ML20214R065
| ML20214R065 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/19/1986 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML18041A142 | List: |
| References | |
| TAC-59122, NUDOCS 8612050358 | |
| Download: ML20214R065 (3) | |
Text
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November 19, 1986 Docket No. 50-219 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
10 CFR 50.62 ATWS RULE (MPA A-20, TAC 59122)
Re:
Oyster Creek Nuclear Generating Station Enclosed is the NRC staff's safety evaluation (SE) of the BWR Owners Group's (BWROG'sl licensing topical report in response to the Anticipated Transients Without Scram (ATWS) rule in 10 CFR 50.62. In accordance with paragraph (c)(6) of 10 CFR 50.62, you are required to submit sufficient information to demonstrate to the Commission the adequacy of an alternate rod injection (ARI) system, a standby liquid control (SLCl system and a reliable reactor coolant recirculating pumps trip (RPT) system for Oyster Creek. To meet this, because you have participated in the BWROG's topical report, you may reference the topical report in support of your plant-specific submittal.
For the SLC system, you should choose one of three alternatives and follow the conditions stated in the staff's SE. For the ARI system, you may use the check list in Appendix A of the staff's SE to address your design details and its conformance with the ARI design objectives and design basis requirements. For the RPT system, you should indicate whether your installed system is the same as the Monticello design or the modified Hatch design.
You are requested to submit your schedule to upgrade your RPT design to either of the approved designs or to demonstrate that your design can perform its function in a reliable manner eauivalent to the two approved designs.
Also, you should propose in your submittal appropriate Technical Specifications for the ATWS related components for Oyster Creek.
You are requested to submit this information for Oyster Creek no later than March 31, 1987. This should provide sufficient time for the NRC staff to review your submittal and then for you to have the necessary equipment installed in the Cycle 12 Refueling (Cycle 12R) outage in 1988.
In your letter dated October 9, 1985, in response to 10 CFR 50.62(d), you committed to meet the requirements in 50.62(c)(3) and 50.62(c)(4), the reouirements on ARI and SLC, respectively, by the Cycle 12R outage. For the requirements on RPT in 10 CFR 50.62(c)(5), you stated that Oyster Creek has an ATWS RPT which is actuated on high reactor pressure and on low-low reactor water 8612050358 861119 PDR ADOCK 05000219 P
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1 Mr. P. B. Fiedler November 19, 1986 i
level. The Cycle 12R outaae is the second refueling outage after July 16, 1984, as specified in 10 CFR 50.62(d) and is, therefore, acceptable to the staff. You are requested to inform the staff of any changes to this schedule.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, N.
tw, Jr., Project Manager BWR Project ' irectorate #1 Division of BWR Licensing
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION Docket File EJordan NRC PDR BGrimes Local PDR JPartlow BWD1 Reading JDonohew OGC-BETH CJamerson WHodges JZwolinski TCollins RDiggs Glainas 0C File RBernero GHolahan l
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Mr. P. B. Fiedler Oyster Creek Nuclear Oyster Creek Nuclear Generatir.g Station Generating Station cc:
Mr. Ernest L. Blake, Jr.
Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C.
20037 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al.
New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David M. Scott, Acting Chief Regional Administrator, Region 1 Bureau of Nuclear Engineering U.S. Nuclear Regulatory Commission Department of Environmental Protection 631 Park Avenue CN 411 King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08625 BWR Licensing Manager GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
P. O. Box 388 Forked River, New Jersey 08731
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