ML17056A054
| ML17056A054 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/14/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056A053 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 8906210089 | |
| Download: ML17056A054 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY-EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT.NO.
8 TO FACILITY OPERATING LICENSE NO. NPF-69 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR POWER STATION UNIT NO.
2 DOCKET NO. 50-410 INTRODUCTION By letter dated November 10, 1988, Niagara Mohawk Power Corporation (the licensee) requested an amendment to the Technical Specification for Nine Mile Point Unit No. 2.
The amendment would incorporate the requirements of Generic Letter 88-01.
The staff has reviewed the application and prepared the following evaluation.
EVALUATION Generic Letter 88-01 "I'IRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" was issued on January 25, 1988.
The Generic l.etter provides staff positions regarding the intergranular stress corrosion cracking (IGSCC) problems in Boiling Water Reactor (BWR) austenitic stainless steel piping.
The Generic Letter Applies to all BWR piping made of austenitic stainless steel that, is four inches or larger in nominal diameter and contains reactor coolant at a temperature above 200'F during power operation regardless of Code classification.
It also applies to reactor vessel attachments and appurtenances.
The Generic Letter requires an Inservice Inspection (ISI)
Program to be implemented for the piping covered under the scope of the letter and to revise the Technical Specifications to incorporate the letter requirements.
Model Technical Specifications were enclosed in the Generic Letter.
By letter dated November 10, 1988, the licensee submitted a Technical Specification amendment application to incorporate the requirements of Generic Letter 88-01.
The Specification's are identical to the model Specification's included in the Generic Letter.
The amended specifications will impose additional requirements to the unit's surveillance requirements and will not create a safety concern.
In fact, the new requirements are designed to minimize and control IGSCC problems, thereby enhancing safety.
Based on the above the staff finds the licensee's proposed amendment acceptab'Ie.
ENVIRONMENTAL CONSIDERATION This amendment involves a change in a surveillance requirement for the facility components located within the restricted areas as defined in 10 CFR 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 9 89ab14
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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,Sec 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.
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 these amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Dated:
June 14, 1989 PRINCIPAL CONTRIBUTOR:
N. Slosson
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