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Category:Letter
MONTHYEARIR 05000333/20240032024-11-12012 November 2024 Integrated Inspection Report 05000333/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20240902024-10-29029 October 2024 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000333/2024090 JAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation IR 05000333/20244022024-10-28028 October 2024 Material Control and Accounting Program Inspection Report 05000333/2024402 (Cover Letter Only) ML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24282B0302024-10-11011 October 2024 Project Manager Assignment RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 ML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 05000333/LER-2023-004, For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem2023-12-0101 December 2023 For James A. Ftizpatrick Nuclear Power Plant, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG a Subsystem 05000333/LER-2022-003-02, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2023-09-0808 September 2023 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2023-002-01, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-08-14014 August 2023 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-2023-003, Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem2023-06-23023 June 2023 Emergency Diesel Generator Fuel Oil Supply Procedure Error B Subsystem 05000333/LER-2023-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2023-06-13013 June 2023 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 05000333/LER-1922-003-01, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2023-04-28028 April 2023 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System2023-04-19019 April 2023 Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System 05000333/LER-2022-002-01, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation2023-01-31031 January 2023 Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation 05000333/LER-2021-001-01, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas2023-01-10010 January 2023 Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas 05000333/LER-2022-003, Safety Relief Valves Lift Setpoint Found Out of Tolerance Low2022-11-30030 November 2022 Safety Relief Valves Lift Setpoint Found Out of Tolerance Low 05000333/LER-2022-002, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation2022-11-22022 November 2022 Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation 05000333/LER-2022-001, Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure2022-06-28028 June 2022 Exhaust Drain Pot Line Filled with Water Up to HPCI Turbine Due to Relay Failure 05000333/LER-2021-003, Air Solenoid Valve Condition Results in Main Steam Isolation Valve (MSIV) Fast Closure Test Failure2022-01-14014 January 2022 Air Solenoid Valve Condition Results in Main Steam Isolation Valve (MSIV) Fast Closure Test Failure 05000333/LER-2021-002, Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure2022-01-14014 January 2022 Automatic High Pressure Coolant Injection (HPCI) System Function Prevented by Control Circuit Relay Failure 05000333/LER-2021-001, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas2021-10-22022 October 2021 Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas 05000333/LER-2020-003-01, High Pressure Coolant Injection Inoperable Due to Oil Leak2021-09-0808 September 2021 High Pressure Coolant Injection Inoperable Due to Oil Leak 05000333/LER-2020-003, High Pressure Coolant Injection Inoperable Due to Oil Leak2020-06-0909 June 2020 High Pressure Coolant Injection Inoperable Due to Oil Leak 05000333/LER-2020-002, Unanalyzed Condition Due to Unprotected Control Circuits Running Through Multiple Fire Areas2020-04-14014 April 2020 Unanalyzed Condition Due to Unprotected Control Circuits Running Through Multiple Fire Areas 05000333/LER-2020-001, Automatic Scram Due to Main Turbine Trip on High RPV Water Level2020-03-31031 March 2020 Automatic Scram Due to Main Turbine Trip on High RPV Water Level JAFP-17-0051, LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System2017-06-0505 June 2017 LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System 05000333/LER-2017-0012017-03-13013 March 2017 Vent Line Socket Weld Failure, LER 17-001-00 for James A. Fitzpatrick Nuclear Power Plant RE: Vent Line Socket Weld Failure 05000333/LER-2016-0042016-08-23023 August 2016 Transformer Fault Results in Manual Scram and Secondary Containment Vacuum Below Technical Specification Limit, LER 16-004-00 for James A. Fitzpatrick Regarding Transformer Fault Results in Manual Scram and Secondary