ML14197A336
| ML14197A336 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/25/2014 |
| From: | Lyon C Plant Licensing Branch IV |
| To: | Heflin A Wolf Creek |
| Lyon C | |
| References | |
| TAC MF4304 | |
| Download: ML14197A336 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 25, 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-11 (TAC NO. MF4304)
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-11 for the Wolf Creek Generating Station. The licensee proposed an alternative to certain pressure test requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, IWC-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 July 15, 2014. Please provide a response to the enclosed questions within 30 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-11 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 Systems (ADAMS) Accession No. ML14182A091 ), Wolf Creek Nuclear Operating Corporation (the licensee) submitted for the U.S. Nuclear Regulatory Commission (NRC) approval request for alternative 13R-11 for the Wolf Creek Generating Station. The licensee proposed an alternative to a certain requirement of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI. The request relates to performing system leakage test of the reactor pressure vessel (RPV) head flange seal leak-off piping using an alternative pressure in lieu of the pressure required by the ASME Code,Section XI, IWC-5221.
The NRC staff requests the following additional information in order to complete its review of the request.
- 1.
Please discuss whether or not the subject piping can be pressure tested in accordance with the ASME Code,Section XI, IWA-5000 and IWC-5000 before removing the RPV head in the beginning of a refueling outage. If yes, the proposed relief request would not be needed. If no, please discuss the hardship and potential personnel radiation exposure, including an estimate for person-roentgen equivalent man (rem) exposure with consideration of as low as reasonably achievable (ALARA) for the system leakage test performed in accordance with IWC-5221 before removing the RPV head in the beginning of a refueling outage.
- 2.
In Section 4.0 of the Attachment to the letter dated June 26, 2014, the licensee stated, in part, The installation of the plugs and subsequent use would incur additional radiological dose due to additional time for personnel at the reactor vessel flange.
Please provide an estimate for amount of personnel radiation exposure (i.e.,
person-rem exposure) for the installation of the plugs and subsequent removal.
- 3.
Please explain if any segment(s) of the RPV flange leak-off piping is insulated and inaccessible for the ASME Code-required VT-2 visual examination. If yes, please discuss how the licensee will perform the VT -2 visual examination of the insulated and inaccessible segment(s) of the subject piping.
Enclosure
- 4.
Please discuss the construction materials for the subject RPV flange leak-off piping. Discuss operating experience (e.g., plant-specific, fleet, and industry) regarding potential degradation of the subject piping due to any known degradation mechanisms that would lead to pipe through-wall leakage.
- 5.
Please discuss the reactor coolant system leakage detection capabilities at the plant, or any measure(s) taken, to monitor and identify leakage in an unlikely event of a through wall leak in the RPV flange seal leak-off line piping concurrent with leak or failure of the RPV flange inner seal during normal operation.
July 25, 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-11 (TAC NO. MF4304)
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-11 for the Wolf Creek Generating Station. The licensee proposed an alternative to certain pressure test requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, IWC-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 July 15, 2014. Please provide a response to the enclosed questions within 30 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, NRR/DE/EPNB ADAM s Accession No.: ML14197A336
- email d ated July 15, 2014 OFFICE NRRIDORULPL4-1/PM NRRIDORULPL4-1/LA NRRIDE/EPNB/BC(A)*
NRRIDORULPL4-1/BC NRRIDORULPL4-1 /PM NAME FLyon JBurkhardt JTsao MMarkley (PBamford for) FLyon DATE 7/23/14 7/22/14 7/15/14 7/25/14 7/25/14 OFFICIAL RECORD COPY