ML092430393

Correction to Amendment No. 260 Modification of Surveillance Requirements for Containment Air Cooling and Filtering System and Removal of License Conditions

ML092430393
Person / Time
Site:	Fort Calhoun
Issue date:	09/28/2009
From:	Wang A Plant Licensing Branch IV
To:	Bannister D Omaha Public Power District
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME0051
Download: ML092430393 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 28, 2009 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station FC-2-4 Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT NO.1 - CORRECTION TO AMENDMENT NO. 260 RE: MODIFICATION OF SURVEILLANCE REQUIREMENTS FOR CONTAINMENT AIR COOLING AND FILTERING SYSTEM AND REMOVAL OF LICENSE CONDITIONS (TAC NO. ME0051)

Dear Mr. Bannister:

On July 22,2009, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 260, to Facility Operating License No.DPR-40 for the Fort Calhoun (FCS), Unit 1. The amendment consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated October 31, 2008.

Amendment No. 260 modified TS 3.6(3), "Containment Recirculating Air Cooling and Filtering System," by adding two new Surveillance Requirements (SRs) and modifying SRs 3.6(3)b, e and

f. In addition, the amendment removed the license conditions related to the replacement and testing of containment air cooling and filtering (CACF) unit high-efficiency particulate air filters and surveillance testing of the CACF unit relief ports. Omaha Public Power District had committed to these license conditions by letter dated April 10, 2008, and were implemented via TS Amendment No. 255 dated May 2, 2008.

Amendment No. 260 deleted Additional Conditions (2) and (3) in Appendix B associated with Amendment 255. In addition, Amendment No. 260 renumbered Additional Condition (4) for Amendment No. 257 to Additional Condition (2). Due to an administrative error, the issued revised page Appendix B - Page 1 of the TSs inadvertently revised the implementation date for Additional Condition (2). Our approval of Amendment No. 257 stated that the amendment shall be effective as of the date of its issuance and shall be implemented within 270 days of the date of issuance. However, our approval Amendment No. 260 revised Appendix B - Page 1 to state that Amendment No. 257 is effective as of its date of issuance and shall be implemented prior to startup from the 2008 refueling outage. Therefore, the effective date stated for Amendment No.

257 was inadvertently changed as result of our approval of Amendment No. 260.

This error did not impact Amendment No. 260 for FCS. The error does not change the NRC staff conclusions regarding Amendment No. 260 for FCS. Enclosed is a corrected version of page Appendix B - Page 1. Please discard the associated page from the previous amendment and replace it with the enclosed page.

D. Bannister -2 If you have any questions, please call me at 301-415-1445.

Sincerely, Alan B. Wang, Proj Plant Licensing Bra I h IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

As stated cc w/encl: Distribution via Listserv

ENCLOSURE CORRECTED APPENDIX B - PAGE 1 FOR AMENDMENT NO. 260 FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285

TECHNICAL SPECIFICATIONS Appendix B Additional Conditions Renewed Facility Operating License No. DPR-40 Omaha Public Power District shall comply with the following conditions on the schedules noted below:

Amendment Number Additional Conditions Implementation Date 181 (1) The licensee is authorized to relocate certain technical The amendment specification requirements to licensee-controlled documents. shall be implemented Implementation of this amendment shall include the as of its date of relocation of these technical specification requirements to the issuance.

appropriate documents, as described in the licensee's application dated November 20, 1996, as supplemented by letters dated February 20, 1997, and March 25, 1997, and evaluated in the staffs safety evaluation dated March 27, 1997.

257 (2) Upon implementation of Amendment No. 257 adopting The amendment is TSTF-448, Revision 3, the determination of control room effective as of the envelope (CRE) unfiltered air in leakage as required by TS date of its issuance 3.1, Table 3-3, Item 10.b. in accordance with TS 5.24c.(i), and shall be the assessment of CRE habitability as required by implemented within Specification 5.24c.(ii), and the measurement of CRE 270 days of the date pressure as required by Specification 5.24d, shall be of issuance.

considered met. Following implementation:

(a) The first performance of TS 3.1, Table 3-3, Item 10.b., in accordance with Specification 5.24c.(i), shall be within the next 18 months as the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.24c(ii), shall be within the next 9 months as the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, Specification 5.24d., shall be within the next 138 days.

Appendix B -Page 1 Amendment No. 1g1 ,255, 257, 260

D. Bannister -2 If you have any questions, please call me at 301-415-1445.

Sincerely, IRA!

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing OfFice of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

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