ML071840351

Application for License Renewal

ML071840351
Person / Time
Site:	Vogtle
Issue date:	06/27/2007
From:	Stinson L M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-1261
Download: ML071840351 (15)

Text

L. M. Stinson (Mike) Southern Nuclear Vice President Operating Company, Inc.Fleet Operations Support 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 A SOUTHERN June 27, 2007 COMPANY Energy to Serve Your World" Docket Nos.: 50-424 NL-07-1261 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Voatle Electric Generating Plant Units 1 and 2 Application for License Renewal Ladies and Gentlemen:

Pursuant to 10 CFR Part 54, Southern Nuclear Operating Company (SNC) hereby applies for the renewal of the operating licenses for the Vogtle Electric Generating Plant (VEGP), Units 1 and 2.SNC is the licensed operator of VEGP, which it operates for the benefit of Georgia Power Company, Oglethorpe Power Company, Municipal Electric Authority of Georgia, and the City of Dalton, Georgia (collectively, the "owners").

The current license for Unit 1 (Facility Operating License No. NPF-68) expires on January 16, 2027, and the license for Unit 2 (Facility Operating License No. NPF-81) expires on February 9, 2029. By this submittal, SNC seeks to extend the term of each operating license by 20 years beyond the current expiration dates.As of the date of this submittal, VEGP Unit 2 has 18 years of operating experience, instead of 20 years as required by 10 CFR 54.17(c).

By letter dated January 9, 2007, the NRC granted SNC an exemption to the requirements of 10 CFR 54.17(c) for VEGP Unit 2, thus allowing the license renewal application for Unit 2 to be submitted concurrently with the application for Unit 1.The enclosed License Renewal Application contains the information required by the license renewal regulations set forth in 10 CFR Part 54. in addition, it satisfies the environmental regulations set forth in 10 CFR Part 51.As required by 10 CFR 54.21 (b), current licensing basis changes which have a material effect on the content of this application will be identified at least annually while the application is under NRC review, and at least three months prior to the scheduled completion of the NRC review.

U. S. Nuclear Regulatory Commission NL-07-1261 Page 2 Enclosure I provides a single compact disc (CD), formatted in a manner that is consistent with "Guidelines for Electronic Submissions to the Commission," published in the Federal Register on October 10, 2003 at 68 FR 58826.To facilitate NRC review, the following items are also provided:* One (1) CD with the VEGP LRA in electronic format suitable for posting on the NRC web page,* Eighty (80) CDs containing the VEGP LRA, associated boundary drawings, and the Updated Final Safety Analysis Report (Revision

14) for Vogtle Electric Generating Plant in electronic format, and* Five (5) paper copies of the VEGP LRA and associated boundary drawings (four copies sent to NRR and one copy sent to Region II).The boundary drawings are being submitted to aid in the review of the application, and are not part of the application.

Enclosure 2 provides the License Renewal Future Action Commitment List. This list will be updated as required throughout the LRA review process.Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.If you have any questions, please advise.Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY L. M. Stinson Vice President Fleet Operations Support Sworn to and subscribed before me this 51_ day of 2007.N Notary Public _My commission expires: k LMS/JAMIdaj U. S. Nuclear Regulatory Commission NL-07-1261 Page 3

Enclosures:

1. VEGP License Renewal Application

2. License Renewal Future Action Commitment List cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President w/o Enclosures Mr. T. E. Tynan, Vice President

-Vogtle w/o Enclosures Mr. D. H. Jones, Vice President

-Engineering w/o Enclosures Mr. B. J. George, Manager -Nuclear Licensing w/ Enclosures Mr. N. J. Stringfellow, Licensing Supervisor

-Vogtle w/ Enclosures RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator w/ Enclosures Mr. B. K. Singal, NRR Project Manager -Vogtle w/ Enclosures Mr. D. J. Ashley, License Renewal Project Manager -Vogtle w/ Enclosures Mr. G. J. McCoy, Senior Resident Inspector

-Vogtle w/Enclosures State of Georgia Mr. N. Holcomb, Commissioner

-Dept. of Natural Resources w/o Enclosures Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 1 Implement the ACCW System Carbon Steel Component Program as described in A.2.1 Prior to the period B.3.1 VEGP LRA Section B.3.1. of extended operation 2 Implement the Bolting Integrity Program as described in VEGP LRA Section B.3.2. A.2.2 Prior to the period B.3.2 of extended operation 3 Enhance Boric Acid Corrosion Control Program documents to address the effects A.2.3 Prior to the period B.3.3 of borated water leakage onto materials other than steels, including electrical of extended components (e.g., electrical connectors), that are susceptible to boric acid operation corrosion.

