10-4-2017 | On August 8, 2017, at 1554 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.91297e-4 months <br />, while the plant was at 100 percent rated thermal power, during restoration from testing of the High Pressure Core Spray ( HPCS) Suppression Pool ( SP) Level High Instrumentation, unexpected as-left indications were found that impacted both of the required channels of instrumentation. With both SP level instruments inoperable, a loss of safety function existed.
While venting the sensing line, the HPCS system was aligned to the suppression pool water source. This source of water is HPCS's safety-related source of water. The automatic suction swap on high suppression pool level is implicitly assumed in the accident and transient analysis since it assumes that the HPCS suction source is the suppression pool.
Since the HPCS system was aligned to the suppression pool when the failure occurred, the assumptions of the accident analysis are met, and no safety system functional failure occurred.
The cause for the unexpected as-left indications is due to air entrained in the sensing line which came out of solution.
The safety significance of this event is considered to be small. This event is being reported under 50.73(a)(2)(v)(D) for a loss of safety function. |
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Category:Letter
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Penfield-Perry Nuclear Power Plant Unit 1-License Renewal Scoping Summary Rpt L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 IR 05000440/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000440/2024401 L-24-036, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-27027 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-24-020, License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 22024-06-27027 June 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 2 IR 05000440/20240112024-06-17017 June 2024 Fire Protection Team Inspection Report 05000440/2024011 ML24157A3782024-06-0606 June 2024 – Revised Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 ML24141A1632024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-116, Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification2024-05-16016 May 2024 Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification L-24-085, Nudear Power Plant, Submittal of Emergency Plan, Revision 622024-05-0606 May 2024 Nudear Power Plant, Submittal of Emergency Plan, Revision 62 L-24-103, Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams2024-05-0202 May 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams ML24117A1222024-04-26026 April 2024 Confirmation of Initial License Examination IR 05000440/20240012024-04-24024 April 2024 Integrated Inspection Report 05000440/2024001 L-24-097, Submittal of 2023 Annual Radiological Effluent Release Report2024-04-22022 April 2024 Submittal of 2023 Annual Radiological Effluent Release Report L-24-096, Submittal of Annual Radiological Environmental Operating Report2024-04-22022 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24095A3282024-04-19019 April 2024 License Renewal Revised Schedule Letter L-24-066, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency2024-04-15015 April 2024 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency L-24-083, Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification2024-04-15015 April 2024 Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification L-24-057, Submittal of the Decommissioning Funding Status Report2024-03-28028 March 2024 Submittal of the Decommissioning Funding Status Report ML24088A1922024-03-28028 March 2024 Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-076, Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-22022 March 2024 Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24064A2212024-03-14014 March 2024 Letter to Rod L. 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[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000440/LER-2017-0062017-12-0101 December 2017 Loss of Safety Function due to the Inoperability of Both Trains of Motor Control Center Ventilation, LER 17-006-00 for Perry Nuclear Power Plant Regarding Loss of Safety Function due to the Inoperability of Both Trains of Motor Control Center Ventilation 05000440/LER-2017-0042017-10-0404 October 2017 Loss of Safety Function for High Pressure Core Spray Suppression Pool Level Instrumentation, LER 17-004-00 for Perry re Loss of Safety Function for High Pressure Core Spray Suppression Pool Level Instrumentation 05000440/LER-2017-0052017-10-0404 October 2017 Controller Malfunction results in Momentary Degradation of Secondary Containment Pressure, LER 17-005-00 for Perry Nuclear Power Plant Regarding Controller Malfunction Results in Momentary Degradation of Secondary Containment Pressure 