ML101370091
| ML101370091 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/20/2010 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | Matthew Sunseri Wolf Creek |
| Singal, B K, NRR/DORL, 301-415-301 | |
| References | |
| TAC ME3766 | |
| Download: ML101370091 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 20,2010 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 SUB~IECT: WOLF CREEK GENERATING STATION - NON-ACCEPTANCE WITH OPPORTUNITY TO SUPPLEMENT, LICENSE AMENDMENT REQUEST TO REMOVE HIGH/LOW PRESSURE DESIGNATION FROM PRESSURIZER POWER-OPERATED RELIEF VALVES (TAC NO. ME3766)
Dear Mr. Sunseri:
By letter dated April 13, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML101100479), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) submitted a license amendment request for Wolf Creek Generating Station (WCGS). The proposed amendment would revise the approved fire protection program to remove the high/low pressure designation from the pressurizer power-operated relief valves (PORVs) and their associated block valves. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.
The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by June 1, 2010. This will enable the NRC staff to complete its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application. If the application is subsequently accepted for review, you will
M. Sunseri -2 be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with Ms. Diane Hooper and Messrs. Steven Wideman, Jeff Suter, Brian Fox and Ken Fredrickson of your staff on May 13, 2010.
If you have any questions, please contact me at 301-415-3016 or via e-mail at Balwant.singal@nrc.gov.
Sincerely, bo.! ~\ t-6~~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Supplemental Information Needed cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST REGARDING PRESSURE BOUNDARY DESIGNATION FOR THE PRESSURIZER POWER-OPERATED RELIEF VALVES AND THEIR ASSOCIATED BLOCK VALVES WOLF CREEK GENERATING STATION DOCKET NO. 50-482 By letter dated April 13, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML101100479), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) requested an amendment to the Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station (WCGS). This license amendment request (LAR) is seeking approval by the U.S. Nuclear Regulatory Commission (NRC), pursuant to license condition 2.C(5), to make changes to the approved fire protection program as described in the WCGS Updated Safety Analysis Report (USAR). Specifically, a revision to the response to the (NRC) Question 280.5, documented on page 280-5 of the NRC Questions Section at the end of the USAR, is requested regarding the removal of the high/low pressure interface designation from the pressurizer power-operated relief valves (PORVs) and their associated block valves.
The above-referenced license condition allows the licensee to make changes to the approved fire protection program without prior NRC approval only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. WCNOC has determined that NRC review and approval of the proposed change is warranted.
The NRC staff has reviewed the LAR and concluded that the scope of the analysis is incomplete since impacts of the proposed LAR on the plant are not discussed in the LAR. Therefore, additional information is needed to enable an independent assessment regarding the acceptability of the LAR. To enable this independent assessment, the following information is required:
- Please provide a description of the safety impact that the proposed license amendment would have on the plant.
- Please provide a description of any modifications or changes to the operation of the pressurizer PORVs and their associated block valves, including electrical control circuits and cable rerouting, which would occur, if this license amendment were accepted.
- Please provide a description of any changes to the post-fire safe shutdown analysis, including new or revised procedures, operator manual actions, and other operator post-fire guidance documents, which would occur if this license amendment were accepted.
Enclosure
M. Sunseri - 2 be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with Ms. Diane Hooper and Messrs. Steven Wideman, Jeff Suter, Brian Fox and Ken Fredrickson of your staff on May 13, 2010.
If you have any questions, please contact me at 301-415-3016 or via e-mail at Balwant.singal@nrc.gov.
Sincerely,
/raj Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Supplemental Information Needed cc w/encl: Distribution via Listserv DISTRIBUTION:
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