ML080560409
| ML080560409 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  (DPR-040) |
| Issue date: | 02/27/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Markley, M T, NRR/DORL/LP4, 301-415-5723 | |
| Shared Package | |
| ML080560407 | List: |
| References | |
| TAC MD6221 | |
| Download: ML080560409 (2) | |
Text
- 2.
Accordingly, Renewed Facility Operating License No. DPR-40 is amended by changes as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 251, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented prior to startup from the 2008 refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. DPR-40 and Technical Specifications Date of Issuance: December 17, 2007
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 251 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285
1.0 INTRODUCTION
By application dated July 31, 2007 (Agencywide Documents Access and Management System Accession No. ML072150050), Omaha Public Power District (the licensee) requested changes to the Technical Specifications (TS) (Appendix A to Renewed Facility Operating License No.
DPR-40) for the Fort Calhoun Station, Unit No. 1 (FCS).
The proposed amendment would revise TS 2.7(1), Electrical Systems - Minimum Requirements, TS 2.7(2), Electrical Systems - Modification of Minimum Requirements, and TS 3.7(5), Emergency Power System Periodic Tests - Required Safety Related Inverters. The licensee proposed adding two safety-related swing inverters to the 120 Volt (V) alternating current (ac) instrument buses. Specifically, the proposed changes would revise Limiting Conditions for Operation (LCO) TSs 2.7(1) and 2.7(2) to take advantage of the additional operational flexibility the swing inverters will provide. In addition, editorial changes to correct spelling and formatting errors were made to TS 2.7 and TS 3.7.5.
2.0 REGULATORY EVALUATION
FCS was licensed for construction prior to May 21, 1971, and at that time committed to the draft General Design Criteria (GDC). The draft GDC, which is similar to Appendix A, General Design Criteria for Nuclear Power Plans in Part 50 of Title 10 of the Code of Federal Regulations (10 CFR), that govern emergency power at FCS are Criterion 24 and Criterion 39 from the FCS Updated Safety Analysis Report. The U.S. Nuclear Regulatory Commission (NRC) staff used the following requirements to review the licensees amendment request:
Criterion 24 - Emergency Power for Protection Systems In the event of loss of all offsite power, sufficient alternate sources of power shall be provided to permit the required functioning of the protection systems.
This criterion is met. Emergency power is available from two completely independent diesel generator (DG) sets and from two completely independent 125 volt d-c [direct current] systems for essential d-c loads.