ML20215M473
| ML20215M473 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/24/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20215M476 | List: |
| References | |
| DPR-59-A-101 NUDOCS 8610300274 | |
| Download: ML20215M473 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION X
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E WASHINGTON, D. C. 20555
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4 POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET N0. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLAN _T_
AMENDMENT TO FACILITY OPERATING LICEN5t Amendment No.101 s,
License No. DPR-59 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State ofNewYork(thelicensee)datedJuly 24, 1986, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954,
, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements l
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
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. (2) Technical Specifications 3
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION AV Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 24, 1986 S
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ATTACHMENT TO LICENSE AMENDMENT NO.101 FACILITY OPERATING LICENSE NO DPR-59 T-DOCKET NO. 50-333 l
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 246 246a - page added t
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1 JAFNPP l
5.5 (Cont'd)
B. The spent fuel storage pool is designed to maintain k.gr less than 0.95 under all condi-tions as described in the Authority's applica-tion for spent fuel storage modification trans-mitted to the NRC July 26, 1978.
This k gg value is satisfied if the maximaus, exposure dependent, infinite lattice multiplication i
factor, k,,
of the individual fuel bundle is i
less than or equal to 1.36.
The number of a
spent fuel assemblies stored in the spent fuel pool shall not exceed 2244.
i 5.6 SEISMIC DESIGN The reactor building and all engineered safeguards are designed on a basis of dynamic analysis using acceleration response sp,ectrum curves which are i
i normalized to a ground motion of 0.08 g for the i'
Operating Basis Earthquake and 0.15 g for the j
t f
g
=
k
,J Amendment No.
, pd, 101
{
JAFNpp 5.5.B Bases The spent fuel pool' and high density fuel storage racks are Class I structures designed t
to store up to 2244 fuel bundles. The storage racks are designed to maintain a suberitical configuration having a multiplication factor (k gg) less than 0.95 for all possible opera-tional and abnormal conditions.
The nuclear criticality analysis for the Spent Fuel Racks (Reference 1) concludes that fresh fuel bundles with,3.3 w/o U-235 meet the 0.95 k.gr limit with a 3.2% 4 k margin.
This design basis bundle was reanalyzed to determina its infinite lattice multiplication factor, k o.
when in a reactor core geometry (Reference 2).
This k.,was obtained under conservative calculational assumptions and reduced by 2.33 times the standard deviation in the calculation resulting in the Technical Specification limit of 1.36.
i References
- 1) Increased Spent Fuel Storage Modification, Stone & Webster Engineering Corporation, Boston, Mass. March 15, 1986.
l
- 2) General Electric letter, p.
Van Dieman to l
C.
- Rocke, FitzPatrick Fuel Storage K-infinity Conversion, Revision 1,
dated July 10, 1986.
i
.J Jmendment No.
101 246a