ML20196G018
| ML20196G018 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/25/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20196G011 | List: |
| References | |
| NUDOCS 9812070192 | |
| Download: ML20196G018 (2) | |
Text
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UNITED STATES
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p NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. speeHom i
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REl.ATED TO AMENDMENT NO. 24 6 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
DOCKET NO. 50-333 l
1.0 INTRODUCTltQN On August 3,1998, as supplemented October 20,1998, the Power Authority of the State of New York (the licensee, also known as the New York Power Authority) requested changes to the Technical Specifications (TSs) for the James A. FitzPatrick Nuclear Power Plant. The proposed changes revise a note to allow rpplication of the safety limit minimum critical power ratio (SLMCPR) to Cycle 14. Presently, the SLMCPR applies only to Cycle 13. The supplemental information submitted on October 20,1998, provides additional details regarding the Cycle 14 fuel cycle design. This supplementalinformation does not affect the NRC staff's proposed finding of no significant hazards considerations.
2.0 E. VALUATION I
The proposed change consists of revision of a note on page 7 of the FitzPatrick TS which applies to TS section 1.1.A. The proposed note reads as follows:
NOTE: TS 1.1.A is applicable for Cycle 14 only.
Presently, this note applies only to Cycle 13. Tha Cycle 14 SLMCPR in TS l.1.A is not changed L
from the value of 1.09 for two recirculation loop operation and 1.10 for single loop operation.
l These values are for reactor pressure 2785 psig and core flow 210% of rated flow, i
l The Cycle 14 core design is a mixed core of GE12 and GE11 fuel, consisting of 560 fuel j
i assemblies, of which there are 174 twice-bumed GE11,4 twice-bumed ATRIUM-1 OA lead test assemblies,190 once-bumed GE12, and 192 new GE12 fuel assemblies.
l The Cycle 14 SLMCPR analysis was performed by General Electric (GE) using the plant-and l
cycle-specific fuel and core parameters, NRC-approved methodologies including GESTAR-11 (NEDE-2401 1-P-A-1 1, Sections 1.1.5 and 1.2.5), a revised R-factor methodology described in NEDE-32505P, "R-Factor Calculation Method for GE-11, GE-12 and GE-13 Fuel," November 1995, and proposed Amendment 25 to GESTAR-11. The revised R-factor calculation method used the same NRC-approved equation stated in GESTAR (Topical Report NEDE-24011-P-A),
except for adding the correction factors and substituting rod-integrated powers for the lattice peaking factors to account for the effects of the part-length-rod design. The proposed Amendment 25 to GESTAR-11 provides cycle-specific Safety Limit MCPRs that replace the former generic bounding Safety Limit MCPR.
The NRC staff reviewed the following: (1) the R-factor calculation method for GE-11 and GE-12 l
fuel, (2) the justification for the SLMCPR value of 1.09 for the Cycle 14 operation, and (3) the 9012070192 981125 PDR ADOCK 05000333 P
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2-relevant information provided in the proposed Amendment 25 to GESTAR-11, NEDE-24011 (which is under the staff review). The staff concluded that the Cycle 14 SLMCPR analysis for FitzPatrick using a revised R-factor calculation method in conjunction with the approved method is acceptable. The Cycle 14 SLMCPR will ensure that 99.9% of the fuel rods in the core will not experience ooiling transition which satisfies the requirements of General Design Criterion 10 of Appendix A to 10 CFR Part 50 regarding acceptable fuel design limits. Therefore, the staff has concluded that the justification for analyzing and determining the SLMCPR value of 1.09 for FitzPatrick Cycle 14 operation is acceptable since (1) the approved methodologies were used, (2) the current TS limit of 1.09 is conservative with respect to the Cycle 14 calculated SLMCPR of j
1.084. The proposed change from Cycle 13 to Cycle 14 to reflect the applicability of the i
proposed TS change to the upcoming Cycle 14 operation for FitzPatrick is also acceptable.
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3.0 STATE CONSULTATION
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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 change requirements 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 amendments involve 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 involve no significant hazards consideration, and there has been no public comment on such finding (63 FR 48264). Accordingly, the amendment meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmentalimpact 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 enoangered 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: T Huang Date:
November 25, 1998
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