RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .
RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591
RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
IR 05000237/2024003
ML24291A027
RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)
ML24291A020
ML24303A024
ML24303A030
ML24303A053
ML24303A110
ML24303A043
ML24303A017
ML24303A146
ML24303A015
ML24303A089
ML24291A025
IR 05000237/2025401
RS-24-104, Nuclear Radiological Emergency Plan Document Revision
ML24303A135
ML24303A099
ML24303A049
ML24303A055
ML24303A060
ML24303A047
ML24303A142
ML24303A051
ML24303A027
ML24303A117
ML24303A064
ML24303A013
ML24303A144
ML24303A020
ML24303A069
ML24303A134
ML24303A071
ML24317A143
ML24323A079
ML24324A320
ML24331A259
ML24352A207
RS-24-135, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24344A274
IR 05000010/2024001
ML24353A137
ML25017A230
05000249/LER-2024-002, Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications
ML24351A145
05000237/LER-2024-001, Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function
05000249/LER-2024-002, Low Pressure Coolant Injection Pump Suction Relief Valve Inoperable as a Primary Containment Isolated Valve Resulted in a Condition Prohibited by Technical Specifications
05000237/LER-2024-001, Containment Cooling Service Water Valve Failure Resulted in a Condition Prohibited by Technical Specifications and Loss of Safety Function
Exelon Generation Company, LLC www.exeloncorp.com Dresden Nuclear Power Station Nucear 6500 North Dresden Road Morris, IL 60450-9765 10 CFR 50.73 SVPLTR # 07-0024 May 1,2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Licensee Event Report 249/2007-001 -00, "Unit 3 High Pressure Coolant Injection System Declared Inoperable" Enclosed is Licensee Event Report 249/2007-001-00, "Unit 3 High Pressure Coolant Injection System Declared Inoperable," for Dresden Nuclear Power Station, Unit 3. This event is being reported in accordance with 10 CFR 50.73(a)(2)(v)(D), "Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident."
Should you have any questions concerning this report, please contact Mr. James Ellis, Regulatory Assurance Manager, at (815) 416-2800.
Respectfully, Danny G ost Site Vi President Dresden Nuclear Power Station Enclosure cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
ý6-200)4)
, the NRC may dig its/characters for each block)inot conduct or sponsor, and a person is not required to respond to, the digis/carater foreac blck)infnrm~tinn conllecrtion.
3. PAGE Dresden Nuclear Power Station, Unit 3 05000249 1 OF 3
Specify in Abstract below or in (If more space is required, use additional copies of NRC Form 366A) (17) closure documentation that did not clearly document that not all of the original work scope was completed. As a result, several sections of Unit 2 and 3 HPCI System piping susceptible to FAC that were not replaced were incorrectly removed from the FAC Inspection Program.
D.
Safety Analysis
The safety significance of the event is minimal. TS 3.5.1 allows Unit 3 to remain at power for 14 days with an inoperableHPCI if the Isolation Condenser System (IC) is operable. Unit 3 was in compliance with TS 3.5.1 during this event as the IC was operable and HPCI was inoperable for approximately 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. Therefore, the consequences of this event had minimal impact on the health and safety of the public and reactor safety.
E.
Corrective Actions
Unit 3 HPCI System Inlet Drain Pot drain piping with the pinhole leak was replaced.
Unit 2 and 3 HPCI System carbon steel piping susceptible to FAC has been identified, evaluated for acceptance of the degraded condition until replacement and scheduled for replacement in future outages.
The Work Control process has been significantly enhanced since 1997 to ensure sufficient closeout documentation including the use of a computerized process (PASSPORT) for entering closeout documentation, implementation of procedure MA-AA-716-011, 'Work Execution and Closeout," and the use of First Line Supervisors to enter work documentation notes.
F.
Previous Occurrences
A review of DNPS Licensee Event Reports (LERs) for the last three years did not identified any LERs associated with piping that was found with a through wall leak and susceptible to FAC.