ML20083M485

Amend to 840209 Application for Amend to License DPR-40, Revising Tech Specs Re Limiting Conditions for Operation on Reactor Coolant Flow for Cycle 9 Reload Application

ML20083M485
Person / Time
Site:	Fort Calhoun
Issue date:	04/16/1984
From:	William Jones OMAHA PUBLIC POWER DISTRICT
To:	John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20083M488	List: ML20083M485 ML20083M495
References
LIC-84-113, NUDOCS 8404180160
Download: ML20083M485 (2)

Text

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f Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 April 16, 1984 LIC-84-ll3 Mr. James R. Miller, Chief l U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Renctors Branch No. 3 Washington, D.C. 20555

Reference:

Docke t No. 50-285

Dear Mr. Miller:

Cycle 9 Reload Amendment Application Pursuant to discussions held on April 11, 1984 with members of your staff, the attached information is provided as an amendment to the District's Application for Amendment of Operating License dated February 9, 1984 and filed February 14, 1984. Attachment A contains the proposed Technical Specifications wording and support-ing revised tables. Attachment B contains the discussion, justifi-cation, and significant hazards consideration for the proposed re-vision. This revision replaces only those pages which were changed from the original submittal.

Sincerely, IA k hk k W. C. Jones Division Manager Production Operations WCJ/JJF:jmm Attachments cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D.C. 20036 Mr. E. G. Tourigny, Project Manager Mr. L. A. Yandell, Senior Resident Inspector 8404180160 840416 PDR ADOCK 05000285 45 5124 Employment with Equal 0pportunity Male / Female

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REVISIONS TO CYCLE 9 RELOAD APPLICATION (1) The proposed limiting conditions for operation on recctor coolant flow have been revised to leave the actual flow the limit in the Technical Sp?>cifications and to include indicated flow rate in a footnote.

(2) Table B-1 has been revised to reflect the change discussed l

in (1) above.

(3) Table 7-2 has been revised to clarify the methods used to account for uncertainties and to explicitly discuss the j methods used to calculate DNBR.

(4) Tables 7.2.1-1 and 7.2.5-1 have been revised to more ac-curately show that the effects of uncertainties on system l

parameters were treated deterministically and that the DNBR calculations were performed using a method which statistical-ly combined the DNBR calculational factors.

(5) Tables 7.2.2-1 and 7.2.3-1 have been revised to show the extremes of a range of values for selected key parameters that were considered in a statistical combination of un-i certainties for these parameters.

a.

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I ATTACHMENT A

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