ML12205A007
| ML12205A007 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 07/12/2012 |
| From: | Hartz L Dominion Energy Kewaunee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 12-423 | |
| Download: ML12205A007 (8) | |
Text
Do'minion Energy Kewaunee, Inc. m inion 5000 Dominion Boulevard, Glen Allen, VA 23060 D July 12, 2012 ATTN: Document Control Desk Serial No.12-423 U. S. Nuclear Regulatory Commission LIC/JG/RO Washington, DC 20555-0001 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION INSERVICE INSPECTION PROGRAM FOURTH TEN-YEAR INTERVAL LIMITATION TO EXAMINATION RELIEF REQUEST NO. RR-G-5 SUPPLEMENT AND RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION By application dated September 28, 2011 (Reference 1), Dominion Energy Kewaunee, Inc. (DEK), requested approval, pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii),
of relief request RR-G-5 for the Fourth Ten-year Interval of the Inservice Inspection (ISI)
Program for Kewaunee Power Station (KPS). That submittal requested relief from inspecting those areas that either could not be examined in accordance with American Society of Mechanical Engineers (ASME)Section XI Code requirements or could not be examined without significant modifications to the plant. The initial submittal was supplemented on May 9, 2012 (Reference 2).
Subsequently, the Nuclear Regulatory Commission (NRC) staff transmitted a request for additional information (RAI) regarding the relief request (Reference 3).- The RAI questions and associated DEK responses are provided in Attachment 1 to this letter.
The NRC staff also noted that the supplemental submittal (Reference 2), which discussed two Category B-J, Item 9.31, pipe branch connection welds (RC-W3BC and RC-W34BC), contained a note stating "RC-W3BC and RC-W34BC - 50% Limitation Relief Request is expected to be submitted at the end of the 3 rd Period examinations."
Note that RC-W34BC is a substitute for RC-W22BC. Because these welds will be the subject of a future relief request, DEK is removing them from the current submittal.
Specifically, DEK hereby revises Reference 1 by requesting withdrawal of the following two relief requests:
- RR-G-5-8: 8" Reactor Coolant Pipe Branch Connection Weld RC-W3BC
- RR-G-5-9: 6" Reactor Coolant Pipe Branch Connection Weld RC-W22BC No further consideration should be afforded to the two specific relief requests listed above.
467
Serial No.12-423 Relief Request RR-G-5 Response to RAI's Page 2 of 3 If you have questions or require additional information, please feel free to contact Mr.
Jack Gadzala at 920-388-8604.
Very truly yours, Leslie N. Hartz Vice President - Nuclear Support Services
Attachment:
- 1. Response to Request for Additional Information, Relief Request No. RR-G-5
References:
- 1. Letter from J. Alan Price (DEK) to Document Control Desk (NRC), "Inservice Inspection Program Fourth Ten-Year Interval Limitation to Examination Relief Request No. RR-G-5," dated September 28, 2011.
- 2. Letter from J. Alan Price (DEK) to Document Control Desk (NRC), "Inservice Inspection Program Fourth Ten-Year Interval Limitation to Examination Relief Request No. RR-G-5 Supplement and Response to Request for Additional Information," dated May 9, 2012.
"ME7378 - Kewaunee - Relief Req. RR-G-5-1 to -40 Request for Additional Information (RAI) - second round," dated June 17, 2012.
Commitments made by this letter: NONE
Serial No.12-423 Relief Request RR-G-5 Response to RAI's Page 3 of 3 cc: Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. Karl D. Feintuch, Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station
Serial No.12-423 ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. RR-G-5 FOURTH TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM (JUNE 16, 2004- JUNE 16, 2014) 1ST PERIOD AND 2ND PERIOD KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Serial No.12-423 Attachment 1 Page 1 of 4 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. RR-G-5 On June 17, 2012, the NRC transmitted a request for additional information (RAI)
(Reference 1) to Dominion Energy Kewaunee (DEK) concerning Request for Relief (RR) RR-G-05. RR-G-05 requests relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," for Kewaunee Power Station (KPS).
The RAI questions are provided below, followed by the DEK response.
NRC Question ME7378-RAII-EPNB-McL-007-2012-07-09
Background
There are two risk-informed program methodologies that are generally accepted for use by the NRC. They have been developed by the Electrical Power Research Institute (EPRI) and the Westinghouse Owners Group (WOG) and are documented in Topical Report TR-1 12657, Revised Risk-Informed Inservice Inspection Evaluation Procedure, Revision B-A, and Topical Report WCAP-14572, Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report, Revision 1-NP-A, respectively. The two programs use either ASME Code Case N-578-11, Risk-Informed Requirements for Class 1, 2 or 3 Piping, Method B Section X1, or Code Case N-577 1, Risk-Informed Requirements for Class 1, 2 or 3 Piping, Method A, both of which assign a new Examination Category R-A, listing welds, or other elements, according to expected forms of degradation.
