ML12283A269

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Request for Additional Information, Round 4, Technical Specification Changes to Support Installation of GE Hitachi Power Range Neutron Monitoring System; Implementation of Prnm/Arts/Mellla
ML12283A269
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/15/2012
From: Lauren Gibson
Plant Licensing Branch IV
To: Reddeman M
Energy Northwest
Gibson L
References
TAC ME7905
Download: ML12283A269 (4)


Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 2012 Mr. Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) Richland, WA 99352-0968 COLUMBIA GENERATING STATION -REQUEST FOR ADDITIONAL INFORMATION REGUARDING LICENSE AMENDMENT REQUEST TO IMPLEMENT PRNM/ARTS/MELLLA (TAC NO. ME7905)

Dear Mr. Reddemann:

By letter dated January 31,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120400144), as supplemented by letters dated July 31,2012, and September 12, 2012 (ADAMS Accession Nos. ML12219A255 and ML12248A136, respectively), Energy Northwest (the licensee) submitted a license amendment request for Columbia Generating Station that would allow the licensee to expand the operating domain by the implementation of Average Power Range Monitor/Rod Block Monitor/Technical Specifications/Power Range Neutron Monitoring/Maximum Extended Load Line limit Analysis (ARTS/PRNM/MELLLA).

The Neutron Monitoring System would be modified by replacing the analog Average Power Range Monitor subsystem with the Nuclear Measurement Analysis and Control (NUMAC) Power Range Neutron Monitoring System. The licensee would expand the operating domain to Maximum Extended Load line limit Analysis (MELLLA) and make changes to certain allowable values and limits and to technical specifications.

The changes to the technical specifications include the adoption of Technical Specifications Task Force (TSTF) Change Traveler TSTF-493, "Clarify Application of Setpoint Methodology for LSSS [Limiting Safety System Setting] Functions," Option A surveillance notes. Furthermore, the amendment would allow a change in the licensing basis to support Anticipated Transient without Scram accident mitigation with one Standby Liquid Control pump instead of two. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that additional information identified in the enclosure to this letter is needed in order for the NRC staff to complete its review. The draft copy of the request for additional information was provided to Mr. Zachary Dunham of your staff via e-mail on September 17, 2012. Please provide a response within 30 days of the date of this letter.

M. Reddeman -If you have any questions regarding this matter, I may be reached at (301) 415-1056 or via e-mail at lauren.gibson@nrc.gov.

Sincerely, Lauren K. Gibson, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO IMPLEMENT PRNM/ARTS/MELLLA ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 By letter dated January 31,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120400144), as supplemented by letters dated July 31,2012, and September 12, 2012 (ADAMS Accession Nos. ML12219A255 and ML12248A136, respectively), Energy Northwest (the licensee) submitted a license amendment request for Columbia Generating Station that would allow the licensee to expand the operating domain by the implementation of Average Power Range Monitor/Rod Block MonitorlTechnical Specifications/Power Range Neutron Monitoring/Maximum Extended Load Line Limit Analysis (ARTS/PRNM/MELLLA).

The Neutron Monitoring System would be modified by replacing the analog Average Power Range Monitor subsystem with the Nuclear Measurement Analysis and Control (NUMAC) Power Range Neutron Monitoring System. The licensee would expand the operating domain to Maximum Extended Load Line Limit Analysis (MELLLA) and make changes to certain allowable values and limits and to technical specifications.

The changes to the technical specifications include the adoption of Technical Specifications Task Force (TSTF) Change Traveler TSTF-493, "Clarify Application of Setpoint Methodology for LSSS [Limiting Safety System Setting] Functions," Option A surveillance notes. Furthermore, the amendment would allow a change in the licensing basis to support Anticipated Transient without Scram accident mitigation with one Standby Liquid Control pump instead of two. The U.S. Nuclear Regulatory Commission staff has reviewed the submitted information and determined that the following information is needed in order for the staff to complete its evaluation. In the submittal, there is information related to verification and validation (V&V) of the software for this upgrade, but there does not appear to be information related to V& V of the operator actions. Please describe the on-site validation of the system, with the revised procedures, and trained operators. Please describe the long-term human performance monitoring program, if any, and how this modification affects it. Enclosure

-M. Reddeman If you have any questions regarding this matter, I may be reached at (301) 415-1056 or via e-mail at lauren.gibson@nrc.gov.

Docket No. 50-397

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrDraAhpb Resource RidsNrrPMColumbia Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource MKeefe, NRR/DRAlAHPB Sincerely, IRA! Lauren K. Gibson, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ADAMS Accession No. ML12283A269

  • via email **via memo OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DRAlAHPB/BC NRR/LPL4/BC NRR/LPL4/PM NAME LKGibson JBurkhardt

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