On October 4, 2017 at 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />, while in Mode 1 at 100 percent rated thermal power, inoperability of both A and B trains of Motor Control Center, Switchgear, and Miscellaneous Electrical Equipment Areas Heating, Ventilation, and Air Conditioning System and Battery Rooms Exhaust System (M23/24) occurred. Train A was shutdown and declared inoperable based on excessive drive belt noise and belt malfunction. Train B was inoperable due to ongoing maintenance on its associated chilled water system. The combination of inoperability resulted in a loss of safety function. Technical Specification (TS) 3.0.3 was entered per plant procedures, and at 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> a plant shutdown was commenced. At 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br />, the A train of M23/24 was declared operable following belt replacement and TS 3.0.3 was exited. The plant was restored to 100 percent rated thermal power at 0804 hours0.00931 days <br />0.223 hours <br />0.00133 weeks <br />3.05922e-4 months <br />.
The cause was determined to be inadequate procedural guidance in that the "general tensioning" method described in plant maintenance procedure, V-belt and Sheave Maintenance, is insufficient for restoring components to a reliable condition. Corrective action includes revising the procedure for correct tensioning guidance.
The safety significance of this event is considered to be very small. This event is being reported in accordance with 10CFR50.73(a)(2)(v)(B), 10CFR50.73(a)(2)(v)(C), and 10CFR50.73(a)(2)(v)(D) as an event or condition that could have prevented the fulfilment of a safety function.
NRC FORM 386 (06-2016) |
LER-2017-006, Loss of Safety Function due to the Inoperability of Both Trains of Motor Control Center VentilationPerry Nuclear Power Plant |
Event date: |
|
---|
Report date: |
|
---|
Reporting criterion: |
10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
---|
Initial Reporting |
---|
ENS 53000 |
10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material |
---|
4402017006R00 - NRC Website |
|
Similar Documents at Perry |
---|
Category:Letter
MONTHYEARIR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 ML24003A8032024-01-0303 January 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML23321A0472023-12-20020 December 2023 Letter to Rod L. Penfield - Perry Nuclear Power Plant, Unit 1 - License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 ML23292A2482023-10-19019 October 2023 Fws to NRC, Federal Agency Coordination Under ESA Section 7 for Perry Nuclear Plant, Unit 1, License Renewal, and Concurrence with Not Likely to Adversely Affect Determination for Northern Long-eared Bat ML23292A2472023-10-19019 October 2023 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 ML23249A1032023-10-0303 October 2023 Letter to Rod L. Penfield, Site Vice President-Perry Nuclear Power Plant, Unit 1-Notice of Intent to Conduct Scoping Process and Prepare an Environmental Impact Statement ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23261B0192023-09-25025 September 2023 Aging Management Audit Plan Regarding the License Renewal Application Review ML23261C3642023-09-25025 September 2023 License Renewal Application Online Reference Portal ML23256A3592023-09-22022 September 2023 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Energy Harbor Nuclear Corp. Application for License Renewal L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000440/20234012023-08-28028 August 2023 Public - Perry Nuclear Power Plant Security Baseline Inspection Report 05000440/2023401 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000440/20230052023-08-24024 August 2023 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2023005) ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML23227A2202023-08-15015 August 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Perry Nuclear Power Plant L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000440/20230022023-08-0202 August 2023 Integrated Inspection Report 05000440/2023002 L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative ML23198A2842023-07-17017 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant IR 05000440/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection Report 05000440/2023010 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener ML23144A3562023-05-25025 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End of Cycle Plant Performance Assessment of Perry Nuclear Power Plant, Unit 1 L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) IR 05000440/20230012023-05-0404 May 2023 Integrated Inspection Report (05000440/2023001) L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report 2024-01-30
[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 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.
- 006 - 00 05000-440 YEAR 2017 Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
INTRODUCTION
On October 4, 2017, at 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />, while in Mode 1 and 100 percent rated thermal power, inoperability of both trains of Motor Control Center, Switchgear, and Miscellaneous Electrical Equipment Areas Heating, Ventilation, and Air Conditioning System and Battery Rooms Exhaust System (M23/24) occurred. This resulted in a loss of safety function.
