ML17056B268
| ML17056B268 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/01/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056B266 | List: |
| References | |
| NUDOCS 9102110211 | |
| Download: ML17056B268 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY-EVALUATNN-BY-THE-OFFICE-OF-NUCLEAR-REACTOR-REGUEATION, RELATED-TQ-AMENDMENT-NQc-
--TO-FACIL,ITY-OPERATING-LICENSE-NQc -DPR-63 NIAGARA-MOHAWK--POKIER-CORPORATION NINE -NICE - POINT "NUCL:EAR-STATION.- UNIT"NQ c '1 DOCKET:-NQc-50-22Q INTRODUCTION By letter dated June 20,
- 1988, as supplemented October 19,
- 1989, Niagara Mohawk Power Corporation (the licensee) submitted a request for revision of the Technical Specifications, Appendix A, to Operating License No.
DPR-63 for the Nine Mile Point Nuclear Station, Unit No.
1.
The proposed changes would consolidate the requirements for suppression chamber level instrumentation into one Technical Specification.
The Technical Specifications currently require the use of suppression chamber water level instrumentation in Technical Specifications 3.6.2, 4.6.2, 3.6. 11, and 4.6.11.
Technical Specifications 3.6.2 and 4.6.2 apply to the operability of plant instrumentation that performs a safety function.
Technical Specifications 3.6.11 and 4.6. 11 apply to ensur ing the availability of selected plant variables for monitoring the specified parameters following an accident.
EVALUATION.
The proposed Technical Specification change would delete the requirements for suppression chamber water level from Technical Specifications 3.6.2 and 4.6.2, Tables 3.6.21 and 4.6.21, and Bases 3.6.2 and 4.6.2.
The Technical Specifications would retain the requirements for suppression chamber water level in Technical Specifications 3.6. 11 and 4.6. 11, Tables 3.6. 11, and 4.6. 11, and Bases 3.6.11 and 4.6.11.
The licensee's rationale for this change is that the suppression chamber water level instrumentation does not automatically initiate any engineered safeguards system.
It does ensure that sufficient information regarding the suppression chamber water level is available to the operator in order to monitor and assess this variable during and following an accident.
Therefore, the suppression chamber water level need only be included in the Accident Monitoring Technical Specifications (Technical Specifications 3.6.11 and 4.6.11).
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Technical Specification Table 4.6.2l requires the suppression chamber water level instrumentation to be calibrated once every six months.
Technical Specification Table 4.6.11 requires the suppression chamber water level instrumentation to be calibrated once during each major refueling outage.
The proposed change would only require the suppression chamber water level instrumentation to be calibrated once during each major refueling outage.
The once per refueling outage calibration frequency is in agreement with the recommendations of Generic Letter 83-36, "NUREG-0737 Technical Specifications,"
and the General Electric Boiling Water Reactors Standard Technical Specifications.
This calibration interval will provide adequate instrumentation performance.
Therefore, the proposed Technical Specification change is acceptable.
In addition to the above noted changes, the licensee proposed the following editorial chanoes.
Tables 3.6.2m and 4.6.2m, Control Room Air Treatment System Initiation, would be redesignated as Tables 3.6.21 and 4.6.21, respectively.
Corresponding changes would also be made in Technical Specifications 3.6.2"and 4.6.2 where these Tables are referenced.
Index pages ii and iii would be corrected to include the appropriate titles and page numbers for Technical Specifications 3.2.6, 4.2.6, 3.6.4, and 4.6.4.
The staff has determined that these proposed changes are purely administrative, do not change any requirements and are, therefore, acceptable..
SUMMARY
Based on the above evaluation, the staff concludes that the licensee's request to revise the Nine Mile Point Nuclear Station, Unit No.
1 Technical Specifications to consolidate the suppression pool chamber water level instrumentation into one Technical Specification is acceptable.
ENVIRONMENTAL,CONSIDERATION This amendment involves a change in a requirement with respect to the installation or use of the facility components located within the restricted areas as defined in 10 CFR Part 20.
The staff has determined that this 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 radi ation 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 tn 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
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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 will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
February 1, 1991 PRINCIPAL CONTRIBUTOR:
B. Marcus
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