ML20076D920
| ML20076D920 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/19/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| REF-SSINS-6820 IEB-83-02, IEB-83-2, LAP-83-390, NUDOCS 8308240009 | |
| Download: ML20076D920 (2) | |
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SERIAL: LAP-83-390 Carolina Power & Light Company AUG 191983 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO CONFIRMATORY ORDER INSPECTION OF BWR STAINLESS STEEL PIPING
Dear Mr. Vassallo:
By letter dated July 22, 1983, you transmitted to Carolina Power &
Light Company (CP&L) a Confirmatory Order for Brunswick Steam Electric Plant Unit No. 1 (Brunswick-1) relating to the inspection of recirculation system piping.
Item 2 of this Confirmatory Order requires that plans for an additional inspection of 20-inch diameter or larger recirculation system piping welds be submitted by August 19, 1983 for Staff review.
Carolina Power & Light Company commits to the following inspection plan for the Brunswick-1 20-inch diameter or larger recirculation system piping welds.
The weld joints listed below will be ultrasonically inspected during the outage presently scheduled to begin between November 1983 and March 1984:
IGSCC Carbon Susceptibility Weld Number SRI Content Rank 1-B32-28-A-3 1.464 0.058 1
1-B32-28-A-15 1.421 0.059 1
1-B32-28-B-3 1.341 0.058 1
These inspections will be performed by personnel qualified in accordance with IE Bulletin No. 83-02 as amended by a letter from Mr. D. C.
Eisenhut to Mr. E. E. Utley dated July 21, 1983.
If flaws indicative of IGsCC are found, appropriate repairs will be made and additional inspections will be The results of conducted in accordance with IWB 2430 of ASME Code Section XI.
the inspections and aay corrective actions taken will be reported to the NRC within 30 days after the end of the outage during which the inspections are Performed.
8308240009 830819 PDR ADOCK 05000324
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4 If you have any questions concerning this information, please contact our staff.
Yours very truly, P. W. Howe Vice President Brunswick Nuclear Project JT/WRM/ccc (7702WRM) cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. S. D. MacKay (NRC) l
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