This event is being reported in accordance with 10CFR50.73(a)(2)(v)(B), 10CFR50.73(a)(2)(v)(C), and 10CFR50.73(a)(2)(v)(D) as an event or condition that prevented the fulfilment of a safety function.
EVENT DESCRIPTION
On October 4, 2017 at 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />, with the plant in Mode 1 and at 100 percent rated thermal power, M23/24 Train A was shutdown and declared inoperable due to a report of excessive drive belt noise and malfunctioning belts on the A supply fan [AHU]. Concurrently, Control Complex Chilled Water (CCCW) Chiller B [KM] was out of service for planned maintenance resulting in Train B of M23/24 being inoperable. This combination resulted in a loss of safety function due to the impact to Division 1,2, and 3 electrical switchgear.
At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, M23/24 was shifted from train A to train B. CCCW Chiller C was already running and had been started at 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br /> on 10/03/17. Cooling to the affected areas through the B train of M23/24 was maintained through use of the nonsafety related CCCW Chiller C, which is able to supply either train with chilled water.
Due to the inoperability of both trains of M23/24, actions were taken in LCO 3.8.7 for Alternating Current (AC) [EA] and Direct Current (DC) [EJ] Distribution Systems, LCO 3.8.4 for DC Sources, LCO 3.8.1 for AC Sources, and the associated support systems. The High Pressure Core Spray System (HPCS) [BC] was also declared inoperable, which is a single train safety system, and therefore an additional loss of safety function.
On October 04, 2017 at 0553 hours0.0064 days <br />0.154 hours <br />9.143518e-4 weeks <br />2.104165e-4 months <br />, event notification EN# 53000 was made to the NRC Operations Center in accordance with 50.72(b)(2)(i) & 50.72(b)(3)(v)(D) for initiation of plant shutdown and loss of safety function. Train A of M23/24 was declared operable at 0620, following belt replacement, and TS 3.0.3 was exited. The plant was restored to 100 percent rated thermal power at 0804 hours0.00931 days <br />0.223 hours <br />0.00133 weeks <br />3.05922e-4 months <br />.
At 0926 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.52343e-4 months <br />, the event notification reporting requirements were updated to include 50.72(b)(3)(v)(B) and 50.72(b)(3)(v)(C), in addition to 50.72(b)(3)(v)(D).
CAUSE
With the B train of the M23 system out of service for maintenance, the belt malfunction on the A train supply fan resulted in a loss of safety function and entry into Technical Specification 3.0.3. It was determined that two V-belts on the M23 A supply fan malfunctioned due to inadequate tensioning. The cause was determined to be inadequate procedural guidance in that the "general tensioning" method supplied in plant maintenance procedure, V-belt and Sheave Maintenance, which requires only a visual check of belt sag, is insufficient for restoring components utilizing V- belts to a reliable operating condition.
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 used to impose an information collection does not display a currently void OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 006 - 00 Perry Nuclear Power Plant Unit 1 05000-440 YEAR 2017
EVENT ANALYSIS
A Probabilistic Risk Assessment (PRA) evaluation was performed. The analysis indicates that the event resulted in a very small change to overall plant risk with a change (delta) in core damage frequency (CDF) of 1.78E-09/yr, and a change (delta) in the large early release frequency (LERF) of 1.11E-09/yr. The delta CDF and delta LERF values are 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 safety significance of this event is considered to be very small.
CORRECTIVE ACTIONS
Corrective actions in response to the event include: revising the maintenance procedure to use the Force Deflection Method for tensioning of the belts; replacing the M23 A supply fan drive belts and restoring M23/24 to operable; and performing an additional check of belt tension on the same train exhaust fan along with the opposite train supply and exhaust fans. Additionally, the belts for the Auxiliary Building ventilation EVE] exhaust fans will be checked.
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.
|
---|
|
|
| | Reporting criterion |
---|
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 |
|