ML14230A757
| ML14230A757 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/21/2014 |
| From: | Lyon C Plant Licensing Branch IV |
| To: | Heflin A Wolf Creek |
| Lyon C | |
| References | |
| TAC MF4305 | |
| Download: ML14230A757 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 21, 2014 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION-REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST FOR ALTERNATIVE 13R-10 (TAC NO. MF4305)
Dear Mr. Heflin:
By letter dated June 26, 2014, Wolf Creek Nuclear Operating Corporation (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) for approval request for alternative 13R-10 for the Wolf Creek Generating Station. The licensee proposed an alternative to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, IWB-5220, for the third 1 0-year interval of the inservice inspection program.
The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to Mr. S. Wideman of your staff on August 18, 2014. Please provide a response to the enclosed questions within 45 days of the date of this letter.
If you have any questions, please contact me at 301-415-2296 or via e-mail at fred.lyon@nrc.gov.
Docket No. 50-482 Enclosure Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR ALTERNATIVE 13R-10 TO ASME CODE REQUIREMENTS WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 By letter dated June 26, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14182A087), Wolf Creek Nuclear Operating Corporation (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) for approval request for alternative 13R-10 for the Wolf Creek Generating Station. The licensee proposed an alternative to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWB-5220, for the third 1 0-year interval of the inservice inspection (lSI) program.
The NRC staff requests the following additional information in order to complete its review of the request.
- 1.
For each pipe segment under consideration (i.e., Portion 1 through Portion 6 piping listed in Section 1.0 of Attachment to 13R-1 0), please provide the applicable examination category and item number as specified in Table IWB-2500-1,Section XI of the ASME Code.
- 2.
Please clarify if any area(s) of Portion 1 through 6 piping in 13R-1 0 are insulated or inaccessible. If yes, discuss whether IWA-5241 (b) and IWA-5242(b) will be followed. If these two subarticles will not be followed, discuss how the licensee will perform the VT-2 visual examination of the insulated or inaccessible area(s).
- 3.
Please discuss whether there are any welded connections (e.g., butt or socket) in the pipe segments under consideration (i.e., Portion 1 through Portion 6 piping listed in Section 1.0 of Attachment to 13R-1 0). If yes, (a) discuss whether any of the welds have been examined by volumetric or surface examinations during the current 1 0-year lSI interval, and whether any weld(s) is in the risk-informed lSI program and has been or will be examined in the current 10-year lSI interval. (b) Discuss whether any pressure boundary leakage was identified during the current 1 0-year lSI interval in each pipe segment under consideration regardless of how the leakage was identified (e.g., from the ASME Code,Section XI, required pressure testing, boric acid corrosion control program walkdowns, reactor restart walkdowns, etc.).
- 4.
Please discuss reactor coolant system (RCS) leakage detection capabilities at the plant, or any measure(s) taken, to monitor and identify leakage during operation in an unlikely event of a through-wall leak in the pipe segments under consideration.
Enclosure
- 5.
As a basis for hardship for Portion 6 piping, the licensee stated, in part, that, Manually opening and closing these inboard valves at RCS pressure and temperature creates potential personnel safety issues.
Please discuss whether hardship is due to Technical Specification limiting conditions, or a radiological dose (as low as is reasonably achievable (ALARA)) concern, or both. If ALARA is a concern, provide estimate for person roentgen equivalent man (rem).
- 6.
For Portion 1 through 5 piping, please discuss whether the hardship is also due to a radiological dose (ALARA) concern. If yes, provide estimate for person roentgen equivalent man (rem).
August 21, 2014 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION-REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST FOR ALTERNATIVE 13R-10 (TAC NO. MF4305)
Dear Mr. Heflin:
By letter dated June 26, 2014, Wolf Creek Nuclear Operating Corporation (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) for approval request for alternative 13R-10 for the Wolf Creek Generating Station. The licensee proposed an alternative to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, IWB-5220, for the third 10-year interval of the inservice inspection program.
The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to Mr. S. Wideman of your staff on August 18, 2014. Please provide a response to the enclosed questions within 45 days of the date of this letter.
If you have any questions, please contact me at 301-415-2296 or via e-mail at fred.lyon@nrc.gov.
Docket No. 50-482 Enclosure Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
Sincerely, IRA/
Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PUBLIC LPL4-1 r/f RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEpnb Resource RidsNrrDorllpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMWolfCreek Resource RidsRgn4MaiiCenter Resource ARezai, NRRIDE/EPNB A AMSA D
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