ML20062M601
From kanterella
| ML20062M601 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/25/1982 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20062M570 | List: |
| References | |
| RP-3, NUDOCS 8208200154 | |
| Download: ML20062M601 (2) | |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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Related Correspondence ML20125A6531985-02-0404 February 1985 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 1 to EP OP-0.1, Reactor Trip Response & Rev 5 to EP G-3, Notification of Offsite Organizations ML20209J1691985-01-31031 January 1985 Public Version of Revised Emergency Response Plan Sops, Including III.10, SOP Dept of General Svcs & III.24, Disaster Preparedness Plan for Peacetime Emergencies. Related Correspondence ML20215B2591984-11-0101 November 1984 Rev 4 to QC Procedure DCP-2, Silicone Room Installation. Partially Withheld Related Info Encl ML20101J2191984-10-31031 October 1984 Public Version of Revised SOPs for San Luis Obispo County Nuclear Power Plant Emergency Response plan.W/841219 Release Memo ML20100K1371984-10-30030 October 1984 Pg&E,Diablo Canyon Power Plant,1984 Emergency Preparedness Field Exercise DCL-84-336, Revised Emergency Plan Implementing Procedures,Including EP R-1 Re Personnel Injury or Illness,Ep R-6 Re Radiological Fire,Ep M-6 Re Nonradiological Fire & EP G-1 Re Accident Classification.Related Correspondence1984-10-25025 October 1984 Revised Emergency Plan Implementing Procedures,Including EP R-1 Re Personnel Injury or Illness,Ep R-6 Re Radiological Fire,Ep M-6 Re Nonradiological Fire & EP G-1 Re Accident Classification.Related Correspondence DCL-84-330, Rev 3 to, Repair/Replacement Program1984-10-19019 October 1984 Rev 3 to, Repair/Replacement Program ML20101B0721984-10-15015 October 1984 Public Version of Revised Emergency Plan Implementing Procedures,Including 1.1 Re Corporate Emergency response,3.2 Re Corporate Communications dept,4.1 Re Matls & 4.9 Re Qa. W/Jm Felton 841213 Memo DCL-84-302, Revised Emergency Plan Implementing Procedures,Including EPOP-0 Re Reactor Trip or Safety injection,EPOP-0.1 Re Reactor Trip Response & EPOP-0.2 Re Natural Circulation Cooldown.Related Correspondence1984-09-10010 September 1984 Revised Emergency Plan Implementing Procedures,Including EPOP-0 Re Reactor Trip or Safety injection,EPOP-0.1 Re Reactor Trip Response & EPOP-0.2 Re Natural Circulation Cooldown.Related Correspondence 1996-10-11 |
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PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT ISI REPAIR PROGRAM PLAN-Diablo Canyon Power Plant, Unit No.1 Procedure: RP-3 Chemical and Volume Control System Cold Leg Loop Charging Valve #8108 The valve was discovered to be operating erratically during routine verification i of the operability of the motor operator. Disassembly of the valve verified that the wedge seat was damaged requiring repair.
The inservice inspection program for Diablo Canyon, Unit No.1 is based upon the ASME Section XI code,1977 edition including Summer 1978 Addendum.
The valve was designed and fabricated in accordance with the requirements of ASME Section III Winter 1970 Addendum. The valve is a 3", 1500#, Motor-0perated Gate Valve and was manufactured by Velan Engineering. The valve wedge is SA-351 CF8, '
hard faced with Stellite No. 6.
Repairs will be made in accordance with the following:
- 1. Disassemble valve and remove wedge.
- 2. Remove hard facing from the wedge by machining and/or grinding ,
in accordance with IWB-4220 of Section XI Summer 1978 Addendum.
- 3. Liquid penetrant examine (ISI-PT-1) area where hard facing was removed. Minor porosity associated with the cast wedge shall be acceptabl e. Penetrant examination will be performed in accor-l dance with ASME Section V requirements.
I i 4. The wedge will be hard faced by welding (WPS 4.56). The welding procedure and welders are qualified to design specification and construction code.
- 5. The first and last weld layer will be examined by the liquid l
penetrant method to assure that no indications are created during welding.
- 6. Final machining of the wedge is to dimensions obtained during disassembly. Liquid penetrant examination of the final machined surface will be in accordance with ASME Section V requirements.
- 7. Pressure test ~after reinstallation will be in accordance with IWA-5214 and IWC-5000 of the Summer 1978 Addendum.
2 Quality assurance will be in accordance with PGandE's Quality Assurance Program for nuclear power plants.
l i
- 9. Documentation will be in accordance with Section XI and the repair will be recorded on Form NIS-2 per Code' Case N-308.
O!ho$h5 l PDR L
4 l
i
! Procedure: RP-3 l r
- 10. The service of an Authorized Nuclear Inservice Inspector will ,
be used for the repair. i Prepared /L l .. m Date 6-9-94 ';
Maintenance Engineet N
Reviewed h /. ! Date6/fdt)
[QC/ISI Approved M C 7 --
T Date#NI73 Plant Manager
. .. .- - - . - . - - - , . - - . . - . -_.
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