05000440/LER-2017-0022017-06-27027 June 2017 Loss of Safety Function Due to Main Turbine Bypass Valve Opening, LER 17-002-00 for Perry Nuclear Power Plant Regarding Loss of Safety Function Due to Main Turbine Bypass Valve Opening 05000440/LER-2017-0032017-06-26026 June 2017 Annulus Exhaust Gas Treatment System Loss of Safety Function, LER 17-003-00 for Perry Nuclear Power Plant Regarding Annulus Exhaust Gas Treatment System Loss of Safety Function 05000440/LER-2016-0042017-02-24024 February 2017 Loss of Safety Function Due to Two Inoperable Standby Liquid Control Subsystems, LER 16-004-00 for Perry Regarding Loss of Safety Function Due to Two Inoperable Standby Liquid Control Subsystems L-16-366, LER 16-03-001 for Perry Nuclear Power Plant Loss of Safety Related Electrical Bus Results in a Loss of Shutdown Cooling2016-12-21021 December 2016 LER 16-03-001 for Perry Nuclear Power Plant Loss of Safety Related Electrical Bus Results in a Loss of Shutdown Cooling L-16-365, LER 16-01-001 for Perry, Unit 1, Regarding Pressure Boundary Leakage, Level 8 Automatic SCRAM, and APRM Loss of Safety Function2016-12-21021 December 2016 LER 16-01-001 for Perry, Unit 1, Regarding Pressure Boundary Leakage, Level 8 Automatic SCRAM, and APRM Loss of Safety Function ML16138A3342016-05-17017 May 2016 ASP Analysis - Reject Perry Nuclear Power Plant, Unit 1 (440-2014-005) ML16138A3362016-05-17017 May 2016 ASP Analysis - Reject Perry Nuclear Power Plant, Unit 1 (440-2014-004) 05000440/LER-2016-0032016-04-0808 April 2016 Loss of Safety Related Electrical Bus Results in a Loss of Shutdown Cooling, LER 16-003-00 for Perry Regarding Loss of Safety Related Electrical Bus Results in a Loss of Shutdown Cooling 05000440/LER-2016-0022016-04-0808 April 2016 Manual Reactor SCRAM Due to Spurious Opening of Safety Relief Valves, LER 16-002-00 for Perry Regarding Manual Reactor SCRAM Due to Spurious Opening of Safety Relief Valve 05000440/LER-2016-0012016-03-23023 March 2016 Pressure Boundary Leakage, Level 8 Automatic SCRAM, and APRM Loss of Safety Function, LER 16-001-00 for Perry Nuclear Power Plant Regarding Drywell Leakage, Level 8 Automatic SCRAM and APRM Loss of Safety Function L-13-194, LER 13-S02-01 for Perry, Unit 1 Regarding Security Weapon Left Unattended2013-06-25025 June 2013 LER 13-S02-01 for Perry, Unit 1 Regarding Security Weapon Left Unattended L-13-143, LER 13-S02-00, for Perry Nuclear Power Plant, Unit 1, Regarding Security Weapon Left Unattended2013-04-30030 April 2013 LER 13-S02-00, for Perry Nuclear Power Plant, Unit 1, Regarding Security Weapon Left Unattended L-13-119, LER 13-S01-00 for Perry Nuclear Power Plant, Unit 1, Regarding Local Power Range Monitors Delivered to the Incorrect Address2013-03-15015 March 2013 LER 13-S01-00 for Perry Nuclear Power Plant, Unit 1, Regarding Local Power Range Monitors Delivered to the Incorrect Address L-12-114, LER 12-S02-00, for Perry Nuclear Power Plant, Unit 1, Regarding Potential Vulnerability in a Safeguards Security System2012-03-22022 March 2012 LER 12-S02-00, for Perry Nuclear Power Plant, Unit 1, Regarding Potential Vulnerability in a Safeguards Security System L-12-083, LER 12-S01-00, Latent Software Error Resulted in Improperly Authorized Visitor Access Into Protected Area2012-02-29029 February 2012 LER 12-S01-00, Latent Software Error Resulted in Improperly Authorized Visitor Access Into Protected Area L-08-052, LER 07-04-001 for Perry Nuclear Power Plant Re Automatic Reactor Protection System Actuation Due to Feedwater Control Power Supply Failure2008-02-15015 February 2008 LER 07-04-001 for Perry Nuclear Power Plant Re Automatic Reactor Protection System Actuation Due to Feedwater Control Power Supply Failure ML0533301242005-11-18018 November 2005 LER 05-03-00 for Perry Nuclear Power Plant Lack of Suction Flow Path Causes High Pressure Core Spray to Be Inoperable ML0509602632004-12-17017 December 2004 Final Precursor Analysis - Perry Grid Loop 2017-06-27
[Table view] |
comments regarding burden estimate to the Information Services Branch (T-2 F43). U.S. Nuclear Regulatory Commission. Washington, DC 20555-0001, or by e-mail to 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 - 004 - 00 Perry Nuclear Power Plant Unit 1 05000-440 YEAR 2017 Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
INTRODUCTION
On August 8, 2017, at 1554 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.91297e-4 months <br />, while the plant was at 100 percent rated thermal power, during restoration from testing of the High Pressure Core Spray (HPCS) [BG] Suppression Pool (SP) [BT] Level High Instrumentation, [LIT] unexpected as-left indications were found that impacted both of the required channels of instrumentation. With both SP level instruments inoperable, a loss of safety function existed.
