ML083470491

Issuance of Amendment Regarding Revisions to Improved Technical Specification Surveillance Requirement 3.7.5.2, Emergency Feedwater System

ML083470491
Person / Time
Site:	Crystal River
Issue date:	01/09/2009
From:	Farideh Saba Plant Licensing Branch II
To:	Young D Florida Power Corp
Saba F, NRR/DORL/LPL2-2, 301-415-1447
References
TAC MD7960
Download: ML083470491 (10)

Text

January 9, 2009 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 - ISSUANCE OF AMENDMENT REGARDING REVISIONS TO IMPROVED TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 3.7.5.2, EMERGENCY FEEDWATER SYSTEM (TAC NO. MD7960)

Dear Mr. Young:

The Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 231 to Facility Operating License No. DPR-72 for Crystal River, Unit 3 in response to your letter dated January 17, 2008. The amendment revises Improved Technical Specification Surveillance Requirement 3.7.5.2, Emergency Feedwater System, to make the pump test frequency consistent with Technical Specifications Task Force Standard Technical Specification Change Traveler-101, Revision 0.

A copy of the safety evaluation is enclosed. The notice of issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Farideh E. Saba, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Amendment No. 231 to Facility Operating License DPR-72 Safety Evaluation cc w/enclosures: Distribution via ListServ

January 9, 2009 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 - ISSUANCE OF AMENDMENT REGARDING REVISIONS TO IMPROVED TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 3.7.5.2, EMERGENCY FEEDWATER SYSTEM (TAC NO. MD7960)

Dear Mr. Young:

The Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 231 to Facility Operating License No. DPR-72 for Crystal River, Unit 3 in response to your letter dated January 17, 2008. The amendment revises Improved Technical Specification Surveillance Requirement 3.7.5.2, Emergency Feedwater System, to make the pump test frequency consistent with Technical Specifications Task Force Standard Technical Specification Change Traveler-101, Revision 0.

A copy of the safety evaluation is enclosed. The notice of issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Farideh E. Saba, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Amendment No. 231 to Facility Operating License DPR-72

2. Safety Evaluation cc w/enclosures: Distribution via ListServ Distribution:

PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsOgcRp RidsNrrLACSola RidsNrrDorlDpr RidsAcrsAcnw_MailCTR RidsRgn2MailCenter RidsNrrPMFSaba ADAMS ACCESSION NO.: ML083470491 NRR-058 OFFICE LPL2-2/PM LPL2-2/LA ITSB/BC CRXB/BC OGC NLO LPL2-2/BC RSola GCranston NAME JPaige for FSaba RElliott AJones TBoyce 12/23/08 12/22/08 12/29/087 01/07/09 01/07/09 DATE 01/09/09 OFFICIAL RECORD

FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.231 License No. DPR-72

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power Corporation, et al. (the licensees), dated January 17, 2008, 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 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, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 231, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Thomas H. Boyce, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: January 9, 2009

ATTACHMENT TO LICENSE AMENDMENT NO. 231 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following page of Facility Operating License DPR-72 with the attached revised page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.

Remove Insert 4 4 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.

Remove Insert 3.7-10 3.7-10

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 231 TO FACILITY OPERATING LICENSE NO. DPR-72 FLORIDA POWER CORPORATION, ET AL.

CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302

1.0 INTRODUCTION

By letter dated January 17, 2008 (Agencywide Documents Access and Management System Accession No. ML080250020), the Florida Power Corporation (the licensee) requested changes to the Technical Specifications (TSs) for Crystal River Unit 3 (CR-3). The proposed changes revise the CR-3 Improved TS Surveillance Requirement (SR) 3.7.5.2, Emergency Feedwater System, to make the test frequency at CR-3 consistent with NUREG-1430, Volume 1, Revision 3, Standard Technical Specification for Babcock and Wilcox Plants - Specifications.

The Nuclear Regulatory Commission (NRC) staffs proposed no significant hazards consideration determination was published in the Federal Register on May 20, 2008 (73 FR 29163).

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The licensee provides technical specifications in order to maintain the operational capability of structures, systems and components that are required to protect the health and safety of the public. The NRCs regulatory requirements that are related to the content of the TS are contained in Title 10 of Code of Federal Regulations (10 CFR) Section 50.36, Technical Specifications. The TS requirements in 10 CFR 50.36 include the following categories: (1) safety limits, limiting safety systems settings and control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.

In general, there are two classes of changes to TSs: (1) changes needed to reflect modifications to the design basis (TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TS over time. This amendment deals with only the second class of changes. In determining the acceptability of such changes, the staff interprets the requirements of the current version of 10 CFR 50.36, using as a model the accumulation of generically approved guidance in the improved standard TS.

Within this general framework, licensees may remove material from their TSs on two conditions:

(1) the material is not required to be in the TSs based on the staff interpretation of 10 CFR 50.36, including judgments about the level of detail required in the TSs, and (2) there exist suitable alternative regulatory controls for the material.

Paragraph 10 CFR 50.36(c)(3) states, Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.

Section 10 CFR 50.55a, Codes and Standards. Paragraph 50.55a(g) requires that certain American Socie ty of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)

Class 1, 2, and 3 pumps and valves be designed to enable inservice testing (IST) and that testing be performed to assess operational readiness in accordance with the Section XI requirements of the ASME Code. This is to help ensure operational readiness of equipment through the detection of degradation and the verification that adequate margins are maintained.

3.0 TECHNICAL EVALUATION

The NRC approved Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler-101 (TSTF-101), Revision 0, which revised the auxiliary feedwater (emergency feedwater for Babcock and Wilcox plants) pump test frequency. TSTF-101 revised STS 3.7.5, Auxiliary Feedwater System, to require verifying that the developed head for each emergency feedwater (EFW) pump is greater than or equal to the required head on a frequency set by the IST program instead of every 31 days on a staggered basis. The current CR-3, SR 3.7.5.2 specifies EFW pump head requirements and require testing every 45 days on a staggered test basis. The amendment removes the specific pump head frequency from the SR and requires both pump performance measurement and testing frequency to be in accordance with the IST program. The new test frequency is consistent with the ASME Code requirements. The ASME Code,Section XI requires performance of IST at 3-month intervals, which is comparable to the 45-day frequency on a staggered basis. Based on operating experience, these pump test frequencies confirm operability, trend performance and detect incipient failures by indicating abnormal performance.

The licensees application is based on TSTF-101, Revision 0, which showed that the proposed change meets the relevant NRC regulations and there is reasonable assurance that the health and safety of the public will not be endangered. The NRC approved TSTF-101, Revision 0, as incorporated in NUREG-1430, Volume 1, Revision 3. Based on this review, the NRC staff has established that the requested TS changes are consistent with the current STSs and reflect changes based on TSTF-101, Revision 0. Consequently, the changes satisfy the underlying applicable NRC regulations. Therefore, the staff finds the licensees proposed change to SR 3.7.5.2, to be acceptable.

4.0 STATE CONSULTATION

Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, NRC Senior Project Manager, the State of Florida does not desire notification of issuance of license amendments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The NRC has

previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (73 FR 29163).

Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). 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.

6.0 CONCLUSION

The NRC 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 Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Farideh E. Saba Date: January 9, 2009