ML062770301

Transmittal of Wolf Creek, Application for Renewed Operating License

ML062770301
Person / Time
Site:	Wolf Creek
Issue date:	09/27/2006
From:	Garrett T Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ET 06-0038
Download: ML062770301 (12)

Text

Terry J. Garrett Vice President, Engineering ET 06-0038 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: Application for Renewed Operating License Gentlemen:

Pursuant to Code of Federal Regulations, Title 10, Parts 50, 51 and 54, Wolf Creek Nuclear Operating Corporation (WCNOC) hereby requests the renewal of Facility Operating License Number NPF-42 for the Wolf Creek Generating Station (WCGS), Unit No. 1.

The current Operating License for WCGS expires at midnight, March 11, 2025. WCNOC requests that the WCGS Operating License be extended for 20 years beyond the current expiration date to midnight, March 11, 2045.

The enclosed License Renewal Application contains the information required by 10 CFR Part 54 for filing an application and the application meets the timeliness requirements of 10 CFR 54.17(c) and 10 CFR 2.109(b).

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.

Attachment II provides a summary of commitments made in this application. Implementation of new programs may require additional action items not included in this list. WCGS is committed to including new program elements in the corrective action program.

The Enclosure provides the CD-ROM submittal of the WCGS License Renewal Application in accordance with 10 CFR 2 Subpart A, 10 CFR 50.4, and 10 CFR 50.30.

ET 06-0038 Page 2 of 2 If you have any questions concerning this matter, please contact me at (620) 364-4084, or Mr.

Kevin Moles at (620) 26.

Very truly yours,

Attachment:

I - Oath

- List of Regulatory Commitments

Enclosure:

License Renewal Application cc: J. N. (NRC), wle G.E. Werner (NRC),

B. S. (NRC),

Senior Resident Inspector (NRC),

Attachment I to ET 06-0038 Page 1 of 1 STATE OF KANSAS COUNTY OF COFFEY Terry J. Garrett, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

Vice Engineering SUBSCRIBED and sworn to before me day 2006.

Notary Public I MY COMMISSION EXPIRES January 11,2010 Expiration Date

Attachment II to ET 06-0038 Page 1 of 8 LIST OF REGULATORY COMMITMENTS The following table identifies a summary of those actions committed to by Wolf Creek Nuclear Operating Corporation (WCNOC) in this License Renewal Application (LRA). All commitments have a due date of March 11, 2025. Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions regarding these commitments to Mr. Kevin Moles at (620) 364-4126.

COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section Boric Acid Corrosion Program A1.4 Prior to the period of extended operation, procedures will be (RCMS 2006-198) enhanced to state that susceptible components adjacent to potential leakage sources will include electrical components and connectors.

Nickel-Alloy Penetration A1.5 Prior to the period of extended Nozzles Welded To The Upper operation, procedures will be Reactor Vessel Closure Heads enhanced to indicate that detection of of Pressurized Water Reactors leakage or evidence of cracking in the vessel head penetration nozzles or (RCMS 2006-199) associated welds will cause an immediate reclassification to the "High" susceptibility ranking, commencing from the same outage in which the leakage or cracking is detected.

Closed-Cycle Cooling Water A1.10 Prior to the period of extended System operation, a new periodic preventive maintenance activity will be developed (RCMS 2006-200) to specify performing inspections of the internal surfaces of valve bodies and accessible piping while the valves are disassembled for operational readiness inspections to detect loss of material and fouling.

Inspection of Overhead Heavy A1.11 Prior to the period of extended Load and Light Load (Related operation, procedures will be to Refueling) Handling enhanced to: (1) identify industry Systems standards or Wolf Creek Generating Station (WCGS) specifications that (RCMS 2006-201) are applicable to the component, and (2) specifically inspect for loss of material due to corrosion or rail wear.

Attachment II to ET 06-0038 Page 2 of 8 COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section Fire Protection A1.12 Prior to the period of extended operation: (1) fire damper inspection (RCMS 2006-202) and drop test procedures will be enhanced to inspect damper housing for signs of corrosion, (2) fire barrier and fire door inspection procedures will be enhanced to specify fire barriers and doors described in USAR Appendix 9.5A, "WCGS Fire Protection Comparison to APCSB 9.5-1 Appendix A", and WCGS Fire Hazards Analysis, and (3) training for technicians performing the fire door and fire damper visual inspection will be enhanced to include fire protection inspection requirements and training documentation.

Fuel Oil Chemistry A1.14 Prior to the period of extended operation: (1) the emergency fuel oil (RCMS 2006-203 day tanks will be added to the ten year drain, clean, and internal inspection program, and (2) procedures will be enhanced to provide for supplemental ultrasonic thickness measurements if there are indications of reduced cross sectional thickness found during the visual inspection of the emergency fuel oil storage tanks.

