ML20086G462

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Forwards Application for Amend to License DPR-40,revising TS Sections 1-5 to Implement Core Operating Limits Rept Per Generic Ltr 88-16
ML20086G462
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 11/27/1991
From: Gates W
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20086G466 List:
References
GL-88-16, LIC-91-321A, NUDOCS 9112050120
Download: ML20086G462 (2)


Text

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1 Omaha Public Power District i 444 South 16th Street Mall November 27, 1991 Omaha. Nebraska G8102 22 ri LIC-91 321A 402/63G 2000 U. S. Nuclear Regulatory Commission Attn: Docutaent Control Desk Mail Station PI-137 Washington, DC 20555

References:

1. Docket No. 50 285
2. Generic Letter 88-16 "Removi,1 of Cycle Specific Parameter Limits from Technical Specifications," October 4, 1988 Gentlemen:

SUBJECT:

Application for Amendment of Operating License Enclosed please find Omaha Public Power District's (OPPD) " Application for Amendment of Operating License" which seeks to amend the fort Calhoun Technical Specifications by eliminating the cycle-specific operating limits and incorporating the Core Operating Limits Report, which will contain the cycle-specific limits. These changes are in response to NRC Generic letter 88-16 which encourages all licensees to eliminate cycle-specific limits from the Technical Specifications. The proposed changes have been developed consistent with the guidance provided in the generic letter.

In support of the proposed changes, the following documentation is being submitted for your review and approval:

Discussion, Justification and No Significant Hazards Analysis Attachment A: Transient-Safety Limits Attachment B: Summary Description of Technical Specification Changes Attachment C: Proposed Technical Specification Changes Attachment D: Example of Core Operating Limits Report (Cycle 13)

The proposed changes are considered administrative in nature. OPPD has eva!uated the proposed changes and has determined that they do not involve a significant hazards consideration as defined in 10 CFR 50.92.

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U. S. Nuclear Regulatory Commission ,

LIC-91-321A Page 2 If you should have any questions, please contact me.

  • Sincerely, 4

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/n W. G. Gates y Division Manager Nuclear Operations WGG/sel Attachment c: LeBoeuf, Lamb, Leiby & MacRae R, D. Martin, NRC Regional Administrator, Region IV D. L. Wigginton, NRC Senior Project Manager R. P. Mullikin, NRC Senior Resident inspector

11. Borchert, Director Division of Radiological llealth State of Nebraska l

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