4 Implement the Buried Piping and Tanks Inspection Program as described in VEGP A.2.4 Prior to the period B.3.4 LRA Section B.3.4. of extended operation 5 Implement the CASS RCS Fitting Evaluation Program as described in VEGP LRA A.2.5 Prior to the period B.3.5 Section B.3.5. of extended operation 6 Enhance Closed Cooling Water Program documents to indicate the components in A.2.6 Prior to the period B.3.6 each system that are most susceptible to various corrosion mechanisms and to of extended ensure that corrosion monitoring is appropriately accomplished.

operation Page 1 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 7 Implement the External Surfaces Monitoring Program as described in VEGP LRA A.2.8 Prior to the period B.3.8 Section B.3.8. of extended operation 8 Implement the following enhancements to the Fire Protection Program: A.2.9 Prior to the period B.3.9* Wall thickness evaluations will be performed on water suppression piping of extended systems using non-intrusive volumetric testing or visual inspections to ensure operation, except that wall thicknesses are within acceptable limits. Initial wall thickness for sprinkler head evaluations will be performed before the end of the current operating term. replacement or Subsequent evaluations will be performed at plant specific intervals during the testing;period of extended operation.

The plant specific inspection intervals will be determined based on previous evaluations and site operating experience.

Sprinkler head* A sample of sprinkler heads will be inspected using the guidance of NFPA 25 replacement or"Inspection, Testing and Maintenance of Water-Based Fire Protection Systems" testing will be (1998 Edition), Section 2-3.1.1, or NFPA 25 (2002 Edition), Section 5.3.1.1.1.

implemented prior Where sprinkler heads have been in service for 50 years, they will be replaced of 50 years from or representative samples from one or more sample areas will be submitted to time system was a recognized testing laboratory for field service testing. This sampling will be placed in service.performed every 10 years after the initial field service testing. The 50 years of time in service begins when the system was placed in service, not when the plant became operational.

• Fire Protection Program procedures will be revised to provide more detailed instructions for visual inspection of Fire Pump Diesel fuel supply lines for leakage, corrosion, and general degradation while the engine is running during fire suppression system pump tests.Page 2 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 9 Enhance the Flux Thimble Tube Inspection Program by preparing an overall A.2.11 Prior to the period B.3.11 program procedure documenting the Flux Thimble Tube Inspection Program of extended administration and implementing activities credited for license renewal. operation 11 Implement the following enhancements to the Generic Letter 89-13 Program: A.2.12 Prior to the period B.3.12" Develop an overall program procedure for the Generic Letter 89-13 Program to of extended describe the various program activities that comprise Generic Letter 89-13 operation Program and their implementing controls such as chemistry procedures, maintenance activities, scheduled surveillances, or other mechanisms.

• Add inspection of the-NSCW Transfer Pumps' casings and bolting.* Add the NSCW Cooling Tower spray nozzles as a specific item to be inspected during the cooling tower inspection.

Page 3 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 12 Implement the Nickel Alloy Management Program for Non-Reactor Vessel Closure A.2.14 Program B.3.14 Head Penetration Locations as described in VEGP LRA Section B.3.14. implementation to The program will be based on the following commitments:

be completed prior to the period (1) SNC will continue to participate in industry initiatives directed at resolving of extended PWSCC issues, such as owners group programs and the Electric Power operation Research Institute Materials Reliability Program. This is an ongoing commitment.

Numbered items are implemented (2) SNC will comply with applicable NRC Orders. This is an ongoing commitment.

as noted in the (3) SNC will submit a program inspection plan for VEGP that includes item.implementation of applicable Bulletins, Generic Letters, and staff accepted industry guidance.

