ML20065Q107
| ML20065Q107 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/11/1990 |
| From: | Crimmins T Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-11, NLR-N90216, NUDOCS 9012140222 | |
| Download: ML20065Q107 (2) | |
Text
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s ULC ! 1 1993 HLR-N90216 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlement ADDITIONAL INFORMATION REGARDING GENERIC LETTER 88-11
!! OPE CREEK GENERATING STATION DOCKET NO. 50-354 By letters dLted November 28, 1988, March 8, 1990 and April 17, 1990, Public Service Electric & Gas Company (PSE&G) responded to Generic Letter 88-11 and subsequent requests for additional information regarding radiation embrittlement of reactor vessel materials.
By letter dated June 27, 1990, the Nuclear Regulatory Commission accepted PSE&G's response and provided its safety evaluation.
Specifically, analysis of a flux wire dosimeter removed from the llope Creek reactor vessel at the end c
- the first fuel cycle and subsequent analytical work demonstrated the llope Creek reactor vessel pressure-temperature curves are conservative for 32 EFPY using Reg. Guide 1.99, Rev. 2 methods.
The next specimen removal and analysis / analytical confirmation of the curves required by Technical Specifications (3/4.4.6, Table 4.4.6.1.3-1) will occur at 6 EPPY.
Based on the referenced correspondence, PSE&G has satisfied the requirements of Generic Letter 88-11.
PSE&G withdraws its commitment made by PSE&G letter NLR-N90167, dated August 27, 1990 to remove a surveillance capsule during the next refueling outage and to submit revised pressure-temperature curves based on analysis of that capsule.
To allow the evaluation of specimens later in the life of the reactor vessel, PSE&G will remove the next surveillance capsule as required by Hope Creek Technical Specifications.
After that capsule has been analyzed, any required changes to the pressure-temperature curves will be submitted to the NRC.
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NLR-N90216 Should there be any questions with regard to this submittel, please do not hesitate to contact us.
Sincerely,
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C Mr. Stephen Dembek Licensing Project Manager Mr. T.
P. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Depa t'nent of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
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