ML20147D297

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Amend #52 to Facil Oper Lic #DPR-46 Revising Tech Specs Increase in Storage Capacity of Spent Fuel Pool from 740 to 2366 Fuel Assemblies
ML20147D297
Person / Time
Site: Cooper Entergy icon.png
Issue date: 09/29/1978
From: Grimes B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20147D231 List:
References
TAC-06962, TAC-6962, NUDOCS 7810140015
Download: ML20147D297 (4)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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-NEBRASKA PUBLIC POWER DISTRICT 00CXET NO. 50-298 COOPER NUCLEAR STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. OPR-46

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Nebraska Public Power District dated July 22, 1977, as supplemented by letters dated November 30, December 16,1977, June 12, 28, July 5 and 14, 1978, com- .

plies 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 CFR Chapter I;

8. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 l the public; and E. The issuance of this amendment is in accordance with 10 CR Part i 51 of the Ccmmission's regulations and all applicable requirements have been satisfied.
2. Accordingly, the 'iicense is amended by changes to the Technical Soecifications as indicated in the attachment to this license amencment and par & graph 2.C(2) of Facility License No. OPR-46 is hereby amended to read as follows: j (2) Technical Soecifications The Technical Soecifications contained in accendices A and B, as revised througn Amendment No. 52, ara hereby.incorocrated in the license. The licensee '

shal1 operate tne facility in accordance with the

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Technical Specifications.

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3. This license amendment is effective as of the date of its issuance. .E FOR THE NUCLEAR REGULATORY C0tEISSION '

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Brian K. Grimes, Assistant. Director for Engineering and Projects Division of Operating Reactors .

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Attachment:

Changes to the Technical-Specifications SENE*3EE 8 Date of Issuance:

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ATTACHMENT TO LICENSE AMENDMENT'NO. 52 i FACILITY OPERATING LICENSE NO. DPR-46 0 DOCKET NO. 50-298

- Remove page 218 of Appendix A and replace with revised page 218. Marginal lines indi:: ate area of change. ,

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5.4.C' (contd.)

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. penetrations shall' be designed in accordance with standards set l

. Section V-2.3.4 of the SAR. .;

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5.5 Fuel Storage 4 A. The new fuel' storage facility shall be such that the K,ff dry is less than ) -

0.90 and flooded in less than 0.95.

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3. The spent fuel storage racks are designed and shall be maintained with a ,

nominal 6 9/16 inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a Kegg equivalent to < 0.95 with l the storage pool filled with unborated water. The K f, has been con-servativelycalculatedtobe0.9271whichiswellbu$oOthe=aximum allowable K of. 0.95 as described in Section X-3.5 of Volume IV of the

'SAR. In ad$kfion, fuel'in the storage pool shall have a U-235 loading of 3

< 14.5 grams of U-235 per axial centimeter of fuel assembly.  !

C. The spent fuel storage pool is designed and shall be maintained with a f Storage Capacity limited to no more than 2366 fuel assemblies, D. The fuel handling bridge fuel hoist has a load-limit cell set at no more than 1230 pounds. .f 5.6 Seismic Design

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The seismic design for-Class I structures and equipment is based on dynamic analyses using acceleration response spectrum curves which are based on a ground motion of 0.1.g. The vertical ground acceleration assumed is equal to of the horizontal ground acceleration. For'the design of Class I structures and equipment, the maximum horizontal and vertical accelerations were con- ,

sidered to occur simultaneously. Where' applicable, stresses were added r

directly.  !-

The combined stresses resulting from dead, live, pressure, thermal and earthquake having a ground acceleration of 0.2g are such that a safe shut-  ;

down can be achieved. [

5.7 Barge Traffie r

Barge traf fic on the Missourt River past the site has been analyzed to i determine that the present size and cargo materials do not create a hazard -

to the safe operation of the plant. Contact will be maintained with the i Corps of Engineers to determine if and when additienal analyses are required due' to changes in barge size or cargo. ,

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218

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