SVPLTR 10-0019, Regulatory Commitment Change Summary Report
| ML101310392 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/30/2010 |
| From: | Hanley T Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SVPLTR #10-0019 | |
| Download: ML101310392 (3) | |
Text
~Exeltn Exelon Generation Company, LLC www.exeloncorp.com NEuclea Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 April 30, 2010 SVPLTR: #10-0019 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 Nuclear Docket Nos. 50-237 and 50-249
Subject:
2009 Regulatory Commitment Change Summary Report Please find enclosed the 2009 Commitment Change Summary for Dresden Nuclear Power Station. Revisions to docketed regulatory correspondence were processed using Nuclear Energy Institute's (NEI) 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes", dated July 1999.
Should you have any questions concerning this summary, please contact Mr. Patrick Quealy, Acting Regulatory Assurance Manager at 815-416-2800.
Respectfully, Tim Hanley Site Vice President Dresden Nuclear Power Station
Enclosure:
Attachment A: Dresden Nuclear Power Station Commitment Change Summary for 2009 cc:
NRC Regional Administrator, Region III NRC Senior Resident Inspector, Dresden Nuclear Power Station
Attachment A Dresden Nuclear Power Station Commitment Change Summary for 2009 Commitment Date of Original Original Commitment Revised Commitment Basis For Revision Revision Commitment Document Tracking No.
Revision 09-02 2/24/09 ComEd letter to D.
Install on line leakage monitoring Exelon/Dresden is deleting the Dresden currently monitors the feedwater Eisenhut dated systems. The monitoring systems commitment to monitor the nozzles for cracking using Ultrasonic Testing 2/23/81 will detect bypass leakage past the temperatures at the feedwater methods rather than thermocouples. The UT secondary seal by means of nozzles.
testing is more reliable than the thermocouples mounted on the thermocouples.
outside surface of the nozzles.
09-07 7/7/09 Exelon letter RS-One-Time inspection of HPCI Delete Commitment for One-Time Commitment intention was to inspect the 04-020, dated lubrication oil hoses for age related inspection of the HPCI lubricating HPCI lubricating oil system flexible hoses, February 3, 2004.
degradation.
oil system flexible hoses.
which were assumed to be made of elastomer material; however the hoses were actually determined to be carbon steel piping.
Quad Cities identified these hoses as being made of carbon steel material during there one-time inspection. They also performed NDE on the carbon steel and determined that there was no degradation to the material.
Quad Cities HPCI Turbine and lubricating system is identical to the one here at Dresden Station.
09-08 9/10/09 Dresden License Dresden committed to "BWR Water Dresden commits to following the Dresden follows the current EPRI guidance in Renewal Request.
Chemistry Guidelines: 2000 most recent EPRI Guideline for effect for BWR Water Chemistry Guidelines Letter RS-03-001, Revision," EPRI TE 103515-R2, BWR Water Chemistry. The rather than an older version of the Guidelines.
dated January 3, Final Report, February 2000 and current guideline is BWRVIP-190:
2003.
subsequently BWRVIP-130: BWR BWR Vessel and Internals Vessel and Internals Project BWR Project, BWR Water Chemistry Water Chemistry Guidelines - 2004.
Guidelines - 2008 Revision, TR 1016579.
09-09 7/2/09 Dresden SVP DAP 03-05, Out of Service Process, DOP 6500-04, rev 26 removed the Engineering Change (EC) 353251 evaluated Letter JMHLTR was revised to include specific time time limits specifying how long a 4 the total number of breakers which can be left 98-002, Response limits associated with 4kV breakers kV breaker can be in the test in any position other than racked in, and still to Notice of that are out of service and being position.
maintain seismic qualification. This Violation NRC temporary lifted in the test position administrative limitation is incorporated in Inspection Report to be consistent with the limits found procedure DOP 6500-04.
50-in the operating procedure DOP 10/237/249/97019 6500-04, Racking out of Safety.
Related 4kV Breakers.
Page 1 of 2
Attachment A Dresden Nuclear Power Station Commitment Change Summary for 2009 P.
Commitment Date of Original Original Commitment Revised Commitment Basis For Revision Revision Commitment Document Tracking No.
Revision 09-22 SVP Letter 09-An aging management program will An aging management program The commitment included an evaluation that 0053, dated be implemented for thermal aging will be implemented for thermal requires the material composition be obtained 11/12/2009.
and neutron irradiation aging and neutron irradiation from certified material test reports (CMTR5).
embrittlement of CASS reactor embrittlement of CASS reactor The CMTRs could not be located for the internal components within the internal components within the components in question. The purpose of the scope of license renewal. A scope of license renewal. A commitment is to determine the CASS component specific evaluation for component specific evaluation for components where a loss of fracture the loss of fracture toughness will be the loss of fracture toughness will toughness may affect the function of the included. For those components be included, If material component and to establish an inspection where the loss of fracture toughness composition cannot be program for those susceptible components.
may affect the function of the determined, a loss of fracture This change conservatively assumes that the component, an inspection will be toughness may be assumed as an components are susceptible and establishes performed as part of the ISI alternative to a specific evaluation, an inspection program the same as would be Program.
For those components where it is required by the original commitment if an assumed or the evaluation has evaluation had concluded there was a loss of determined a loss of fracture fracture toughness that may affect the toughness may affect the function function of the component.
of the component, an inspection will be performed as part of the ISI Program.
Page 2 of 2