EVENT DESCRIPTION
On August 8, 2017, at 1321 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.026405e-4 months <br />. surveillance testing commenced on the HPCS SP level high instrumentation and one channel was declared inoperable. On August 8, 2017, at 1554 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.91297e-4 months <br />, during restoration from surveillance testing of the HPCS SP level high instrumentation, unexpected as-left indications were found that impacted both of the required channels of instrumentation. Technical Specification (TS) 3.3.5.1 "Emergency Core Cooling System (ECCS) Instrumentation" condition D was entered. Condition D requires HPCS to be aligned to the SP; however, HPCS was already aligned to the SP since earlier in the day in anticipation of the testing.
On August 8, 2017, at 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br />, venting was performed on the level instrumentation sensing line and the erroneous reading was corrected. The restoration from the venting was completed and the level instrumentation was declared operable on August 8, 2017, at 1747 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.647335e-4 months <br />.
On August 8, 2017, at 2022 hours0.0234 days <br />0.562 hours <br />0.00334 weeks <br />7.69371e-4 months <br />, event notification EN# 52891 was made to the NRC Operations Center to report a loss of safety function.
Suppression Pool Water Level High — TS 3.3.5.1 SP Water Level-High signals are initiated from two level transmitters. The logic is arranged such that either transmitter and associated trip unit can cause the suppression pool suction valve to open and the Condensate Storage Tank (CST) [KA] suction valve to close. This function is implicitly assumed in the accident and transient analyses, which take credit for HPCS, since the analyses assume that the HPCS suction source is the suppression pool.
CAUSE
The cause for the unexpected as-left indications that impacted both of the required channels of instrumentation is related to air entrained in the sensing line caused by air being introduced from air accumulation in the suppression pool over time which moved to a vertical section of the sensing line during venting.
comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission. Washington DC 20555-0001. or by e-mail 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, arid a person is not required to respond to. the information collection.
EVENT ANALYSIS
While venting the instrumentation, the HPCS system was aligned to the suppression pool water source. This source of water is HPCS's safety-related source of water. The automatic suction swap on high suppression pool level is implicitly assumed in the accident and transient analysis since it assumes that the HPCS suction source is the suppression pool. Since the HPCS system was aligned to the suppression pool when the failure occurred, the assumptions of the accident analysis are met, and no safety system functional failure occurred.
Probabilistic Risk Assessment review concludes that the associated event, from a qualitative analysis, is of low risk (small safety) significance. The condition was introduced during the surveillance activity, was identified in a timely manner, and was immediately corrected. Additionally, HPCS was aligned to the inventory source that would have been the inventory source that would have been transferred to given the subject instrumentation functioned appropriately. The function/availability of HPCS was never affected. On this basis, there would be no corresponding change (delta) in core damage frequency (CDF). and no corresponding change (delta) in the large early release frequency (LERF). The delta CDF and delta LERF values would therefore be well below the acceptable thresholds of 1.0E-06/yr and 1.0E-07/yr, respectively, as discussed in Regulatory Guide 1.174. Therefore, the risk of this event is considered small in accordance with the regulatory guidance.
CORRECTIVE ACTIONS
Corrective actions include revising local leak rate testing instruction of the sensing line penetration to perform a fill and vent of the sensing line during every performance to reduce the buildup of entrained air.
PREVIOUS SIMILAR EVENTS
A review of LERs and the corrective action database for the past three years identified no similar events.
COMMITMENTS
There are no regulatory commitments contained in this report. Actions described in this document represent intended or planned actions, are described for the NRC's information, and are not regulatory commitments.
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05000440/LER-2017-001 | Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000440/LER-2017-002 | Loss of Safety Function Due to Main Turbine Bypass Valve Opening LER 17-002-00 for Perry Nuclear Power Plant Regarding Loss of Safety Function Due to Main Turbine Bypass Valve Opening | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000440/LER-2017-003 | Annulus Exhaust Gas Treatment System Loss of Safety Function LER 17-003-00 for Perry Nuclear Power Plant Regarding Annulus Exhaust Gas Treatment System Loss of Safety Function | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000440/LER-2017-004 | Loss of Safety Function for High Pressure Core Spray Suppression Pool Level Instrumentation LER 17-004-00 for Perry re Loss of Safety Function for High Pressure Core Spray Suppression Pool Level Instrumentation | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000440/LER-2017-005 | Controller Malfunction results in Momentary Degradation of Secondary Containment Pressure LER 17-005-00 for Perry Nuclear Power Plant Regarding Controller Malfunction Results in Momentary Degradation of Secondary Containment Pressure | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000440/LER-2017-006 | Loss of Safety Function due to the Inoperability of Both Trains of Motor Control Center Ventilation LER 17-006-00 for Perry Nuclear Power Plant Regarding Loss of Safety Function due to the Inoperability of Both Trains of Motor Control Center Ventilation | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000440/LER-2017-007 | 1 OF | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
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