ML18093A513
| ML18093A513 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/25/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18093A514 | List: |
| References | |
| NLRN87220, NUDOCS 8712040352 | |
| Download: ML18093A513 (2) | |
Text
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Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 November 25, 1987 NLR-N87220 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SURVEILLANCE SPECIMEN CAPSULE TEST REPORT SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Attached, per the requirements of 10CFR50, Appendix H, Section III.A, is the technical report on the surveillance specimen capsule "U" which was withdrawn from Salem Unit 2 during the October 1986 refueling outage.
Comparison of 30 ft-lb. transition temperature increases for the Salem Unit 2 surveillance material with predicted increases using the methods of NRC Regulatory Guide 1.99 Revision 2 show that the plate material and weld metal transition temperature increase are higher than predicted.
However, a review of the results of the previous capsule, capsule "T" -
WCAP 10492, shows that this trend was previously identified and incorporated into the existing heatup and cooldown curves.
Comparison of existing Technical Specifications curves which are valid for 7 EFPY and the new curves which are valid for 10 EFPY indicates that the curves have moved primarily to reflect the longer validity of the curves.
A License Change Request (LCR) revising the Unit 2 heatup and cooldown curves based on the Westinghouse report will be forwarded to you by November 1988.
This LCR will include a modification of the Technical Specification design basis section to reflect the use of Rev. 2 of Regulatory Guide 1.99 and state-of-the-art f luence measurement and material damage predictions.
Should you have any questions, please do not hesitate to contact us.
Attachment reii12040352 871125--------1 I
PDR ADOCK 05000311 i
P PDR.
Sincerely,
Document Control Desk 2
C Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 11-25-87