ML17054A680
| ML17054A680 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/18/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17054A679 | List: |
| References | |
| NUDOCS 8405150480 | |
| Download: ML17054A680 (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.
57 TO FACILITY OPERATING LICENSE NO. DPR-63 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 DOCKET NO. 50-220 1.0 Introduction
'y letter dated November 4, 1983 Niagara Mohawk Power Corporation (the licensee) proposed changes to the Technical Specifications (TS) of Facility Operating License No. DPR-63'for the Nine, Mile Point Nuclear Station, Unit No. 1.
The revision to the Technical Specifications addressed in this Safety Evaluation regards a change to the limiting conditions for operation, surveillance requirements, and bases pertaining to the inservice inspection, the augmented inservice inspection and inservice'testing programs.
Requirements for the inservice testing and augmented inspection programs were not formerly included in the Technical Specifications.
The proposed Technical Specification changes achieve consistency with 10 CFR 50.55(a)(g) and more closely match the Standard Technical Specifications.
The Technical Specification changes are general enough to permit changes in accordance with Section XI of the ASME Boiler and Pressure Vessel Code to meet the updating provisions of 10 CFR 50 without a corresponding Technical Specification change.
This submittal does not affect, or change, the present programs being implemented by Niagara Mohawk.
Changes to the inservice inspection or inservice testing programs must receive prior approval from the Nuclear Regulatory Commission.
2.0 Evaluation The licensee has proposed changes to the Technical Specifications for the inservice inspection and testing programs for the Nine Mile Point Nuclear Station, Unit No. 1.
The change for the Inservice Inspection Program is necessary to update Technical Specifications with the revised Inservice Inspection Program approved by the staff in a Safety Evaluation report dated September 19, 1983.
The change adding the Inservice Testing Program is necessary, since the requirement for inservice testing of components in accordance with the ASME Boiler and Pressure Vessel Code was established by changes in 10 CFR subsequent to the issuance of the Nine Mile Point Nuclear Station, Unit 1 license.
The changes to the Technical Specifica-tions for the inservice inspection and testing programs are consistent with NUREG-0123, Standard Technical Specifications for Boiling Water Reactors that is endorsed by Chapter 16 of the Standard Review Plant and are, therefore, acceptable.
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Niagara Mohawk Power Corporation has replaced the recirculation system and portions of other system piping attached to the recirculation system at Nine Mile Point Nuclear Station, Unit No. I with "conforming material" as defined in NUREG-0313, Rev.
1.
The licensee has proposed an augmented inservice inspection for the balance of systems containing "non-conforming" service sensitive piping identified by NUREG-0313, Rev.
1.
The program requires the extent of inspections in accordance with the frequencies contained in the NUREG using procedures that have been shown capable of finding in situ stress corrosion cracking and by individuals qualified to (I) the ASME Boiler and Pressure Code,Section XI and (2) Ultrasonic Testing Operator Training for Intergranular Stress Corrosion Cracking developed by the EPRI Non-destructive Examination Center.
We find the proposed augmented inspection program acceptable since the extent of inspection and frequencies specified in NUREG-0313, Rev. I are met for the remaining non-conforming service sensitive piping systems.
3.0 Environmental Considerations We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental
- impact, and pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement, or negative declaration and environmental impact appraisal need not 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 will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Robert A. Hermann Dated:
April 18, 1984
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