The inspection plan will be submitted to the staff for review and approval not less than 24 months prior to entering the period of extended operation for VEGP Units 1 and 2.13 The Nickel Alloy Management Program for Reactor Vessel Closure Head A.2.15 Ongoing B.3.15 Penetrations will implement commitments for reactor vessel closure head penetrations associated with nickel alloys from: (1) NRC Orders, Bulletins, and Generic Letters, and;(2) Staff-accepted industry guidelines.

Page 4 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 14 Implement the following enhancements to the Oil Analysis Program: A.2.16 Prior to the period B.3.16" An overall program procedure or guideline will be prepared to formalize the of extended sampling and analysis activities performed.

operation* Viscosity, neutralization number and flash point of lubricating oil samples will be required for components where the oil is changed based on its analyzed condition (instead of being changed on a regular schedule regardless of condition).

• When a lubricating oil sample's particle count exceeds established limits or action levels, analytical ferrography or elemental analysis will be used to identify wear particles or corrosion products for the lubricating oil system components in the scope of license renewal.15 Implement the One-Time Inspection Program as described in VEGP LRA Section A.2.17 Inspections will be B.3.17 B.3.17. performed within a window of ten years immediately preceding the period of extended operation.

Page 5 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 16 Implement the One-Time Inspection Program for ASME Class 1 Small Bore Piping A.2.18 inspections will be B.3.18 as described in VEGP LRA Section B.3.18. performed within a window of ten years immediately preceding the period of extended operation.

17 Implement the One-Time Inspection Program for Selective Leaching as described A.2.19 Inspections will be B.3.19 in VEGP LRA Section B.3.19. performed within a window of ten years immediately preceding the period of extended operation.

18 Enhance the Periodic Surveillance and Preventive Maintenance Activities to include A.2.21 Prior to the period B.3.21 the following:

of extended* Steam Generator Blowdown Secondary Sample Bath Shell inspections operation* Steam Generator Blowdown Corrosion Product Monitor cooler shell inspections

• Potable Water System water heater housing inspections (for the in-scope water heaters)Page 6 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 19 Implement the Piping and Duct Inspection Program as described in LRA Section A.2.22 Prior to the period B.3.22 B.3.22. of extended operation 20 Implement the Reactor Vessel Internals Program as described in LRA Section A.2.24 Program B.3.24 B.3.24. implementation to The program will be based on the following commitments:

be completed prior to the period (1) SNC will participate in the industry program for investigating and managing of extended aging effects on reactor internals.

This is an ongoing commitment.

operation; (2) SNC will evaluate and implement the results of the industry programs, such as Numbered items the Electric Power Research Institute Material Reliability Program, as are implemented applicable to the VEGP reactor internals.

This commitment will be fully as noted in the implemented prior to the period of extended operation.

item.(3) SNC will submit an inspection plan for the VEGP reactor internals to the NRC for review and approval not less than 24 months before entering the period of extended operation for VEGP Units 1 and 2.Page 7 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 21 Implement the following enhancements to the Reactor Vessel Surveillance A.2.25 As noted in the B.3.25 Program: numbered items (1) Prior to removal of the last surveillance capsule in each unit, program documents will be revised to require that tested and untested specimens from all capsules removed from the VEGP reactor vessels remain in storage.(2) Alternate dosimetry will be installed to monitor neutron fluence on the reactor vessel after removal of the last surveillance capsule in that unit. This enhancement will be implemented prior to removal of the last surveillance capsule in each unit.23 Implement the following enhancements to the Structural Monitoring Program: A.2.32 Prior to the period B.3.32" The scope of the Structural Monitoring Program will be expanded to include the of extended additional structures that require monitoring for license renewal. operation" The scope of inspection for structures that require monitoring for license renewal will be clarified.

An area-based inspection will be performed unless a detailed inspection scope is provided." The Structural Monitoring Program scope for hangers and supports will be clarified.