The Kewaunee Risk-Informed Inservice Inspection (RI-ISI) program is based on the NRC-approved EPRI Topical Report TR-112657, Rev B-A. The NRC approved the Kewaunee RI-ISI program plan in its safety evaluation dated September 23, 2005 (Agencywide Documents Access & Management System (ADAMS) Accession Number ML052660057)
RAI Item McL-001 To ensure an efficient review and to clarify the Kewaunee RI-ISI program ranking of the subject welds submitted for relief from the ASME Code-required examination coverage, please provide the equivalent ranking of the Kewaunee RI-ISI program that is applicable
- 1. ASME Code Cases N-577-1 or N-578-1 are not approved for use in RG-1.147, Revision 16. Licensees base their RI-ISI inspection sample size and examination methodology on Table 1 of ASME Code Case N-577-1 or N-578-1.
Serial No.12-423 Attachment 1 Page 2 of 4 or equal to that of ASME Code, Item R-A and "damage mechanisms" in the enclosed tables below: [Table Template provided in NRC request.]
Response
The requested information is provided in the table below:
i-h bb.4U I-'K-VV1 UM h'l- fU- Nozzie-to-baTe tflO None K1 .ZU B-F B5.40 PR-W26DM PZR 6" Nozzle-to-Safe End 37.0% None R1.20 B-F B5.40 RC-W67DM PZR 14" Nozzle-to-Safe End 26.0% Thermal R1.11 Transient (TT)
B-J B9.11 PR-W27 6" PZR Relief Circumferential Weld 50.0% None R1.20 B-J B9.11 RC-W60 6" Reactor Coolant Circumferential Weld 50.0% Thermal R1.11 Transient (TT)
B-J B9.11 SI-W51 6" Safety Injection Circumferential Weld 86.7% None R1.20 B-J B9.11 RHR-W9 8" Residual Heat Removal Circumferential Weld 50.0% None R1.20 Thermal Transient (TT) R1.11 B-J B9.11 SI-W74 12" Safety Injection Circumferential Weld 50.0% and Intergranular and Stress Corrosion R1.16 Cracking (IGSCC)
B-J B9.31 RC-W3BC 8" Reactor Coolant Pipe Branch Connection 27.0% Withdrawn B-J B9.31 RC-W22BC 6" Reactor Coolant Pipe Branch Connection 50.0% Withdrawn C-F-1 C5.13 ICS-W180 6" Containment Spray Circumferential Weld 50.0% None R1.20 C-F-1 C5.13 ICS-W181 6" Containment Spray Circumferential Weld 50.0% None R1.20 C-F-1 C5.13 RHR-W419 6" Residual Heat Removal Circumferential Weld 50.0% None R1.20 C-F-1 C5.13 ICS-W45 8" Containment Spray Circumferential Weld 50.0% None R1.20
Serial No.12-423 Attachment 1 Page 3 of 4 C-F-1 C5.14 SI-W429 6" Safety Injection Circumferential Weld 50.0% None R1.20 C-F-1 C5.21 SI-W249 3" Safety Injection circumferential Weld 50.0% None R1.20 C-F-1 C5.21 AFW-W148 3" Auxiliary Feedwater Circumferential Weld 50.0% None R1.20 C-F-1 C5.21 AFW-W151 3" Auxiliary Feedwater Circumferential Weld 50.0% None R1.20 C-F-1 C5.21 AFW-W152 3" Auxiliary Feedwater Circumferential Weld 50.0% None R1.20 C-F-1 C5.21 AFW-W155 3" Auxiliary Feedwater Circumferential Weld 50.0% None R1.20 C-F-2 C5.61 AFW-W156 3" Auxiliary Feedwater Circumferential Weld 68.0% None R1.20 C-F-2 C5.61 AFW-W171 3" Auxiliary Feedwater Circumferential Weld 85.0% None R1.20 C-F-2 C5.61 AFW-W172 3" Auxiliary Feedwater Circumferential Weld 63.0% None R1.20 C-F-2 C5.61 AFW-W178 3" Auxiliary Feedwater Circumferential Weld 83.0% None R1.20 C-F-2 C5.61 AFW-W189 3" Auxiliary Feedwater Circumferential Weld 87.0% None R1.20 C-F-2 C5.61 AFW-W190 3" Auxiliary Feedwater Circumferential Weld 87.0% None R1.20 C-F-2 C5.61 AFW-W191 3" Auxiliary Feedwater Circumferential Weld 85.0% None R1.20 C-F-2 C5.61 AFW-W192 3" Auxiliary Feedwater Circumferential Weld 83.0% None R1.20 C-F-2 C5.61 AFW-W194 3" Auxiliary Feedwater Circumferential Weld 67.0% Withdrawn C-F-2 C5.61 AFW-W195 3" Auxiliary Feedwater Circumferential Weld 85.0% None R1.20 C-F-2 C5.61 AFW-W196 3" Auxiliary Feedwater Circumferential Weld 62.0% Withdrawn C-F-2 C5.61 AFW-W197 3" Auxiliary Feedwater Circumferential Weld 67.0% Withdrawn C-F-2 C5.61I AFW-W198 3" Auxiliary Feedwater Circumferential Weld 62.0% Withdrawn
Serial No.12-423 Attachment 1 Page 4 of 4
Reference:
"ME7378 - Kewaunee - Relief Req RR-G-5-1 to -40 Request for Additional Information (RAI) - second round," dated June 17, 2012.