12-20-2016 | On October 23, October 24, and October 31, 2016, with Hope Creek Generating Station ( HCGS) in a planned refueling outage and the reactor cavity flooded in OPCON 5, HCGS performed operations with a potential to drain the reactor vessel ( OPDRV) without an operable secondary containment. These operations are prohibited by Technical Specification (TS) 3.6.5.1; however, NRC guidance provided in Enforcement Guidance Memorandum (EGM) 11-003, Revision 3, allowed the implementation of interim actions as an alternative to full compliance. These actions were compiled in a plant procedure for the OPDRV activities performed at HCGS during Refueling Outage (HR20) in October 2016.
These OPDRV activities were planned activities that were completed under the guidance of plant procedures and confirmed to have low safety significance based on the interim actions taken. Since these actions were deliberate, no cause determination was necessary. Consistent with the guidance provided in EGM 11-003, Revision 3, HCGS will submit a license amendment request to adopt a Technical Specification Task Force (TSTF) traveler associated with generic resolution of this issue within four months after the issuance of the Notice of Availability of the TSTF traveler.
These conditions are being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by TS. |
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Category:Letter
MONTHYEARML24295A3742024-10-23023 October 2024 Project Manager Assignment IR 05000354/20240032024-10-23023 October 2024 Integrated Inspection Report 05000354/2024003 ML24291A0572024-10-17017 October 2024 License Amendment Request (LAR) – Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 1 LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle IR 05000272/20244022024-09-23023 September 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/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 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024 – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5 ML24145A1772024-07-15015 July 2024 And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary ML24197A0552024-07-15015 July 2024 Requalification Program Inspection 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) LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves IR 05000272/20245012024-06-12012 June 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20240112024-04-0101 April 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal IR 05000272/20244032024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 LR-N24-0021, And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums 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 LR-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report IR 05000354/20230062024-02-28028 February 2024 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2023006) IR 05000272/20244012024-02-26026 February 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges 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 IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 – Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers 2024-09-05
[Table view] 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 LR-N24-0027, 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-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
[Table view] |
Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to Impose an information collection does not display a currently valid OMB control http://www.nrc.govireadino-rm/doc-collections/nureos/staff/sr1022/r31) number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
Hope Creek Generating Station 05000-354 YEAR
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor (BWR/4)* Reactor Pressure Vessel (AC) - EIIS Identifier {AC/RPV} Secondary Containment (NG) - EllS Identifier {NG} *Energy Industry Identification System {EIIS} codes and component function identifier codes appear as {SS/CCC}
IDENTIFICATION OF OCCURRENCE
Event Dates: October 23, October 24, and October 31, 2016 Discovery Dates: October 23, October 24, and October 31, 2016
CONDITIONS PRIOR TO OCCURRENCE
Hope Creek was shut down for Refueling Outage H1R20 in Operational Condition (OPCON) 5 - Refueling Operations.
DESCRIPTION OF OCCURRENCE
On October 23, October 24, and October 31, 2016, with Hope Creek Generating Station (HCGS) in a planned refueling outage and the reactor cavity flooded in OPCON 5, HCGS performed operations with a potential to drain the reactor vessel (OPDRV) without an operable secondary containment {NG}. These operations are prohibited by Technical Specification (TS) 3.6.5.1, "Secondary Containment Integrity." The NRC recognized that such activities may need to be performed during refueling outages while activities were underway with the Boiling Water Reactor Owners (BWROG) to formulate acceptable generic changes to the BWSR Technical Specifications (TS). NRC guidance provided in Enforcement Guidance Memorandum (EGM) 11-003, Revision 3, "Enforcement Guidance Memorandum on Dispositioning Boiling Water Reactor Licensee Noncompliance with Technical Specification Containment Requirements During Operations With a Potential for Draining the Reactor Vessel," dated January 15, 2016, allowed the implementation of specific interim actions, as an alternative to full compliance with TS, while the improvements in the TS are under development with the BWROG. The required interim actions specified in the EGM were incorporated into plant procedure OP-HC-108-102, "Management of Operations with the Potential to Drain the Reactor Vessel.
