ML20237E309

Amend 113 to License DPR-46,revising Tech Specs Re Design Features of Fuel Storage Facilities

ML20237E309
Person / Time
Site:	Cooper
Issue date:	12/21/1987
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237E296	List: ML20237E294 ML20237E309 ML20237E326
References
NUDOCS 8712280263
Download: ML20237E309 (4)

Text

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/ o UNITED STATES

!"' 'n NUCLEAR REGULATORY COMMISSION

.E WASHINGTON, D. C. 20555

% ...s /

N_EBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.113 3 License No. DPR-46

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

A. The application for amendment by Nebraska Public Power District (the licensee) dated October 20, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 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 i Commission; C. There is reasonable assur wce (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 r,ot 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.

2. Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:

8712280263 871221 PDR ADOCK 05000298 p PDR

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(2) Technical Specification The Technical Specifications contained in Appendix A, as revised through Amendment No.113, are hereby incorporated in the license.

The licensee shall operate tne facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

d. 6< [W Jose A. Calvo, _ Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 21, 1987 l

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ATTACHMENT TO LICENSE AMENDMENT NO.ll3 FACILITY OPERAhNG LICENSE NO. DPR-46

i DOCKET NO. 50-298 1 a

Replace the following page of the Appendix A Technical-Specifications with the enclosed page. The revised a"eas are indicated by marginal lines.

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5.4.C .

(cont'd) penetrations shall be designed in accordance with standards ser. forth in Section V-2.3.4 of the SAR.

5.5 Tuel Storage A. The new fuel storage vault shall be such that the K dry is less than 0.90 and flooded is less than 0.95. These K limI N are satisified by maintaining the maximum, exposure-dependent I of the individual fuel bundles

_< 1.29.

B. 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. K ff shall be maintained ( 0.95 with the storage!

pool filled with unborated watef This K is satisfiId by maintaining the maximum, exposure-dependent K, of the indINdual fuel bundles < 1.29.

C. The spent fuel storage pool is designed snd shall be maintained with a storage capacity limited to no more than 2366 fuel assen.blies.

D. The fuel handling bridge fuel hoist has a load-limit cell set at no more than 1230 pounds.

5.6 Seismic Design The seismic design for Class 1 structures and equipment is based on dynamic analyses using acceleration response spectrum curves which are bas'ed on a ground motion of 0.1.g. The vertical ground acceleration assumed is equal to h 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 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 Traffic f Barge traffic on the Missouri River past the site has been analyzed to 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 Corps of Engineers to determine if and when additional analyses are required due to changes in barge size or cargo.

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-218- Amendment No. ER,113 j