ML17055C733
| ML17055C733 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/11/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Mangan C NIAGARA MOHAWK POWER CORP. |
| References | |
| TAC-59116, NUDOCS 8612230219 | |
| Download: ML17055C733 (4) | |
Text
December 11, 1986 Docket No. 50-220 Mr. C. V. Manaan, Senior Vice President Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Mangan:
SUBJECT:
PLANT-SPECIFIC ATWS REVIEW GUIDELINES AND IMPLEMENTATION SCHEDULE (TAC 59116)
Re:
Nine Mile Point Nuclear Station, Unit No.
1
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HLi JZwolinski BWDl staff Enclosed is the staff's October 21, 1986, safety evaluation (SE) in support of the BWR Owners Group's licensing topical response to the ATWS rule, 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 (SLC) system and a reliable reactor coolant recirculating pump trip (RPT) system.
Those licensees/applicants, who participated in the BWR Owners Group topical
- report, may reference the topical report in support of their 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, we suggest you use the checklist found in Appendix A of the staff's SE to address the 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 desian.
The staff requires those utilities with the RPT desians to submit their schedule to upgrade their designs to either of the above approved desians or to demonstrate that their present design can perform its function in a reliable manner equivalent to the two approved designs.
Technical Specifications should be proposed for ATWS related components in your plant-specific submittal.
In order to support timely closure of this issue we request plant-specific inputs by March 31, 1987.
Please advise Janet Kelly, your NRC Project Manaaer, of any problems or questions.
This request for information, was Sigcerl.ly approved by OMB under clearance number "ur~9>>~1>>9ned by 3150-0011.
John A. Zwolinski, Director BWR Project Directorate Pl Division of BWR Licensing
Enclosure:
Safety Evaluation (ANO:8611030127) cc w/enclosure:
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Mr. C. V. Manaan Niagara,t"ohawk Power Corporation Nine Nile Point Nuclear Station, Unit No.
CC:
Troy B. Conner, i~r., Esquire Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.
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Washington, D.
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20006 Frank P..
- Church, Supervisor Town of Scriha R.
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- Oswego, New York 13126 Niagara Mohawk Power Corporation ATTN:
Hr. Thomas Perkins Plant Superintendent Nine Vile Point Nuclear Station Post Office Box 32
- Lycoming, New York
'13093 Resident Inspector U. S. Nuclear Regul'atory Commission Post ~ffice Box 126
- Lycoming, New York 13093
.lohn W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Reoional Administrator, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Yr. i)ay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223