ML17058A795
| ML17058A795 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/10/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17058A794 | List: |
| References | |
| NUDOCS 9106130140 | |
| Download: ML17058A795 (6) | |
Text
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
125 TO FACILITY OPERATING LICENSE NO.
DPR-63 NIAGARA HOHAMK POWER CORPORATION NINE NILE POINT NUCLEAR STATION UNIT NO.
1 DOCKET NO. 50-220
1.0 INTRODUCTION
By letter dated Hay 26,
- 1989, as amended January 5, 1990, Niagara tlohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station Unit tlo. 1, Technical Specifications (TS).
The requested changes would revise TS Figure 3.4.1 (Reactor Building Pressure) to clarify that the reactor building pressures specified thereon are actually reactor building differential pressures.
2.0 EVALUATION The proposed revisions to TS Figure 3.4.1 would clarify that the reactor building pressures specified thereon are actually reactor building differential pressures.
The NRC staff has reviewed the proposed changes and has determined
. that the Figure 3.4.1 pressures were obviously intended to be differential pressures.
The proposed changes clarify the original intent of the figure.
Therefore, the proposed revisions to Figure 3.4.1 are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONtIENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The NRC 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
t4
exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (56 FR 20041).
Accordingly, the 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 the amendment.
- 5. 0 CQNCL.US ION The Commission has 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, (2) such activities wi 11 be conducted in compliance with the Commission s regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Donald S.
Brinkman Date:
June lO, 1991
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June 10, 1991 Docket No. 50-220 Distr-tbutioA;-
tlHWTr NRC/Local PDRs PDI-l Reading SVarga JCalvo RACapra DBrinkman CVogan OGC CCowgill DHagan GH111 (4)
Wanda Jones CGrimes ACRS(10)
GPA/PA OC/LFMB Plant File CMcCracken Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
SUBJECT:
ISSUANCE OF AMENDMENT FOR NINE MILE POINT NUCLEAR STATION UNIT NO. l (TAC NO. 74754)
The Commission has issued the enclosed Amendment No. l25 to Facility Operating License No.
DPR-63 for the Nine Mile Point Nuclear Station Unit No. l (NMP-1).
The amendment consists of changes to the Technical Specifications in response to your application transmitted by letter dated May 26,
- 1989, as amended January 5,
1990.
Sincerely, ORIGINAL SIGNED BYs The amendment revises Technical Specification Figure 3.4.1 to correct errors of omission in the labeling of the graph on the figure.
The revisions to
'igure 3.4. 1 clarify that Reactor Building pressures specified thereon are actually differential pressures.
A copy of the related Safety Evaluation is enclosed.
A Notice of Issuance will be inc1uded in the Commission's next regu1ar biweekly Federa'I"
~ge ister-notice.
Donald S. Brinkman, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
l.
Amendment No. 12~ to DPR-63 2.
Safety Evaluation cc w/enclosures:
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NMPl AMEND 74754
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