LR-N07-0100, Report of Changes, Tests and Experiments
| ML071730048 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/14/2007 |
| From: | Gaffney M Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N07-0100 | |
| Download: ML071730048 (4) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUN 1 4 2007 LR-N07-01 00 0 PSEG Nuclear LLC 1 OCFR50.59 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 1 OCFR50.59, "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, 2005 through February 28, 2007.
This report also includes summaries of changes, tests and experiments prepared at HCGS prior to the current reporting period, but implemented after March 1, 2005.
If you have any questions or comments on this transmittal, please contact Francis D. Possessky at (856) 339-1160.
Sincerely, Michael Gaffney y
Regulatory Assurance Manager - Hope Creek Attachment 95-2168 REV. 7/99
JUN 1 4 2007 Page 2 LR-N07-01 00 C
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 & Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08B1 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 086
Attachment LR-N07-0100
SUMMARY
OF CHANGES, TESTS AND EXPERIMENTS HOPE CREEK Emergency Diesel Generator (EDG) Lube Oil Keep Warm Pump Temporary Modification The purpose of this change was to remove the automatic function of "C" EDG lube oil keep warm heater by electronically removing the lube oil keep warm heater thermostat (HiKJ-1KJTS-7539C). The setpoint for the thermostat is 138 F (turn heater off), and the installation of a jumper requires operator action to maintain temperature. This modification was required due to the thermostat vibration caused by a degraded oil pump in close proximity and causing the heater to cycle excessively.
Extended Power Uprate Radiological Design Basis Accident Analysis Update This revision was to update the Design Basis Accident (DBA) radiological analyses documented in the design calculations to assess the impact of the extended power uprate (EPU) project.
Specifically, to determine if the analysis could be safely and conservatively adopted as current design and licensing bases. The post-EPU resulting projected dose for each DBA was determined to be within the regulatory allowable limits with adequate margin for future safe operation of the plant during the remaining design life of the plant including the life extension.
The resulting dose projections are less than 10% of the minimal dose margin. The revised analyses neither impose any additional restrictions to safe operation of the plant nor require modification to any hardware as described in the UFSAR. The plant will continue operating safely and post accident dose mitigation functions will be performed as described in the applicable sections of the UFSAR.
Mechanical Equipment Qualification (MEQ) Program Deletion This change was to delete the description of the Mechanical Equipment Qualification (MEQ) program from the Hope Creek UFSAR. Commensurate changes are required to certain Hope Creek maintenance procedures that require maintenance or replacement of MEQ components.
Appropriate revisions will be made to UFSAR Section 3.11, as well as other relevant sections, to address the deletion of the MEQ program.
General Electric Noble Chemical Application Infrequently Performed Test or Evolution This change was to perform the General Electric (GE) Noble Chemical application process.
This evolution is the deposition of noble metal on the material surface of reactor components and associated piping to significantly reduce the electrochemical corrosion potential (ECP) in the presence of excess hydrogen concentration. This technique has been shown, by both laboratory and operating plant experience, to enhance the effect of hydrogen water chemistry (HWC) in controlling intergranular stress corrosion (IGSCC) with minimal impact on plant operating dose rates. The Reactor Coolant Pressure Boundary (RCPB), nuclear fuel, Residual Heat Removal (RHR), Reactor Water Cleanup (RWCU), and Incore Neutron detectors will be deposited with noble metal. A General Electric (GE) evaluation determined that the noble metal deposit as well as the undeposited products will not reduce structural integrity, create structural interference or affect the performance of any component involved, including pumps, valves, seals, or heat exchangers.
Attachment LR-N07-01 00 Independent Spent Fuel Storage Installation This change was to implement the onsite storage of irradiated fuel at an Independent Spent Fuel Storage Installation (ISFSI). The spent fuel will be stored using the HI-STORM 100 (Holtec International Storage and Transfer Operation Reinforced Module) Dry Fuel Storage System.
Localized High Drywell Temperatures After RF1 1 Refueling Outage (NUCR 70023178 CROD CRFA)
This change permitted high drywell temperatures (hot spots) as indicated on three drywell temperature elements. The evaluation was based upon a temperature limit of 194 degrees in the drywell. The temperature limit of 194 degrees is based on the maximum conductor temperature to allow a 40-year EQ service life for power cables.