• Program requirements will be revised to include periodic ground water monitoring to confirm that groundwater chemistry remains non-aggressive as defined in NUREG 1801.* Underwater inspection of the NSCW cooling tower basins, including appropriate inspection and acceptance criteria, will be added to the Structural Monitoring Program.Page 8 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 24 Enhance the Structural Monitoring Program -Masonry Walls to include monitoring A.2.33 Prior to the period B.3.33 of masonry walls in the structures that are in scope for license renewal, but are not of extended currently monitored under the program. operation 25 Implement the Non-EQ Cables and Connections Program as described in LRA A.2.34 Implement B.3.34 Section B.3.34. program and complete first inspection prior to the period of extended operation 26 Implement the Non-EQ Inaccessible Medium-Voltage Cables Program as described A.2.35 Implement B.3.35 in LRA Section B.3.35. program and complete first inspection prior to the period of extended operation Page 9 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 27 Implement the Non-EQ Cable Connections One-Time Inspection Program as A.2.36 Inspections will be B.3.36 described in LRA Section B.3.36. performed within a window of ten years immediately preceding the period of extended operation.

28 Implement the following enhancements to the Fatigue and Cycle Monitoring A.2.38 Prior to the period B.3.38 Program: of extended" Implementing documents will be revised to address the effect of the full operation structural weld overlays applied to the pressurizer spray and surge nozzles on the stress-based module calculation of CUF.* The VEGP UFSAR will be revised to require fatigue monitoring of the Accumulator/RHR nozzles and pressurizer heater penetrations.

• Implementing documents will be revised to reduce acceptable CUF values to account for environmental fatigue effects for those NUREG-6260 locations monitored for fatigue.* Implementing documents will be revised to explicitly require that the corrective actions initiated for exceeding an acceptance criterion include a review to identify and assess any additional affected reactor coolant pressure boundary locations.

Page 10 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 29 To ensure that the fatigue cycle limits are not exceeded, SNC will replace the A.3.2.5 As stated in the 4.3.5 steam generator secondary side handhole bolts after 30 years of service. The commitment B.3.2 handhole bolts have been previously replaced and are scheduled to be replaced again during the spring outages in 2026 and 2028 for Units 1 and 2, respectively.

Alternatively, a less restrictive replacement schedule may be developed and documented based on updated analyses initiated by the Bolting Integrity Program.30 To ensure that the fatigue cycle limits are not exceeded, SNC will replace the A.3.2.5 As stated in the 4.3.5 steam generator secondary side manway bolts after 30 years of service. The commitment B.3.2 manway bolts have never been replaced and are scheduled for replacement during the spring outages in 2017 and 2019 for Units 1 and 2, respectively.

Alternatively, a less restrictive replacement schedule may be developed and documented based on updated analyses initiated by the Bolting Integrity Program.31 The VEGP Pressure-Temperature Limits Report (for each unit) will be updated to A.3.1.5 Prior to the unit 4.2.5 address neutron embrittlement for a 60-year operating life, including any changes A.3.6.4 entering the 4.7.4 to the cold-overpressure mitigation system setpoints.

period of extended operation Page 11 of 12 Enclosure 2 NL-07-1261 VEGP License Renewal Future Action Commitment List ITEM UFSAR RELATED NO. COMMITMENT SUPPLEMENT SCHEDULE LRA LOCATION SECTIONS/REFS 32 Implement a replacement schedule for the small diameter (< 2-inch) flexible hoses None Prior to the period described below: of extended* Radiation Monitoring System flexible hoses associated with the vent stack operation 2.3.3.25 radiation monitor sample line.* Emergency Diesel Generator System flexible hoses associated with the fuel oil 2.3.3.20 supply lines from the fuel oil headers to the fuel injector pumps.* ACCW System flexible hoses associated with the normal charging pump motor 2.3.3.6 coolers.* Hydrogen Recombiner and Monitoring System flexible hoses associated with 2.3.3.20 the calibration gas and oxygen bottles." Main Steam System flexible hoses between the ARV hydraulic actuator and the 2.3.4.1 hand pump unit.* Drain System flexible hoses installed on the Containment Bldg Tendon Gallery 2.3.3.23 Sump Pump discharge lines.* Fire Protection System flexible hoses associated with the fire pump diesel fuel 2.3.3.19 oil system.33 Ensure the fatigue monitoring limits implemented as part of the Fatigue and Cycle A.3.2.1 Prior to the period 4.3.1.7 Monitoring Program are adequate to ensure that charging and letdown intermediate of extended break location CUF values remain less than 0.1 for 60 years of operation.

operation Page 12 of 12