ML19246A664
| ML19246A664 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/29/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19246A666 | List: |
| References | |
| TASK-09-01, TASK-9-1, TASK-RR NUDOCS 7907060221 | |
| Download: ML19246A664 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISslON f,l
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WASHINGTON, D. C. 20555 Me..+/p/
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CONSUMERS POWER COMPANY DOCKET N0. 50-255 PALISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 49 License No. DPR-20 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated December 18, 1978, as supplemented by letter dated January 12, 1979, complies with the standards and reouirements of the Atomic Energy
-t of 1954, as amended (the Act), and the Comission'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 tne 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 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 have been satisfied.
298 _232
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79070602.2I-
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 49, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This' license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
}.
wn DernisL.Ziemann,,hief Operating Reactors Branch -2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: May 29, 1979
,qg 233 u.
ATTACHMENT TO LICENSE AMENDMENT NO. 49 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET N0. 50-255 Revise Appendix A by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 5-3 5-3 5-4 5-4 2(1B 2M e
scm s' nu sc??LT sv_'- In Msss) (ccetd) 53 532 F.eae:cr c:re and ccetrel a.
De reacter core s'a" apprc=i= ate a right Circular cylinder vith an equivalent dia:eter of about 135 inches and an active height of abou.
2,32 inches, Consist of apprc=i=ately h3,".rcalcy h b.
Se r-acter core s*="
.he fc = cf clad fuel reds ecstaining s1.16 ti:7 enriched traniu=.-
h The fuel re s shall te g cuped into 204 sistern UO pellets.
2 as s er.b lie s.
A core plug or plugs may be used to replace one or mor fuel assemblies subjec to the analysis of the resulting power distribu: ion.
The fully leaded core sha" C- '='- apprcxicate ' y 211,CCO pcus:is UO2 c.
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.s 298 235 a Qp C)?31@8hfiM 1 UVaWMllML k en6ent Mo. U, 49 53
5.4 FUEL STORAGE 5.4.1 New Fuel Storage a.
The pitch of the new fuel storage rack lattice is > 9.375 inches, and every other position in the lattice shall be permanently occupied by an 8" x 8" structural steel box beam or core plugs such that the minimum center-to-center spacing of new fuel assemblies in the alternating storage array is 13.26".
This distance in the alternating storage lattice is sufficient so that Keff will not exceed 0.98 where fuel which contains not more than 41.24 grams of U-235 per axial centimeter of active fuel assembly is in place and optimum (i.e., aqueous foam) moderation is assumed, and Qe Keff will not exceed 0.95 when the storage area is flooded with unborated water.
The calculated Keff includes a conservative allowance for uncertainties as described in CPC letters of 12/18/78 and 1/12/79.
b.
New fuel may also be stored in shipping containers.
c.
The new fuel storage racks are designed as a Class I structure.
5.4.2 Soent Fuel Storage a.
Irradiated fuel bundles will be stored, prior to off-site shipment in the stainless steel-lined spent fuel pool.
b.
The low capacity spent fuel storage racks are designed and shall be maintained with a nominal 11.25" center-to-center distance between fuel assemblies having a maximum U-235 loading of s 38.3 grams of U-235 per axial centimeter of fuel assemb;y placed in the storage racks to ensure a Keff equivalent to 1 0.95 when flooded with unborated water.
c.
The high capacity spent fuel storage racks are designed and shall be maintained with a nominal 10.25" center-to-center distance between fuel assemblies with the exception of the single Type E rack which has a nominal 11.25" center-to-center distance between fuel assemblies. The high capacity spent fuel storage racks are designed such that fuel having a maximum U-235 loading of 41.24 grams of U-235 per axial centimeter placed in the racks would result in a Keff equivalent to 1 0.95 when flooded with unborated water. The K9ff of s 0.95 includes a conservative allowance for uncertainties as described in CPC letter dated December 18, 1978.
d.
The spent fuel pool water boron concentration shall be verified at least once monthly to be ecual to or greater than 1720 opm.
e.
The spent fuel racks are designed as a Class I structure.
f.
Spent fuel shipping casks shall not be moved to the fuel storage building until such time as the NRC has reviewed and approved the spent fuel cask drop evaluation.
g.
Fuel stored in the high capacity storage racks as described in the SER supporting Arendment No. 28 shall have decayed for a minimum of 12 months if the storage racks are not supported by similarly designed, adjacent ragkg and the spent fuel pool wall or the cask anti-tipping device. (11 293 236 References
( )Until needed for fuel storage, two A-type racks in the northeast corner of the spent fuel pool uili be remo.ed and rec'ned with the cask anti-tipping d.vice to orovide rece m ry sei W C restraint FSAR, Appendix A 5-4 FSAR, appendix B Amendment No. E,49