ML17054B554
| ML17054B554 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/01/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17054B553 | List: |
| References | |
| NUDOCS 8504170020 | |
| Download: ML17054B554 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
71 TO FACILITY OPERATING LICENSE NQ.
DPR-63 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 DOCKET NO. 50-220 1.0 Introduction By application dated May 1, 1984 supplemented and clarified by letter dated October 22, 1984, Niagara Mohawk Power Corporation (the licensee) requested an amendment to Appendix A of Operating License No. DPR-63 for Nine Mile Point Nuclear Station, Unit No. 1.
The amendment request involves revising the Technical Specifications to add limiting conditions for operation, surveillance requirements and bases for the Remote Shutdown Panels (RSP).
2.0 Evaluation In its May I, 1984 submittal, the licensee proposed limiting conditions for operation (LCOs) and surveillance requirements for the RSPs.
- Also, the licensee identified those parameters which are monitored on the RSPs and their associated LCOs and surveillance requirements (Tables 3.6-13-1 and 4.6-13-1).
The LCO for the RSPs require that at least one shutdown panel be operable at reactor coolant temperature greater than 212'F and during power operation.
In addition, the RSP LCO defined the criteria for declaring a panel inoperable and identified the actions to be taken when both RSPs were inoperable.
In the case where both panels were inoperable, the licensee was required to submit a special report if at least one panel could not be returned to an operable status within 15 days.
For the monitoring instrumentation, the licensee included all of those parameters identified in its safe shutdown analysis as being needed to achieve hot shutdown, the minimum number of channels required to be
- operable, the frequency of sensor
- checks, and channel calibrations.
There was no specification for isolation or transfer switches.
The reason for this is that the licensee has demonstrated in its safe shutdown analysis that no isolation or transfer switches are required.
The staff reviewed the proposed surveillance requirements for RSP instrumentation at NMP-1.
These requirements, sensor checks and instrument channel calibrations, are listed in Table 4.6-13-1 (Remote Shutdown Panel Monitoring Surveillance Requirements).
Sensor checks are required once per day (except for the "All Rods In" light which will be checked once per refueling cycle),
and instrument channel calibrations will be performed once per 3 months (except for reactor water, torus water, and drywell 8504i y 0g00022 0 85040i PDR ADOCH P
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temperatures, and emergency condenser water level, which will be calibrated once per refueling cycle).
These surveillance frequencies are at least as conservative as those presented in the Standard Technical Specifications for RSP instrumentation at other BWRs.
The licensee's October 22, 1984 letter revised the actions required when both remote shutdown panels were inoperable.
In particular, the new LCO requires that at least one shutdown panel be operable during power operation and whenever reactor coolant temperature is greater than 212'F.
If this cannot be met, shutdown will commence within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the plant must be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Based on its review, the staff has determined that (1) all of the parameters identified in the licensee's safe shutdown analyses have been included in the Technical Specifications, (2) the LCOs and surveillance requirements for the instrument channels are consistent with other Technical Specifications or are within the frequencies recommended by the staff, and (3) the LCOs for the remote shutdown panels ensure opera-bility of the RSPs or require corrective actions in a time frame which is conservative with respect to staff guidance.
Therefore, the staff has concluded that Tables 3.6-13-1 and 4.6-13-1 contained in the May 1, 1984 submittal and Specification 3.6-13 and Surveillance Requirement 4.6-13 contained in the October 22, 1984 submittal are acceptable.
3.0 Environmental Considerations This amendment involves a change in the installation or use of a facility component located within the restricted area as well as a change in a surveillance requirement.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 Conclusion We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment wil.l not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
J. Holonich and R. Kendall Dated:
April 1, 1985
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