ML20203E843
| ML20203E843 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 04/16/1986 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20203E846 | List: |
| References | |
| NUDOCS 8604240449 | |
| Download: ML20203E843 (5) | |
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UNITED STATES
'i NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 f
ARKANSAS POWER & LIGHT COMPANY c
00CKET N0. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated November 20, 1985, as supplemented January 29, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 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 (i) 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is he.reby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, are hereby incorporated in the.
license. The licensee shall operate the facility in accordance with the Technical Specifications.
1 8604240449 860416 PDR ADOCK 05000368 P
2-a 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSICN Georges. Knight
, Director-PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 16, 1986 j
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April 16, 1986 ATTACHMENT TO LICENSE AMENDMENT N0. 71 FACILITY CPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following page of the Appendix "A" Technical Soecifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change. The corresponding I
overleaf page is also provided to maintain document completeness.
Remove Pages Insert Pages 5-S 5-5 4
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j DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,295 + 400 cubic feet at a nominal T of 545 F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
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5.6 FUEL STORAGE CRITICALITY - SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with a nominal 12.8 inch center-to-center distance between fuel assemblies having-a maximum enrichment of 4.3 weight percent U-235 placed in the equivalent to 1 0.95 when flooded with storage racks to ensure a k ff unborated water. The k 8f<0.95includesaconservativeallowance of 1.7% Ak/k for uncert$ ties as described in Section 9.1.2.3 of the FSAR.
In addition, fuel in the storage pool shall have a U-235 loading of 1 47.8 grams of U-235 per axial centimeter of fuel assembly.
CRITICALITY - NEW FUEL
- 5. 6.1. 2 The new fuel storage racks are designed and shall be maintained with a nominal 25.0 inch center-to-center distance between new fuel assemblies such that K will not exceed 0.98 when fuel having a maximum enrichment of 4.1 weig8bfpercent U-235'is in place and aqueous foam 4
moderationisassumedandK[$r.illnotexceed0.95whenthestoragearea w
is flooded With unt ~ated w!
The calculated K includes a conserva-eff tive allowance of '.1% a.k/k for uncertainties.
c DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 399' 10 1/2".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained j
with a storage capacity limited to no more than 486 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
ARKANSAS-UNIT 2 5-5 Amendment No. 71
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