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
MONTHYEARIR 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 ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000354/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 2017-07-07
[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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