ML18092A229
| ML18092A229 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/03/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18092A230 | List: |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 NUDOCS 8407110264 | |
| Download: ML18092A229 (2) | |
Text
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OPS~G Public ServicE? Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department July 3, 1984
- u. s. Nuclear Regulatory Commission Off ice of Nuclear Reactor Regulation Washington, D. c. 20555 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch, Noo 1
Dear Mr. Varga:
REACTOR VESSEL MATERIAL SURVEILLANCE SALEM GENERATING STATION NO. 2 UNIT DOCKET NO. 50-311 Pursuant to the requirements of Appendix H to 10 CFR 50, PSE&G hereby submits WCAP -
10492, "Analysis of Capsule T from the Salem Unit 2 Reactor Vessel Radiation Surveillance Program."
This report includes data required by ASTM-E-185-1973.
The test results show that the increase in the transition temperature of the weld metal and base metal is greater than the "best estimate" value predicted by the methods of Regulatory Guide 1.99 Revision 1.
WCAP-10492 presents new heatup and cooldown limit curves based on the "upper limit" values predicted by Regulatory Guide 1.99.
The new curves are clearly more conservative than the current Technical Specification curves except for the 70° to 170°F range on the heatup limits curve.
In this range, the current Technical Specification curve allows slightly higher pressure.
Westinghouse stated that the new heatup limits curve is limited to 7.0 effective full power years (EFPY) as opposed to the 9.3 EFPY for the present Technical Specification curve, and hence the new curve is more conservative even in the 70° to 170°F range**~~~~~::;;:-;---;;-r;-...-r\\-7n:~~~~
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The Energy People 95-2168 (75M) 12-83
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_.~* I Mr. Steven 7/3/84 Westinghouse has informed us that it is common for the first surveillance capsule to yield a shift in transition temperature greater than predicted, and that testing of subsequent capsules indicates that the shift then returns to the originally predicted curve.
License Change Request 84-07 to incorporate the new curves into the plant's Technical Specifications will be transmitted to the NRC by August 1, 1984.
In the interim, a field directive is being issued to implement the new curves on Unit
- 2.
Should you have any questions, please contact us.
Sincerely, E. A. Liden Manager -
Nuclear Licensing and Regulation C
Mr. Donald c. Fisher Licensing Project Manager Mr. James Linville Senior Resident Inspector