One-Time Inspection A1.16 The One-Time Inspection program conducts one-time inspections of (RCMS 2006-204) plant system piping and components to verify the effectiveness of the Water Chemistry program (A1.2), Fuel Oil Chemistry program (A1.14), and Lubricating Oil Analysis program (A1.23).This new program will be implemented and completed within the ten-year period prior to the period of extended operation.

Selective Leaching of Materials A1.17 The Selective Leaching of Materials program is a new program that will be (RCMS 2006-205) implemented prior to the period of extended operation.

Attachment II to ET 06-0038 Page 3 of 8 COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section Buried Piping and Tanks A1.18 The Buried Piping and Tanks Inspection Inspection program is a new program that will be implemented prior to the (RCMS 2006-206) period of extended operation. Within the ten-year period prior to entering the period of extended operation, an opportunistic or planned inspection will be performed. Upon entering the period of extended operation a planned inspection within ten years will be required unless an opportunistic inspection has occurred within this ten-year period.

One-Time Inspection of ASME A1.19 The fourth interval of the ISI program Code Class 1 Small-Bore at WCGS will provide the results for Piping (RCMS 2006-207) the one time inspection of ASME Code Class 1 small-bore piping.

Inspection of Internal Surfaces A1.22 The Inspection of Internal Surfaces in in Miscellaneous Piping and Miscellaneous Piping and Ducting Ducting Components Components program is a new program that will be implemented prior (RCMS 2006-208) to the period of extended operation.

For those systems or components where inspections of opportunity are insufficient, an inspection will be conducted prior to the period of extended operation to provide reasonable assurance that the intended functions are maintained.

Electrical Cables and A1.24 The Electrical Cables and Connections Not Subject to 10 Connections Not Subject to 10 CFR CFR 50.49 Environmental 50.49 Environmental Qualification Qualification Requirements Requirements program is a new program that will be implemented prior (RCMS 2006-209) to the period of extended operation.

Electrical Cables Not Subject A1.25 A review of the calibration surveillance to 10 CFR 50.49 test results will be completed before Environmental Qualification the period of extended operation and Requirements Used in every 10 years thereafter.

Instrumentation Circuits (RCMS 2006-210)

Attachment II to ET 06-0038 Page 4 of 8 COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section Inaccessible Medium Voltage A1.26 The Inaccessible Medium Voltage Cables Not Subject to 10 CFR Cables Not Subject to 10 CFR 50.49 50.49 Environmental Environmental Qualification Qualification Requirements Requirements program is a new program that will be implemented prior (RCMS 2006-211) to the period of extended operation.

ASME Section XI, Subsection A1.28 Prior to the period of extended IWL operation, procedures will be enhanced to include two new (RCMS 2006-212) provisions regarding inspection of repair/replacement activities. The 2003 edition of ASME Section XI, Subsection IWL, Article IWL-2000, includes two provisions that are not required by the 1998 edition. IWL-2410(d) specifies additional inspections for concrete surface areas affected by a repair/replacement activity, and IWL-2521.2 specifies additional inspections for tendons affected by a repair/replacement activity. In accordance with 10 CFR 50.55a, WCGS will revise their CISI program prior to the next inspection interval to incorporate the ASME Code edition and addenda incorporated into 10 CFR 50.55a at that time.

Masonry Wall Program A1.31 Prior to the period of extended operation, procedures will be (RCMS 2006-213) enhanced to identify un-reinforced masonry in the Radwaste Building within the scope of license renewal that requires aging management.

Structures Monitoring Program A1.32 Prior to the period of extended operation, procedures will be (RCMS 2006-214) enhanced to add inspection parameters for treated wood.

Attachment II to ET 06-0038 Page 5 of 8 COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section RG 1.127, Inspection of Water- A1.33 Prior to the period of extended Control Structures Associated operation, procedures will be with Nuclear Power Plants enhanced: (1) so that the main dam service spillway and the auxiliary (RCMS 2006-215) spillway will be inspected in accordance with the same specification, (2) to clarify the scope of inspections for the spillways, (3) to add the 5 year inspection frequency for the main dam service spillway, and (4) to add cavitation to the list of concrete aging effects for surfaces other than spillways.

Reactor Coolant System A1.35 WCNOC will:

Supplement A. Reactor Coolant System Nickel (RCMS 2006-216) Alloy Pressure Boundary Components Implement applicable (1) NRC Orders, Bulletins and Generic Letters associated with nickel alloys and (2) staff-accepted industry guidelines, and B. Reactor Vessel Internals (1) Participate in the industry programs for investigating and managing aging effects on reactor internals; (2) evaluate and implement the results of the industry programs as applicable to the reactor internals; and (3) upon completion of these programs, but not less than 24 months before entering the period of extended operation, WCNOC will submit an inspection plan for reactor internals to the NRC for review and approval.

