ML020310369
| ML020310369 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  (DPR-040) |
| Issue date: | 03/04/2002 |
| From: | Wang A NRC/NRR/DLPM/LPD4 |
| To: | Ridenoure R Omaha Public Power District |
| References | |
| TAC MB3449 | |
| Download: ML020310369 (9) | |
Text
March 4, 2002 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE:
ADDITION OF TOPICAL REPORT REFERENCES TO TS 5.9.5, "CORE OPERATING LIMITS REPORT" (TAC NO. MB3449)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 203 to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated November 21, 2001.
The amendment adds three topical report references to TS 5.9.5, "Core Operating Limits Report."
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosures:
- 1. Amendment No. 203 to DPR-40
- 2. Safety Evaluation cc w/encls: See next page
March 4, 2002 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE:
ADDITION OF TOPICAL REPORT REFERENCES TO TS 5.9.5, "CORE OPERATING LIMITS REPORT" (TAC NO. MB3449)
Dear Mr. Ridenoure:
The Commission has issued the enclosed Amendment No. 203 to Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated November 21, 2001.
The amendment adds three topical report references to TS 5.9.5, "Core Operating Limits Report."
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285 DISTRIBUTION:
PUBLIC GHill (2)
Enclosures:
- 1. Amendment No. 203 to DPR-40 PDIV-2 Reading WBeckner
- 2. Safety Evaluation RidsNrrDlpmPdiv (SRichards)
RidsNrrPMAWang cc w/encls: See next page RidsNrrLAEPeyton RidsOgcRp RidsAcrsAcnwMailCenter CMarschall, RIV DBujol, RIV TS Pages: ML020640600 LHurley, RIV Package: ML020730252 KDesai ACCESSION NO.: ML020310369 OFFICE PDIV-2/PM PDIV-2/LA SXRB OGC PDIV-2/SC NAME AWang:lf EPeyton KDesai RWeisman SDembek DATE 2/8/02 2/7/02 01/29/02 24 Feb 02 2/21/02 OFFICIAL RECORD COPY
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 203 License No. DPR-40 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated November 21, 2001, 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 Commission; C.
There is reasonable assurance (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 license amendment will not 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, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of 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. 203, 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 within 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 4, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 203 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 5-10 5-10 5-11 5-11
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 203 TO 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 November 21, 2001, Omaha Public Power District (OPPD) requested changes to the Technical Specifications (TSs, Appendix A to Facility Operating License No.
DPR-40) for the Fort Calhoun Station, Unit No. 1. The requested changes would add three analytical methods to the list of approved core operating limits analytical methods in TS 5.9.5, "Core Operating Limits Report," for Fort Calhoun Station Unit 1. This proposed TS change will facilitate future reload calculations to support refueling outages and provides additional flexibility.
2.0 EVALUATION Fort Calhoun Station is planning a refueling outage in May 2002. Forty Westinghouse operating fuel assemblies will be replaced with new Framatome ANP assemblies during the May 2002 refueling outage. This is in addition to the 53 Framatome ANP assemblies that were installed during the last refueling outage. Therefore, of the 133 fuel assemblies in the core, 93 of the assemblies will now be manufactured by Framatome. The remaining 40 Westinghouse fuel assemblies will be replaced during the Fall 2003 refueling outage. Framatome ANP has developed three analytical methodologies to perform reload analyses. The licensee has proposed to reference the following three methods in the TS:
(1)
EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based,"
which was reviewed and approved by the staff for referencing by letter dated March 15, 2001 (Reference 1).
(2)
EMF-96-029(P)(A) Volume 1, EMF-96-029(P)(A) Volume 2, and EMF-96-029(P)(A)
Attachment, "Reactor Analysis System for PWRs, Volume 1, Volume 2, and Attachment," which were reviewed and approved by the staff for referencing by letter dated October 29, 1996 (Reference 2).
(3)
EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," which was reviewed and approved by the staff for referencing by letter dated May 11, 2001 (Reference 3).
These three methodologies are applicable for the reload analyses at the Fort Calhoun Station and have been previously reviewed and approved by the staff. The use of these methodologies will enable replacement of defective fuel assemblies and result in an efficient core operation.
The proposed TS change will add these three topical reports to TS 5.9.5. These approved analytical methods ensure that core parameters remain within prescribed limitations defined by the plants design basis and updated final safety analysis report accident analyses.
Accordingly, the staff finds this proposal acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
6.0 REFERENCES
1.
Letter, NRC to Framatome ANP, Richland, Inc., "Acceptance for Referencing of Licensing Topical Report EMF-2328 (P)(A), Revision 0, 'PWR Small Break LOCA Evaluation Model, S-RELAP5 Based'," dated March 15, 2001.
2.
Letter, NRC to Siemens Power Corporation, "Acceptance for Referencing of Topical Report EMF-96-029(P)(A), Vols. 1 and 2, 'Reactor Analysis System for PWRs'," dated October 29, 1996.
3.
Letter, NRC to Framatome ANP, Richland, Inc., "Acceptance for Referencing of Licensing Topical Report EMF-2310(P)(A), Revision 0, 'SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors'," dated May 11, 2001.
Principal Contributor: K. Desai Date: March 4, 2002
Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn ATTN: James R. Curtiss, Esq.
1400 L Street, N.W.
Washington, DC 20005-3502 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, NE 68008 Mr. Wayne Walker, Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 309 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Ms. Julia Schmitt, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P. O. Box 95007 Lincoln, Nebraska 68509-5007 Mr. David J. Bannister Manager - Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant Post Office Box 550 Fort Calhoun, NE 68023-0550 Mr. Mark T. Frans Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street Suite D Des Moines, IA 50309