ML090700127
| ML090700127 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/26/2009 |
| From: | Gaffney M Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N09-038 | |
| Download: ML090700127 (3) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG FEB 2 6 2009 NuclearLLC LR-N09-038 10 CFR50.59 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 Docket No. 50-354
Subject:
Report of Changes, Tests and Experiments Pursuant to the requirements of 10CFR50.59, "Changes, tests and experiments",
paragraph (d)(2), Hope Creek Generating Station (HCGS) is providing the required report for Facility Operating License No. NPF-57. This report provides a summary of changes, tests and experiments implemented at HCGS during-the period of March 1, 2007 through February 24, 2009.
This report also includes summaries of changes, tests and experiments prepared at HCGS prior to the current reporting period, but implemented after March 1, 2007.
There are no regulatory commitments contained in this letter.
If you have any questions or comments on this transmittal, please contact Timothy Devik at (856) 339-3108.
Sincerely, Michael Gaff Regulatory Assurance Manager - Hope Creek Attachment 95-2168 REV. 7/99
Page 2 LR-N09-038 Document Control Desk cc:
Mr. S. Collins, Administrator - Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager Salem and Hope Creek U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B1 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector-Hope Creek (X24)
P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625 Hope Creek Commitment Tracking Coordinator
Attachment LR-N09-038 Document Control Desk
SUMMARY
OF CHANGES, TESTS AND EXPERIMENTS HOPE CREEK Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement 1 to CENP-287.
The purpose of this change was to increase the mechanical burnup limit of the SVEA-96+ fuel contained in the Hope Creek Generating Station (HCGS) reactor core. In February of 2006, Westinghouse obtained NRC approval of a supplement to the mechanical design methodology topical, WCAP-1 5942-P-A (Formerly CENP-287), Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement 1 to CENP-287, which supports extending the burnup limit for the mechanical design of SVEA-96+ to 62 Gwd/Mtu. This change was required because HCGS would have exceeded the previous mechanical design limit of 50 Gwd/Mtu prior to the end of the current cycle.
Removal of Auto-Close Function for HPCI to FW Discharge Valve HV-8278.
The purpose of this change was to remove the automatic closure function of the HPCI to Feedwater (FW) injection valve H1 BJ-BJ-HV-8278 ("HV-8278"). This change addresses the thermal binding issues associated with this valve as identified on July 31, 2007. An evaluation was performed by MPR Associates (VTD 328271) which determined that thermal binding is a plausible cause for the failure of HPCI feedwater injection valve HV-8278 to open during the recent in-service test (IST). Leaving HV-8278 open following a HPCI injection will eliminate the possibility of the valve binding due to the mechanism identified by MPR Associates. Although the automatic closure is disabled, the valve may be manually closed from the main control room at a convenient time after HPCI is secured.
Removal of Auto-Close Function for RCIC Discharge Valve BD-HV-F013.
The purpose of this temporary modification was to remove the automatic closure function of the RCIC Discharge valve to address the thermal binding issues identified during an extent of condition review for the HPCI HV-8278 thermal binding condition. This change removes the potential for thermal binding of the BD-HV-F013 ("HV-F013") as identified by MPR Associates (VTD 328271).
Leaving HV-F013 open following a RCIC injection will eliminate the possibility of the valve binding due to the mechanism identified by MPR Associates. Although the automatic closure is disabled, the valve may be manually closed from the main control room at a convenient time after RCIC is secured.