ML20062M589
From kanterella
| ML20062M589 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/25/1982 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20062M570 | List: |
| References | |
| RP-2, NUDOCS 8208200150 | |
| Download: ML20062M589 (2) | |
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|---|---|
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Text
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. PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT
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ISI REPAIR PROGRAM PLAN Diablo Canyon Power Plant, Unit No.1 Procedure: RP-2 Auxilary Saltwater Pressure Indicator PS-185A Isolation Valve The isolation valve for pressure indicator PS-185A was found leaking during routine inspection of pressure indicator PS-185A. The leaking occurring at the valve flange face and on the bonnet to body face.
The inservice inspection program for Diablo Canyon, Unit No.1 is based upon the ASME Section XI code 1977 edition including Sumer 1978 Addendum.
The isolation valve was designed and fabricated in accordance with the requirements of ANSI B31.1 1967 edition. The valve -- 11" 150# Gate Valve -- was manufactured by the Aloyco Valve Co. The valve is SA-351 Gr CF8M.
Repairs will be made in accordance with the following:
- 1. Remove all areas of crevice corrosion on the valve flange face and body to bonnet face by machining and/or grinding in accordance with l
IWB-4220 of Section XI Summer 1978 Addendum.
, 2. After removal of defective area, the cavity will be liquid penetrant
! tested (ISI PT-1). Minor porosity associated with the cast valve l
body shall be considered acceptable. Penetrant examination will be l
perfonned in accordance with ASME Section V requirements.
l 3. All areas where evidence of corrosion was removed will be built up d by welding (WPS-4.7). The welding procedure and welders are qualified to the design specification and construction code.
- 4. All weld layers will be examined by the liquid penetrant method to assure that no indications are created during welding.
- 5. Final machining of. the flange face and body to bonnet face to the original dimensions and examine after final machining by the liquid penetrant method in accordance with ASME Section V requirements.
l Minor porosity associated with the valve casting will be considered l
acceptable.
- 6. Pressure test after reinstallation will be in accordance with IWA-5214 and IWD-5000 of the Sumer 1978 Addendum.
- 7. The quality assurance will be in accordance with PGandE's Quality Assurance Program for nuclear power plants.
l
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8208200150 820812 l PDR ADOCK 05000275 G PDR
q Procedure: RP-2 .
- 8. Documentation will be in accordance with Section XI, and the repair will be recorded on Fom NIS-2 in accordance with Code -
Case N-308.
- 9. The services of an Authorized Nuclear Inservice Inspector will be used.
- Prepared Date ,C.2/-P2 Maintenance Engin#er
" Date S/2'lS7 I Reviewed K f.t?
Quality Control /ISI Approved Y 8 [ Date MZai42.:
Plant Manager p ,
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