ML17058B026

Safety Evaluation Supporting Amend 131 to License DPR-63

ML17058B026
Person / Time
Site:	Nine Mile Point
Issue date:	07/27/1992
From:	Office of Nuclear Reactor Regulation
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ML17058B025	List: ML17058B024 ML17058B026
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NUDOCS 9208040336
Download: ML17058B026 (8)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.

131 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 By letter dated May 27,

1992, as supplemented June 22,

1992, Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station Unit No.

1, Technical Specifications (TS).

The requested changes would revise TS Figure 2. 1. 1 (Flow Biased Scram and APRM Rod Block),

TS 3. 1.7 (Fuel Rods),

and associated Bases to replace cycle specific limits with requirements that the reactor be operated within the requirements of limits specified in the Core Operating Limits Report (COLR).

TS 6.9. I.f (Core Operating Limits Report) would be revised to require that the cycle-specific parameters proposed to be removed from TS Figure 2. 1. 1, TS 3. 1.7, and associated Bases be included in the COLR.

The proposed amendment would also correct two typographical errors on pages 64a and 64c of TS 3. 1.7.

The June 22, 1992, letter corrected a typographical error in the May 27,

1992, submittal and did not change the initial proposed no significant hazards consideration determination.

2. 0 EVALUATION Generic Letter (GL) 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications,"

was issued on October 4, 1988, to encourage licensees to propose chaages to TS that would remove cycle-specific limits from TS and include those limits in a Core Operating Limits Report.

GL 88-16 also requires that cycle-specific limits included in the COLR be calculated in accordance with NRC-approved methodology.

License Amendment No.

109 was issued on August 21, 1989, in response to the guidance provided in GL 88-16.

However, License Amendment No.

109 did not remove cycle-specific limits from TS Figure 2. 1. 1 (Flow Biased Scram and APRM Rod Block) or TS 3. 1.7 (Fuel Rods).

The proposed amendment would remove cycle-specific limits from TS Figure 2. 1. 1 and TS 3. 1.7 and expand the requirements of TS 6.9. l.f (Core Operating Limits Report) to include these cycle-specific lim'.ts.

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The NRC staff has reviewed the proposed changes and has determined that they are consistent with the guidance provided in GL 88-16 and, therefore, they are acceptable.

Plant operation continues to be limited in accordance with cycle-specific parameter limits in the COLR that are established using NRC-approved methodology per TS 6.9. 1.f.2.

In addition to the proposal to remove cycle-specific limits from TS Figure

2. 1. 1 and TS 3. 1.7, the licensee proposed to correct typographical errors on TS pages 64a and 64c.

We have reviewed these proposed corrections and have determined that they are indeed administrative changes and, therefore, they 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 ENVIRONMENTAL 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 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 (57 FR 28202).

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 CONCLUSION

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 will 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: July 27, 1992

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Docket,No.

5P-220 x

July 27, 1992 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road

Syracuse, New York 13212

SUBJECT:

ISSUANCE OF AMfNDHfNT FOR NINf HILf POINT NUCLfAR STATION UNIT NO.

1 (TAC NO. M83725)

The Commission has issued the enclosed Amendment No.

131 to Facility Operating License No.

DPR-63 for the Nine Mile Point Nuclear Station Unit No.

1 (NHP-l).

The amendment consists of changes to the Technical Specifications in response to your application transmitted by letter dated Hay 27,

1992, as supplemented June 22, 1992.

The amendment revises Technical Specification (TS) Figure 2. 1. 1, TS 3. 1.7, and associated Bases to replace cycle-specific limits with requirements that the reactor be operated within the requirements of limits specified in the Core Operating Limits Report (COLR).

TS 6.9. l.f is being revised to require that the cycle-specific parameters removed from TS Figure 2. 1. 1, TS 3. 1.7, and associated Bases be included in the COLR.

The amendment is in accordance with the guidance provided in NRC Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits. From Technical Specifications,"

and also corrects two typographical errors on pages 64a and 64c of TS 3. 1.7.

A copy of the related Safety Evaluation is enclosed.

A Notice of Issuance will be included in the Commission's,n'ext regular biweekly Federal Re<eister notice.

Sincerely, Original signed by:

Enclosures:

l.

Amendment No. 131to DPR-63 2.

Safety Evaluation cc w/enclosures:

See next page Donald S. Brinkman, Senior Project Manager Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation OFFICE IIAHE LA:PDI-1 CSVo anC4 PH: PDI-1 DSBrinkman:

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/92 OFFICIAL RECORD COPY FILENAME: B: iNM183725.AMD

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DATED:

Jul 27 1992 AMENDMENT NO.

131 TO FACILITY OPERATING LICENSE NO. DPR-63-NINE NILE POINT UNIT 1

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