Electrical Cable Connections A1.36 Prior to the period of extended Not Subject To 10 CFR 50.49 operation, the infrared thermography Environmental Qualification testing procedure will be enhanced to Requirements require an engineering evaluation when test acceptance criteria are not (RCMS 2006-217) met. This engineering evaluation will include identifying the extent of condition, the potential root cause for not meeting the test acceptance, and the likelihood of recurrence.

Attachment II to ET 06-0038 Page 6 of 8 COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section Metal Fatigue of Reactor A2.1 Prior to the period of extended Coolant Pressure Boundary operation, the Metal Fatigue of Reactor Coolant Pressure Boundary (RCMS 2006-218) program will be enhanced to include:

(1) Action levels to ensure that if the fatigue usage factor calculated by the code analysis is reached at any monitored location, appropriate evaluations and actions will be invoked to maintain the analytical basis of the leak-before-break (LBB) analysis and of the high-energy line break (HELB) locations, or to revise them as required, (2) Action levels to ensure that appropriate evaluations and actions will be invoked to maintain the bases of safety determinations that depend upon fatigue analyses, if the fatigue usage factor at any monitored location approaches 1.0, or if the fatigue usage factor at any monitored NUREG/CR6260 location approaches 1.0 when multiplied by the environmental effect factor FEN, (3)

Corrective actions, on approach to these action levels, that will determine whether the scope of the monitoring program must be enlarged to include additional affected reactor coolant pressure boundary locations in order to ensure that additional locations do not approach the code limit without an appropriate action, and to ensure that the bases of the LBB and HELB analyses are maintained, (4) 10 CFR 50 Appendix B procedural and record requirements. Prior to the period of extended operation, changes in available monitoring technology or in the analyses themselves may permit different action limits and action statements, or may re-define the program features and actions required to address the fatigue time-limited aging analyses (TLAAs).

Attachment II to ET 06-0038 Page 7 of 8 COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section Environmental Qualification of A2.2 Prior to the period of extended Electrical Components operation, program documents will be enhanced to describe methods that (RCMS 2006-219) may be used for qualified life evaluations for the period of extended operation.

Concrete Containment Tendon A2.3 Prior to the period of extended Prestress operation, procedures will be revised to: (1) extend the list of surveillance (RCMS 2006-220) tendons to include random samples for the year 40, 45, 50, and 55 year surveillances, (2) explicitly require a regression analysis for each tendon group after every surveillance, (3) invoke and describe regression analysis methods used to construct the lift-off trend lines, (4) extend surveillance program predicted force lines for the vertical and hoop tendon groups to 60 years, and (5) conform procedure descriptions of acceptance criteria action levels to the ASME Code, Subsection IWL 3221 descriptions.

ASME III Subsection NG A3.2.2 WCNOC will obtain a design report Fatigue Analysis of Reactor amendment to either quantify the Pressure Vessel Internals increase in high-cycle fatigue effects, or to confirm that the increase will be (RCMS 2006-221) negligible. WCNOC will complete this action before the end of the current licensed operating period.

Assumed Thermal Cycle Count A3.2.4 WCNOC will complete the reanalysis for Allowable Secondary Stress of the reactor coolant sample lines Range Reduction Factor in and any additional corrective actions B31.1 and ASME III Class 2 or modifications indicated by them, and 3 Piping (RCMS 2006-222) before the end of the current licensed operating period.

USAR Supplement A0 Following issuance of the renewed operating license in accordance with (RCMS 2006-223) 10 CFR 50.71(e), WCNOC will incorporate the USAR supplement into the WCGS USAR as required by 54.21(d).

Pressure-Temperature (P-T) A3.1.3 WCNOC will revise the Pressure and Limits (RCMS 2006-224) Temperature Limits Report for a 60-year licensed operating life.

Attachment II to ET 06-0038 Page 8 of 8 COMMITMENT LRA, Appendix COMMITMENT DESCRIPTION SUBJECT A, Section Implementation of New N/A Implementation of new programs may Programs require additional action items not included in this list. WCGS is (RCMS 2006-225) committed to including new program elements in the corrective action program.

Enclosure to ET 06-0038 Page 1 of 1 Subject Enclosed is the CD-ROM submittal of the Wolf Creek License Renewal Application.

Contact Name Kevin Moles Mailing Address Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 E-Mail Address kemoles@wcnoc.com Phone Number 620-364-4126 Document Components:

The CD-ROM labeled Wolf Creek License Renewal Application contains the following files:

License Renewal Application Transmittal Letter; WCNOC_Xmttl.pdf (publicly available)

License Renewal Application; WCNOC_LRA.pdf (publicly available)

Environmental Report; WCNOC_AppE.pdf (publicly available)

License Renewal boundary drawings; WCNOC_Dwg.pdf (publicly available)