ML20081H826
| ML20081H826 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/27/1983 |
| From: | Haynes J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8311070598 | |
| Download: ML20081H826 (4) | |
Text
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Southern California Edison Company L
5 AN ONOF RE NUC LE AR GE NE R A T ING S T A TION r.o. so m 128 S A N C LEME N T E, C A LIF CR NI A 92672 October 27, 1983 U. S.17uclear Regulatory Comission Office of Inspection and Enforcement Region V 1450 Maria Lane, suite 210 Walnut Creek, California 94596-5368 Attention:
Mr. John B. Martin, Regional Administratcr
Dear Sir:
Subject:
Docket 170. 50-362 San Onofre riuclear Generating Station Unit 3
Reference:
Letter, J. G. Haynes (SCE) to J. B. Martin, (IEC),
dated June 29, 1983 pursuant to Action Items 2 and 4 of I&E Bulletin 82-02, written inspection reports of reactor coolant pressure boundary closure connection threaded fasteners are to be provided to the appropriate IRC Regional Office within 60 l
days of the completion of an outage which included the opening of nuch closures for component inspection or maintenance.
':he referenced letter provided you with the results of initial inspections performed on fasteners associated with such openings during a recent outage at San Onofre Unit 2 and made reference to our original bulletin response committing to making such reports within 90 days of such outage completion.
Consistent with these connitments, enclosed is a written report on the results of an inspection of fasteners associated with primary manway covers on both Steam Generators at San Onofre Unit 3 perforned during an outage completed on August 8, 1983.
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8311070598 831027 PDR ADOCK 05000362 G
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Mr. John B. Martin October 27, 1983 If there are any questions regarding the above or enclosed information, please contact me.
Subscribed on this 37 day of OL
, 1983.
very truly yours, By:
44fA%
J.G.HAYNES/
STATION MANAGER Subscribed and swor to before me this W day of C J. t 9s;3 c22
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Enclosure cc: Director, Office of Inspection
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.4 SUPPLEME! CAL RESPONSE 'IO IE BULLETIII 10. 82-02 P
DEGRADATION OF THREADED FASTDIERS IN 'IHE REACIOR COOLA!C PRESSURE BOUNDARY OF PWR PLAICS IE BULLETIN NO. 82-02 ACTION ITEM NO. 4, PARTS b. AND c.
REPORT OF INFORMATION REQUESTED IN ACTION ITEM 10. 2 4
I San Onofre Nuclear Generating Station Unit 3 l
October 28, 1983 r
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SUPPLEME! CAL RESPONSE ':0 IE-BULLETIN 10. 82-02 SAN O!OFRE NUCLEAR GENERATI!iG STATION, UNIT 3 DEGRADATION OF THREADED FASTENERS IN WE REAC'IOR COOLA!C PRESSURE BOUNDARY (RCPB) OF POWER PLA!CS P
SCOPE I&E Bulletin No. 82-02 requires, in part, that a written report on the results of the examination performed on threaded fasteners of Reactor Coolant Pressure Boundary closure connections be provided when such closures are opened for companent inspection or maintenance. The report must include a)
Identification of the specific connections examined, and b) the results of the inspection performed per IWA-2210 and IWA-2220 of ASME Code section XI.
RESPONSE
This report covers all inspections performed during the San Onofre Unit 3 outage which ended on August 8, 1983 of threaded fasteners which are within the scope of IE Bulletin 82-02.
Forty (40) primary manway studs and nuts were removed from Steam Generator S31301ME088 and subjected to visual inspection per the requirements of paragraph IWA-2210 of the 1977 Edition of the ASME Boiler and Pressure Vessel Code,Section XI. Minor physical damage to the threads of two (2) cold leg studs (serial numbers 3-15 and 3-18) was observed. The damaged threads were chased and found to be acceptable. All studs and nuts were then subjected to magnetic particle examination (surface examination per IWA-2220). No indications were found. The minor physical damage to the threads, which was determined to be acceptable, appeared to be the result of dropping the stud or otherwise impacting the threads. It is not, therefore, considered to be damage or degradation due to normal in-service conditions.
Forty (40) primary manway studs and nuts were removed from Steam Generator S3130lME089 and subjected to the same examinations as those studs and nuts removed from S3130lME088. No indications were found with either visual or surface examination techniques.
All eighty (80) studs and nuts were returned to service in the steam generator froc which they were removed.
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