ML051940354
| ML051940354 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek (DPR-016) |
| Issue date: | 07/05/2005 |
| From: | Swenson C AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-05-20133, GL-95-007, GL-96-005, NEI 99-04 | |
| Download: ML051940354 (3) | |
Text
AmerGen SM AmerGen Energy Company, LLC www.exeloncorp.com An Exelon Company Oyster Creek US Route g South, P.O. Box 388 Forked River, NJ 08731-0388 NEI 99-04 July 5, 2005 2130-05-20133 U. S. Nuclear Regulatory Commission
___ _Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-1 6 NRC Docket No. 50-219
Subject:
Commitment Change Summary Report - 2004 Enclosed is the 2004 Commitment Change Summary Report for Oyster Creek Generating Station. The content and formiat of information submitted in this report is in accordance with the'guidance provided by NEI 99-04.
If any further information or assistance is nieeded,'please contact David Fawcett at 609-971-4284.
Sinicerely, C. N.' Swenson Vice President, Oyster Creek Generating Station CNS/DIF Enclosure cc:
S. J. Collins, Administrator, USNRC Region I P. S. Tam, USNRC Senior Project Manager,' Oyster Creek'-'
R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No:.04101
2130-05-20133 NEI 99-04 2004 Commitment Change Summary Report for Oyster Creek The following two NRC Commitments tracked in the Oyster Creek Generating Station (OCGS) Licensing Action Request (LAR) database were changed during the calendar year 2004. These changes were evaluated in accordance with Exelon Procedure LS-AA-110, Commitment Management, and determined to require NRC notification during the next Annual Commitment Change Summary Report consistent with NEI 99-04.
Response to Generic Letter96-05 Original Commitment; In response to Generic Letter 96-05 RAI, OCGS declared that "all program valves have been placed on a schedule where all will be tested (from the Motor Control Center (MCC)) within 5 years of the previous test to confirm that the Motor Operated Valve (MOV) performance is not degrading". (LAR 96097.08)
Revised Commitment - OCGS has committed to all three phases of the Joint Owner's Group (JOG) Program that includes (1) the JOG interim static diagnostic test program; (2) the JOG 5-year dynamic test program; (3) the JOG long term periodic test program.
Changed: 05/07/2004 Justification - The original statement was mentioned as a partial response to question 2 of the RAI dated May 12,2000. "in the NRC SE dated October 30, 1997... Topical Report MPR-1 807 describing the JOG Program, the NRC stated that MOV's that will be tested at frequencies beyond five years will need to be grouped with other MOV's that will be tested at frequencies less than five years". OCGS has revised this commitment by no longer performing MCC testing on each individual GL 96-05 MOV within five years of the previous test. This is based on several factors, such as:
Extensive use of EPRI Performance Prediction Methodology (PPM) at OCGS provides a majority of program valves with inherent high margin. A high margin valve could endure some amount of degradation before the capability of the actuator is questioned.hose__
program valves that do not have a PPM calculation were divided into groups for valve factor determination. All of the valve factor valves are on a 10-year test frequency due to high margins.
OCGS still intends to use Motor Power Testing from the MCC on all MOVs following the periodic preventive maintenance inspection and following any program valve maintenance. Additionally, GL 96-05 MOVs with test frequencies of ten years will be scheduled for interim motor power testing: though not necessarily within five years.
Interim motor power testing is one of several methods recognized within Exelon Nuclear Standard MOV Program to extend the valve periodic verification testing out to ten years.
2130-05-20133 NEI 99-04 Response to GL 95-07 Original Commitment: In response to GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves, GPU Nuclear in letter 1940-99-20583 dated 10/28/99, Response to Second Request for Additional Information, stated that the normally closed Isolation Condenser Outboard Condensate Return valves (V-14-34 & V-14-35) will be cycled at 650 psig and 300 psig during reactor cooldown evolutions.
(LAR 95100.09)
Revised Commitment - Deleted and taken to History. Changed: 10/29/2004 Justification - The configuration change ECR OC 04-00895 drilled the reactor side valve disc on the above valves to alleviate the bonnet over-pressurization condition under-all modes of operation. This method is an acceptable method to resolve the bonnet over-pressurization in the dual disc gate valves to resolve GL 95-07 pressure locking issue.
The above valves are dual disc valves. Therefore, the commitment identified above is not necessary after the configuration change that was completed in 1 R20.
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