ML18092B175
| ML18092B175 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/27/1986 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Corbin McNeil Public Service Enterprise Group |
| References | |
| NUDOCS 8606120745 | |
| Download: ML18092B175 (4) | |
Text
Docket Nos. 50-272 and 50-311 Mr. C. A. McNeill, llr.
Vice President - Nuclear May 27, Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. McNeill:
1986
. DI;STRIBUTION UPocket Fi1 e L PDR PAD#3Rdg OELD B. Grimes D. Fischer ACRS 10 NRC PDR Gray File H. Thompson E. Jordan J. Partlow C. Vogan N. Thompson As a result of the staff 1s reviews of the latest rev1s1ons of the heatup and cooldown curves for the Salem Unit 1 and Unit 2 facilities, the following request for additional information should be included in PSE&G 1s evaluation of future Unit 1 and Unit 2 surveillance capsules.
For Unit No. 1, according to the surveillance capsule withdrawal schedule in Section 7 of WCAP 10694, the next capsule will be removed when the reactor vessel has been in operation for 6 EFPY.
The information to be included in the evaluation of this capsule is documented in Attachment 1. Since the withdrawal of this capsule is 4 EFPY earlier than the effective perio9 for the Salem-1 pressure-temperature limits, the information requested in Attachment 1 will be available early enough for the licensee and the staff to determine whether the pressure-temperature limits curves require adjustment to meet the safety margins of Appendix G, 10 CFR 50.
For Unit No. 2, according to the surveillance capsule withdrawal schedule in Table 7-1 of WCAP 10492, the next capsule will be removed when the reactor vessel has been in operation for 3 EFPY.
The information to be included in the evaluation of this capsule is documented in Attachment 2.
Since the withdrawal of this capsule is 4 EFPY earlier than the effective period for the Salem-2 pressure-temperature limits, the information requested in Attachment 2 will be available early enough for the licensee and the staff to determine whether the pressure-temperature limits curves require adjustment to meet the safety margins of Appendix G, 10 CFR 50.
The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Enclosures:
As stated cc w/enclosures:
See next page
/s/DFischer Donald C. Fischer, Senior Project Manager PWR Project Directorate No. 3 Division of PWR Licensing-A, NRR i
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Mr. C. A. McNeill
- Public Service Electric & Gas Company Salem Nuclear Generating Station cc:
Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric & Gas Company P. 0. Box 570 - Mail Code TSE Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey* 08628 Mr. John M. Zupko, Jr.
General Manager - Salem Operations Public Service Electric & Gas Company Post Office Box E Hancocks Bridge, New Jersey 08038 Robert Traae, Mayor Lower Alloways Creek Township Municipal Hall Hancocks Bridge, New Jersey 08038 Thomas Kenny, Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Co111T1ission Drawer I Hancocks Bridge, New Jersey 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, New Jersey 08625 Frank Casolito, Action Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, New Jersey 08628 Richard B. McGlynn, Commission.
Department of Public Utilities*
State of New Jersey 101 Commerce Street Newark, New Jersey 07102 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, Pennsylvania 17120 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, New Jersey 08038 Mr. Bruce A. Preston; Manager Licensing and Regulation Public Service Electirc & Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038
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AITACHMENT i ADDITIONAL INFORMATION TO BE INCLUDED
.IN EVALUATION OF FUTURE SA~EM-1 SURVEILLANCE CAPSULES
- 1) For each fuel assembly use plant specific powe*r distribution in lieu of time-averaged conditions derived from statistical studies of long-term operation of Westinghouse 4 loop plants.
- 2) Which foil reactions are considered to produce the best estimated capsule neutron exposure?
Provide the justification for your choice
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ATIACHMENT 2
- ADDITIONAL INFORMATION TO BE INCLUDED IN EVALUATION OF FUTURE SALEM-2 SURVEILLANCE CAPSULES
- 1)
The discrete ordinate code i~put used to calculate the capsule neutron flux should include a pin-by-pin (outer row) power distribution or a justification for not using pinwise power distribution.
- 2)
For each* fuel assembly use plant specific power distribution in lieu of time-averaged conditions derived from statistical studi~s of long-term operation of Westinghouse 4 loop plants.
- 3)
If the licensee us~s low leakage cores (twice or thrice burned assemblies in outer row of core) neutron analysis should account for the presence of the Pu239. and P-u241 isotopes.
- 4)
Which foil reactions are considered to produce the best estimated capsule neutron exposure? Provide the justification for your choice.