ML20011E471
| ML20011E471 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/05/1990 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-01, GL-88-1, NLS-90-022, NLS-90-22, NUDOCS 9002140200 | |
| Download: ML20011E471 (2) | |
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i Carogne Power & Light Cosgeny SERIAL: NLS-90-022 P.o. Son 1M1
- Ratgh. N C. 27002 FEB 0 51990 l
A. 8 CUTTER Vece President Nuclear Services Department P
United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 l
ICSCC INSPECTION PLANS AND INSPECTION RESULTS Centlemen:
By letter dated June 28, 1989, and August 21, 1989, Carolina Power & Light Company (CP&L) confirmed its decision for reoirculation piping replacement at the Brunswick Steam Electric Plant, Unit 1 and 2 (BSEP 1&2).
I The decision to replace the reoirculation piping eliminates the need for certain ootamitments made relative to the weld inspection / repair program.
Specifically, the 10 SCC inspection plans for BSEP 1&2 were scheduled for submittal three months prior to the next refueling outags.
Also, results from piping weld inspections were to be submitted to NRC 30 days prior to unit s ta rtup.
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In the December 21, 1989 NRC letter accepting CP&L's response to Generio Letter 88-01, it is recognized that submittal to the staff of future 10 SCC i
inspection plans will not be required.
However, if flaws are found that do not meet Paragraph IWB-3500 oriteria of Section XI of A3ME B&PV Code for continued operation without evaluation, the evaluation of the flaws and repair plans should be submitted to the staff for review prior to startup.
In consideration of this staff position, CP&L will not be submitting the IGSCC inspection plans for the next BSEP 1 refueling outage as previously committed.
in our March 14, 1989 letter (NLS-89-061).
In addition, inspection results for submittal to the NRC will be comprised of any flaws that do not meet Paragraph IWB-3500 criteria of Section XI of ASME B&PV Code for continued operation without evaluation.
The evaluation and repair plans for these flaws will be submitted to the NRC prior to startup when practicable.
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