ML20082E276
| ML20082E276 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/31/1995 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-94-03, GL-94-3, LR-N95022, NUDOCS 9504110170 | |
| Download: ML20082E276 (2) | |
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Public Service -
T Electric and Gas
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Cornpany 4
Stanley' La8runa -
Public Service Electric and Gas Company - ' P.O. Box 236, Hancocks Bndge, NJ 08038. 609-339-1700 -
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- MAR 311995 LR-N95022 United States Nuclear Regulatory Commission
~ Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENTAL RESPONSE TO GENERIC LETTER 94-03, l
"INTERGRANULAR STRESS COREOSION CRACKING OF
' CORE SEROUDS IN. BOILING WATER REACTORSH BOPE-CREEK GENERATING STATION DOCKET NO. 50-354 On August 24,-1994, PSE&G responded to Generic Letter (GL) 94-03'.-
1 Reporting Requirement 2 of the GL requested that an inspection plan of the core shroud be submitted to the U.S. Nuclear Regulatory Commission (USNRC) no later than 3 months prior to-performing the inspections except for those plants whose
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inspections would occur less than three months from the. receipt
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of the'GL. 'Our response'for Hope Creek Generation Station (HCGS) indicated that an' augmented inspection program for the core shroud would be developed in consideration of the recommendations-by the Boiling Water Reactor Vessel and Internals Project (BWRVIP).
The BWRVIP recommendations are specified in-the "BWR Core Shroud-Inspection and Flaw Evaluation Guidelines," GENE-523-113-0894)
Revision 0, dated September 1994.
This document was submitted to the USNRC on September 2, 1994 by the BWRVIP. 'The HCGS shroud is considered highly resistant to Intergranular stress Corrosion cracking (IGSCC) due, primarily, to plant water chemistry, material carbon content, fabrication history, neutron-fluence, i
and hot operating time.
The HCGS core shroud has been identified by the BWRVIP Report, Table-3-1, as an inspection Category A facility based on: 1) the l
shroud has been fabricated with low carbon content Type 304L stainless steel; 2) the: core shroud has experienced less than 8 hot operating years, and; 3) the shroud has consistently been exposed to water chemistry below BWR Water Chemistry Guideline Action Levels.
A Category A plant is not expected to experience shroud cracking in the near term and, as such, augmented inspections are not considered necessary at this time.
9504110170 950331 PDR -ADOCK 05000354 j
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MAR 31586 Docuhant Control Desk 2-IR-N95022 A caveat in the above BWRVIP Report is that the individual plants should confirm their categorization based on hot operating years since the frequency.and extent of core shroud weld cracking would i
be expected to correlate with hot operating time.
As in the
'BWRVIP Report, because this data is not readily available, HCGS is using reactor-critical years, which is a close approximation, to determine whether it has passed the 8 year threshold.
HCGS will have approximately 7.7 reactor-critical years at the next refueling.
Commensurate with BWRVIP Inspection Category-A, augmented l
inspections of the HCGS core shroud are not planned for the November 1995 Refueling Outage.
However, in-vessel inspection (IVVI) will be performed, at that time, in accordance with the ASME Code,Section XI, Examination Category B-N-1.
The GL 94-03 augmented inspections of the core shroud will be considered for the March 1997 refueling outage.
If you have any questions in this matter, we will pleased to discuss them with you.
Sincerely,
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Mr. T. T. Martin, Administrator USNRC Region I i
Mr. D. H. Moran USNRC Senior Licensing Project Manager - Hope Creek Mr. R. J. Summers USNRC Senior Resident Inspector - Hope Creek (SO9)
Mr. K. Tosch, Manager IV New Jersey Department of Environmental Protection Bureau of Nuclear Engineering
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