This procedure was then utilized on these occasions as listed in Table 1, during Refueling Outage (H1R20).
Table 1 - HCGS OPDRVs Performed October 2016 Activity / Duration Start End Replacement of Control Rod Drive mechanisms/ 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />, 10 minutes October 23, 2016 at 08:40
EDT
October 23, 2016 at 22:50
EDT
Replacement of Local Power Range October 23, 2016 at 22:50 October 24, 2016 at 08:07 Monitors/ 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, 17 minutes EDT EDT Replacement of Control Rod Drive mechanisms and LPRMs/ 1 day, 16 minutes October 24, 2016 at 08:07
EDT
October 25, 2016 at 08:23
EDT
Fill and Vent of the A and B Reactor Recirculation Pump seal / 1 Day, 41 minutes October 31, 2016 at 11:21
EDT
November 1, 2016 at 12:02
EDT
CAUSE OF EVENT
Implementation of EGM 11-003, Revision 3, interim actions during the HCGS refueling outage (H1R20) was a planned activity. As such, no cause determination was performed for the event.
Reported lessons learned are incorporated Into the licensing process and fed back to industry, Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mall to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget Washington, DC 20503. If a means used to Impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection, Hope Creek Generating Station 05000-354 2016 - 004 - 00
SAFETY CONSEQUENCES AND IMPLICATIONS
The OPDRVs discussed in this report were performed during the HCGS refueling outage (H1R20) and were accomplished using the interim actions provided by the NRC in EGM 11-003, Revision 3. For these events, HCGS adhered to the NRC plain language meaning of OPDRV activities that could potentially result in draining or siphoning the RPV water level below the top of fuel. This included evolutions involving aligning and realigning plant systems prior to achieving steady-state water level control, without taking credit for mitigating measures. HCGS also met the requirements that specify the minimum makeup flow rate and water inventory based on OPDRV activities with long drain down times. Further, an adequate defense-in-depth was maintained to minimize the potential for the release of fission products with secondary containment not operable by (a) monitoring RPV level to identify the onset of a loss of inventory event; (b) maintaining the capability to isolate the potential leakage paths; (c) prohibiting Mode 4 (cold shutdown) OPDRV activities; and (d) prohibiting movement of irradiated fuel with the spent fuel storage pool gates removed in Mode 5. All other Mode 5 TS requirements for activities were followed. Since these compensatory measures were properly implemented, an adequate level of safety was provided during the OPDRV activities described in this report. Based on this information, the performance of these OPDRV activities were determined to have a low safety significance.
PREVIOUS EVENTS
A review of Licensee Event Reports and the corrective action program for the past three years identified the following previous similar concurrences:
- LER 2012-003-00, dated May 5, 2012, reported an OPDRV activity during the 2012 refueling outage (H1 R17). Interim actions in accordance with Revision 0 of the EGM were applied. No corrective actions were stated.
- LER 2013-004-00, dated December 10, 2013, reported OPDRV activities during the 2013 refueling outage (H1R18). Interim actions in accordance with Revision 1 of the EGM were applied. No corrective actions were stated.
- LER 2015-002-11, dated June 10, 2015, reported OPDRV activities during the 2015 refueling outage (H1R19). Interim actions in accordance with Revision 2 of the EGM were applied. No corrective actions were stated.
CORRECTIVE ACTIONS
HCGS will submit a license amendment request to adopt a Technical Specification Task Force (TTF) traveler associated with generic resolution of this issue, within twelve months after the issuance of the Notice of Availability of the TSTF traveler as required by EGM 11-003. This action is being tracked in HCGS Corrective Action Program.
COMMITMENTS
This LER contains no regulatory commitments
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05000354/LER-2016-001 | High Pressure Coolant Injection System Found to be Inoperable During Testing | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000354/LER-2016-002 | High Pressure Coolant Injection System Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000354/LER-2016-003 | 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 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000354/LER-2016-004 | 1 OF 3 LER 16-004-00 for Hope Creek Regarding Operations With a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000354/LER-2016-005 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000354/LER-2016-006 | LER 16-006-01 for Hope Creek, Unit 1, Regarding Mode Change Without B Channel Level Instrumentation Operable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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