach i

Direct Nuclear Power copies to:

-Regional Administrator, Region III' NRC Resident-Inspector l-l

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