ML063470063

License Amendment, Change of Emergency Diesel Generator Required Action 3.8.1.B.4 Completion Time from 14 Days to 7 Days

ML063470063
Person / Time
Site:	Browns Ferry
Issue date:	01/26/2007
From:	Chernoff M NRC/NRR/ADRO/DORL/LPLII-2
To:	Singer K Tennessee Valley Authority
Chernoff M, NRR/DORL, 415-4041
Shared Package
ML063470066	List: ML063470063 ML070300616
References
TAC MD3404, TAC MD3405
Download: ML063470063 (12)

Text

January 26, 2007 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 - ISSUANCE OF AMENDMENTS REGARDING CHANGE OF EMERGENCY DIESEL GENERATOR REQUIRED ACTION 3.8.1.B.4 COMPLETION TIME FROM 14 DAYS TO 7 DAYS (TAC NOS. MD3404 AND MD3405) (TS-457)

Dear Mr. Singer:

The Commission has issued the enclosed Amendment Nos. 298 and 256 to Renewed Facility Operating Licenses Nos. DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units 2 and 3, respectively. These amendments are in response to your application dated October 26, 2006.

The amendments revise Technical Specification Required Action 3.8.1.B.4 for Browns Ferry Nuclear Plant Units 2 and 3. The revision changes the restoration time of an inoperable Emergency Diesel Generator from 14 to 7 days.

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA by B. Mozafari for/

Eva A. Brown, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-260 and 50-296

Enclosures:

1. Amendment No. 298 to License No. DPR-52

2. Amendment No. 256 to License No. DPR-68

3. Safety Evaluation cc w/enclosures: See next page

ML063470063 NRR-058 OFFICE LPL2-2 LPL2-2/PM LPL2-2/LA ITSB/BC DE/EEEA/BC OGC LPL2-2/BC NAME MGutierrez EBrown BClayton TKobetz GWilson SHamrick MChernoff for LRaghavan DATE 12/15/06 12/15/06 12/14/06 12/15/06 12/15/06 12/20/06 1/26/07

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 298 Renewed License No. DPR-52

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated October 26, 2006, 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 Renewed Facility Operating License No. DPR-52 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 298, are hereby incorporated in the license. The licensee 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 from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by M. Chernoff for/

L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Operating License Date of Issuance: January 26, 2007

ATTACHMENT TO LICENSE AMENDMENT NO. 298 RENEWED FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Replace Page 3 of Renewed Operating License DPR-52 with the attached Page 3.

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 marginal lines indicating the areas of change.

REMOVE INSERT 3.8-3 3.8-3

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 256 Renewed License No. DPR-68

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated October 26, 2006, 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 Renewed Facility Operating License No. DPR-68 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 256, are hereby incorporated in the license. The licensee 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 from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by M. Chernoff for/

L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Operating License Date of Issuance: January 26, 2007

ATTACHMENT TO LICENSE AMENDMENT NO. 256 RENEWED FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Replace Page 3 of Renewed Operating License DPR-68 with the attached Page 3.

Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3.8-3 3.8-3

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 298 TO FACILITY OPERATING LICENSE NO. DPR-52 AND AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 DOCKET NOS. 50-260 AND 50-296

1.0 INTRODUCTION

By letter dated October 26, 2006, the Tennessee Valley Authority (TVA, the licensee) submitted a request for changes to the Browns Ferry Nuclear Plant (BFN), Units 2 and 3 Technical Specifications (TSs). The requested changes would revise the completion time for technical specification Required Action 3.8.1.B.4 from 14 days to 7 days for restoration of an inoperable Emergency Diesel Generator (EDG).

2.0 REGULAORY EVALUATION Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The Commissions regulatory requirements related to the content of the TSs are contained in Title 10, Code of Federal Regulations (10 CFR) Section 50.36 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. The requirements for system operability during movement of irradiated fuel are included in the TS in accordance with 10 CFR 50.36(c)(2), Limiting Conditions for Operation.

3.0 TECHNICAL EVALUATION

Plant auxiliary power for each unit at BFN is provided by the main generator through each unit's station service transformers during normal plant operation. If the unit is not operating, the plant power is provided from the 500-kilovolt (kV) switchyard (immediate offsite power source) through the main transformer and the unit station service transformers. Power is also available from the 161-kV system via the two common station service transformers (delayed offsite power source). In the event that all preferred offsite circuits from the 500-kV switchyard become unavailable, then it will result in an automatic transfer of safety-related loads to the common station service transformers. When no offsite power is available, safety-related loads will transfer to the EDGs.

TVA has a total of eight EDGs at the site for the purpose of providing standby power. Although any EDG could be aligned to any unit, four EDGs are normally dedicated to Units 1 and 2 and four are dedicated to Unit 3. All EDGs were manufactured by General Motors Electromotive Division and were deemed to comply with BFNs licensing basis. That determination included the acceptance of a 7-day completion time to perform TS Required Action 3.8.1.B.4. The 7-day completion time took into account the capacity and capability of the remaining ac sources, reasonable time for repairs, and low probability of a DBA occurring during this period.

TVA applied to extend the 7-day completion time to 14 days by letter dated March 12, 1997, as supplemented by letters dated March 30, 1999, April 23, 1999, and June 18, 1999. The extension was granted by the NRC through letter dated August 2, 1999, (Amendment Nos. 259 and 218). The decision to grant completion time extension was partly based on Unit 1 being shutdown. As a result of TVAs decision to restart Unit 1, the 14-day allowed outage time (AOT) is no longer valid. Therefore TVA is requesting to revise the completion time from 14 days to 7 days.

Unit 1 restart does not change the number of off-site power sources or the reliability of each source. Diesel generator (DG) capability and reliability is also not changed. In addition, the physical configuration of the standby ac supply and distribution system interconnects at the various levels of the electrical supply system is not changed.

Additionally, previous work experience indicates that shorter EDG outages can be achieved by performing preventive maintenance while operating. Scheduled maintenance on the DGs is conducted as recommended by the manufacturer. A 7-day AOT is generally sufficient to accommodate scheduled and unscheduled EDG maintenance.

For the reasons discussed above, the NRC staff finds the revision of completion time of Action 3.8.1.B.4 from 14 to 7 days acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Alabama State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change 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 amendments involve 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 Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (71 FR 67398). Accordingly, the amendments meet 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 amendments.

6.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: M. Gutierrez Date: January 26, 2007

Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:

Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Preston D. Swafford, Senior Vice President Nuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 General Counsel Tennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902 Mr. John C. Fornicola, General Manager Nuclear Assurance Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Bruce Aukland, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Robert G. Jones, General Manager Browns Ferry Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. William D. Crouch, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Mr. Robert H. Bryan, Jr., General Manager Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 - ISSUANCE OF AMENDMENTS REGARDING CHANGE OF EMERGENCY DIESEL GENERATOR REQUIRED ACTION 3.8.1.B.4 COMPLETION TIME FROM 14 DAYS TO 7 DAYS(TAC NOS. MD3404 AND MD3405)

Dated: January 26, 2007 Distribution:

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