ML20154J449
| ML20154J449 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 05/18/1988 |
| From: | Cheng C Office of Nuclear Reactor Regulation |
| To: | Hood D Office of Nuclear Reactor Regulation |
| References | |
| TAC-68060, NUDOCS 8805260385 | |
| Download: ML20154J449 (3) | |
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UNITED STATES
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Docket No.: 50-370 MEMORANDUM FOR:
Darl Hood, Project Manager Project Directorate 11-3 Division of Reactor Projects I/II FROM:
C. Y. Cheng, Chief Materials Engineering Branch Division of Engineering and Systems Technology
SUBJECT:
RELIEF FROM ASME CODE SECTION XI REQUIREMENT FOR THE NUCLEAR SERVICE WATER SYSTEM, MCGUIRE NUCLEAR STATION, UNIT 2, RELIEF REQUEST NO. 88-02 (TAC-68060)
By letter dated April 27, 1988, the Duke Power Company (the Licensee) requested relief from the ASME Boiler and Pressure Vessel Code Section XI requirement for hydrostatic testing of repair welds in the Nuclear Service Water System at the McGuire Nuclear Station, Unit 2.
The Licensee, pursuant to 10 CFR 50.55a(g)(5)
(iii), determined that the test requirament of Section XI, 1980 Edition, Winter 1980 Addenda, Articles IWA-4400 and IWA-5000, was impractical to perfom because the repaired piping containing the subject welds could not be isolated for pressurization.
The pump capacity to pressurize the piping is insufficient to offset the leakage through the butterfly valves used to isolate the welded section. The Nuclear Service Water System contains butterfly type valves ranging in size from 18-inch to 36-inch and operates at 6esign pressure and tem-perature of 135 psig and 95*F, respectively.
The integrity of the weld repair is assured by perfoming either a dye penetrant (PT) or magnetic particle (MT) inspection of both the root and final weld passes.
An inservice leak test at system pressure and temperature will be performed to detect weld defects and through wall leakage when the system is place in service.
The Materials Engineering Branch, Division of Engineering and Systems Technology has evaluated Relief Request No. 88-02. We conclude that the ASME Code Section XI test requirement is impractical to perform at the ricGuire Nuclear Station, Unit 2, and that the alternative tests provide an acceptable level of structural integrity for the Nuclear Service Water System.
Compliance with the specific ASME Code Section XI test requirement would result in hardship without a compen-sating inctesse in the level of quality and safety. Relief from the ASME Boiler and Pressure Vessel Code Section XI test requirement is granted as requested by the Licensee.
Contact:
Felix Litton X20926 8805260395 880518 DR ADOCK 0500037o p
MAY 1 s g, 2-This memorandum completes our assignment on TAC-68060. Our SALP report is attached.
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C. Y. Cheng, Chief Materials Engineering Branch Division of Engineering and Systems Technology cc:
L. ':.ao S, Varga J. Richardson J. Norberg D. Hood W. Hazelton M. Hum B. Brown, INEL G. Johnson J. Blake. R-II F. Litton DISTRIBUTION:
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SALP REPORT PLANT: McGuire Nuclear Station Unit 2 LICENSEE:
Duke Power Company DOCKET NO.:
50-370 REVIEWER:
Felix Litton TAC # 68060 LICENSING ACTIYiTY:
ISI Relief Request No. 88-02 EVALUATION CRITERIA RATING REMARKS 1.
Management Involement 2
ai.d Control in Assuring Quality 2.
Approach to Resolution 2
The Licensee's submittals of Technical Issues from were technically sound, a safety standpoint 3.
Respor.siveness to NP.C 2
The Licensee resonded to Initiatives NRC initiatives.
4.
Enforceinent History NA 5.
Reporting and Analysis NA of Reportable Events 6.
Staffing NA g
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