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Category:Licensee Event Report (LER)
MONTHYEAR05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024
Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement
05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024
Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)
05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024
Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram
05000354/LER-2023-003, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-02-12012 February 2024
Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram
05000354/LER-2023-001-02, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable2023-09-25025 September 2023
Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable
05000354/LER-2023-001-01, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable2023-09-11011 September 2023
Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable
05000354/LER-2023-001, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable2023-06-20020 June 2023
Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable
05000354/LER-1922-002, Inoperable Isolation Actuation Instrumentation Caused by Failure to Remove Electrical Jumper2023-01-18018 January 2023
Inoperable Isolation Actuation Instrumentation Caused by Failure to Remove Electrical Jumper
05000354/LER-2022-001, B EDG Inoperable Resulting in a Condition Prohibited by Technical Specifications2022-03-18018 March 2022
B EDG Inoperable Resulting in a Condition Prohibited by Technical Specifications
05000354/LER-2021-001, Safety Relief Valve (SRV) As-Found Setpoint Failures2021-08-13013 August 2021
Safety Relief Valve (SRV) As-Found Setpoint Failures
05000354/LER-2017-0012017-07-0707 July 2017
1 OF 3, LER 17-001-00 for Hope Creek, Unit 1 Regarding Secondary Containment Door Not Latched in Closed Position
05000354/LER-2016-0062017-05-0404 May 2017
LER 16-006-01 for Hope Creek, Unit 1, Regarding Mode Change Without B Channel Level Instrumentation Operable
05000354/LER-2016-0052017-03-13013 March 2017
Reactor Protection System Actuation While the Reactor Was Shutdown, LER 16-005-01 for Hope Creek, Unit 1, Regarding Reactor Protection System Actuation While the Reactor Was Shutdown
05000354/LER-2016-0032017-03-0808 March 2017
As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit, LER 16-003-001 for Hope Creek Generating Station Unit 1 Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit
05000354/LER-2016-0042016-12-20020 December 2016
1 OF 3, LER 16-004-00 for Hope Creek Regarding Operations With a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment
05000354/LER-2015-0052016-01-0505 January 2016
Reactor Scram Due to Invalid RRCS Actuation, LER 15-005-01 for Hope Creek, Unit 1, Regarding Reactor Scram Due to Invalid RRCS Actuation
LR-N12-0114, Retraction of Licensee Event Report 2011-0012012-04-13013 April 2012
Retraction of Licensee Event Report 2011-001
LR-N05-0143, Special Report 05-001-01 Regarding the Cause of Failure and Channel Restoration2005-03-31031 March 2005
Special Report 05-001-01 Regarding the Cause of Failure and Channel Restoration
LR-N04-0526, Special Report 354/04-012-002004-11-18018 November 2004
Special Report 354/04-012-00
LR-N04-0489, LER 04-08-00 for Hope Creek Generating Station Re Potential for Uncontrolled Radiological Release - Reactor Water Clean-up Isolation2004-10-28028 October 2004
LER 04-08-00 for Hope Creek Generating Station Re Potential for Uncontrolled Radiological Release - Reactor Water Clean-up Isolation
2024-09-05
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 A)PSE G LR-N04-0526 Nuclear LLC NOV 1 8 2004 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SPECIAL REPORT 354/04-012-00 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 This Special Report is being submitted pursuant to the requirements of Hope Creek Technical Specification (TS) 3.8.1.1 Action h. TS 3.8.1.1 Action h states:
"With the buried fuel oil transfer piping's cathodic protection system inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring to OPERABLE status."
There are two cathodic protection rectifiers associated with the Emergency Diesel Generator (EDG) buried fuel oil transfer piping, 00-SC505 and 00-SC509. On October 11, 2004, at 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br />, rectifier 00-SC509 was found de-energized. Rectifier 00-SC509 is supplied power from electrical panel 00B509. Investigation of the loss of power to rectifier 00-SC509 identified that feeder breaker 52-50034 that feeds panel 00B509 was tripped due to a ground fault. The ground fault occurred following a fire in the Hope Creek Substation 4 transformer and the associated 480 V motor control center. Hope Creek Substation 4 is part of the non-power block ring bus that feeds loads such as the administration buildings, sewage treatment plant, etc.
In addition to rectifier 00-SC509 losing power, power to rectifier 00-SC505 was tagged on October 29, 2004, as part of a scheduled service water loop outage to allow for underground pipe testing. Power was restored to rectifier 00-SC505, on November 10, 2004, at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> with the release of the associated tags.
Also, on November 10, 2004, power was restored to rectifier 00-SC509 by a temporary diesel generator until repairs are completed to restore the permanent power feed to breaker 52-50034. The use of the temporary diesel generator to power rectifier 00-SC509 essentially restores the cathodic protection for the buried fuel oil piping b:>)I 95-2168 REV. 7/99
Document Control Desk 2 LR-N04-0526 NOV 1 8 2004 functional status; however, the system is not considered OPERABLE since the temporary diesel generator must be stopped once a day for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to refuel.
Repair of the permanent power feed to breaker 52-50034 is currently scheduled to be completed the work week of November 29, 2004.
Sincerely, Plant Manager - Hope Creek BJT C Mr. S. Collins, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 USNRC Senior Resident Inspector - Hope Creek (X24)
Distribution LER File 3.7
