ML19320D132
| ML19320D132 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/27/1980 |
| From: | Andognini G BOSTON EDISON CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 80-124, IEB-79-14, NUDOCS 8007210006 | |
| Download: ML19320D132 (2) | |
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CosTON EDISON COMPANY GENERAL offices 500 SovLaTO. STREET 50efon MASSACMUSETTs 02199
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=WCLEAN OpSmATIONS 08p427.E=T June 27, 1980 BEco Ltr. 680-124 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue
. King of Prussia, PA.'
19406 License No. DPR-35 Docket No. 50-293 IE Bulletin #79-14 Inspection Report
Dear Sir:
Part of Boston Edison's overall commitment regarding IE Bulletin 79-14 was to submit a report with the final results of the inspection within 30 days of the con.pletion of our 1980 refueling outage. Therefore, the following information is now offered:
Summary of Inspection and Analysis Results The physical inspection of safety related piping systems has been completed in accordance with the requirements of IE Bulletin 79-14.
Approximately 550 inspection deviations were issued as a result of tne system walkdowns, all of which have been resolved.
The increase in the number of deviations over that which was reported in the 120 day response is due to inspection of totally in-accessible systems, inspection of inaccessible portions of accessible systems, and additional inspection of accessible systems due to inspection procedure implementation changes.
Of the 550 deviations, about 150 had some direct effect on the piping seismic analysis.
The majority of these e ffects are judged to be minor or insignificant.
The remaining 400 odd inspection deviations affect the pipe supports, with the potential of indirectly affecting the piping stress levels.
However, the vast majority of these deviations would not affect the pipe support's capability to
. function as designed.
Of those deviations that would adversely affect the supports, only a few would be expected to result in pipe stresses greater than code allowable stresses and none would be expected to cause pipe stresses to exceed the operabil-ity criteria.
In addition to the piping system physical inspections, a review was made of the input-documents to all seismic analyses.
This review identified'approximately 350 deviations, all of which have been resolved.
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. BOSTON EDISDN COMPANY Mr. Boyca H. Crisr, Dir:ctcr June 27,1980 Page 2 The inspection deviations affecting piping and the input document deviations were reviewed against the original seismic analyses, representing 95 isometrics.
The results of this review lead to seismic reanalysis of 89 of thoso isometrics.
Hanger guidance was gener'.ed from the reanalysis results and was used to review the pipe supports.
As a result of the investigation of the pipe support problems and problem causes reported in the 120 day response, all 1075 pipe supports for safety related piping were reviewed whether or not seismic reanalysis was performed.
This review, which considered all inspection deviations affecting pipe supports, identified 139 supports exceeding operability criteria stresses. Additionally, design modifica-tions have been identified for 163 supports which were found to be operable but exceed code allowable stress limits.
A more detailed description of the procedures and review criteria utilized in response to IE Bulletin 79-14 will be provided in a final report which we expect to submit by December 31, 1980.
In addition, final statistical information on the inspection, review, and modification results will be presented at that time.
Status of Modifications To date approximately 273 out of the 302 identified support modifications have been completed.
All support modifications which might in any way jeopodize system operability were completed prior to the plant's recent return to power. Of the remaining supports to be modified, approximately six (6) supports which exceed code allowable stresses, but do not exceed operability criteria stresses, will require disassembly to complete the support modification. A schedule for completion of these modfications has not yet been formultated; however, no modification would extend beyond our next refueling outage. All other support modifications are expected to be completed by September 1, 1980.
Very truly yours, JW s
cc:
Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.
C.-
20555
.