Containment Vacuum Below Technical Specification Limit 05000333/LER-2016-0032016-08-0303 August 2016 Concurrent Opening of Reactor Building Airlock Doors, LER 16-003-00 for James A. FitzPatrick Regarding Concurrent Opening of Reactor Building Airlock Doors 05000333/LER-2016-0022016-04-25025 April 2016 Sticking DC Pilot in Solenoid Valve Cluster Assembly Results in Slow MSIV Closures, LER 16-002-00 for James A. Fitzpatrick Nuclear Power Plant, Regarding Sticking DC Pilot in Solenoid Valve Cluster Assembly Results in Slowly MSIV Closure 05000333/LER-2016-0012016-03-23023 March 2016 System Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer, LER 16-001-00 for James A. FitzPatrick Regarding System Actuations during Manual Scram in Response to Frazil Ice Blockage and Residual Transfer 05000333/LER-2015-0082016-02-16016 February 2016 Containment Atmosphere Dilution System Reliability Degraded due to Manufacturer Defect in Temperature Transmitters, LER 15-008-00 for James A. Fitzpatrick Regarding Containment Atmosphere Dilution System Reliability Degraded Due to Manufacturer Defect in Temperature Transmitters 05000333/LER-2015-0062016-02-0404 February 2016 Transitory Secondary Containment Differential Pressure Excursions, LER 15-006-01 for James A. FizPatrick Regarding Transitory Secondary Containment Differential Pressure Excursions 05000333/LER-2015-0072016-02-0101 February 2016 Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit, LER 15-007-00 for James A. Fitzpatrick Regarding Slow Exhaust Fan Start Leads to Secondary Containment Vacuum Below Technical Specification Limit ML1015505722009-12-28028 December 2009 Event Notification for Fitzpatrick on Offsite Notification for Elevated Tritium Levels ML0509505652004-12-17017 December 2004 Final Precursor Analysis - Fitzpatrick Grip Loop 2024-09-04
[Table view] |
LER-2021-001, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas |
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text
Constellation ~
James A. FilzPatrick NPP PO Box110 Lycoming. NY 13093 JAFP-23-0001 January 10, 2023 Timothy C. Peter Site Vice President-JAF United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Subject:
Reference:
Dear Sir or Madam:
James A FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-059 NRC Docket No. 50-333 LER: 2021-001-01, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas FitzPatrick letter, LER: 2021-001, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas, JAFP-21-0096, dated October 22, 2021 This report is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(B). This supplement is being submitted to clarify and add more detail to the reported condition and does not change the intent of the original report.
There are no new regulatory commitments contained in this report.
Questions concerning this report may be addressed to Mr. Mark Hawes, Regulatory Assurance Manager (acting), at (315) 349-6659.
TCP/mh Enclosure:
LER: 2021-001-01, Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas cc:
USNRC, Region I Administrator USNRC, Project Manager USNRC, Resident Inspector INPO Records Center (IRIS)
NRC FORM 366 (08-2020)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (08-2020)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023
- 1. Facility Name James A. FitzPatrick Nuclear Power Plant
- 2. Docket Number 05000333
- 3. Page 1 OF 4
- 4. Title Inadequate Protection Devices for DC Motor Field Shunt Cables Through Separate Fire Areas
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved
Month
Day
Year
Year Sequential Number Revision No.
Month Day Year Facility Name N/A Docket Number N/A 08 24 2021 2021 - 001 - 01 01 10 2023 Facility Name N/A Docket Number N/A
- 9. Operating Mode 1
- 10. Power Level 100 Month Day Year No Yes (If yes, complete 15. Expected Submission date)
Abstract (Limit to 1560 spaces, i.e., approximately 15 single-spaced typewritten lines)
During an extent of condition review for unprotected circuits, the James A. FitzPatrick Nuclear Power Plant (JAF) staff identified three cables for which a postulated fire event could potentially short circuit and cause secondary cable damage. The main circuit breakers in the motor control center compartment do not provide adequate protection of the shunt field circuit cable. This condition affects the DC motors to 27MOV-123, torus exhaust isolation bypass valve, 23MOV-14, HPCI turbine steam inlet isolation valve, and 23MOV-24, HPCI full flow test return to condensate storage isolation valve. The cables for these circuits are routed thru fire areas in South Cable Tunnel, Reactor Building Eastside, and Reactor Building West Crescent; where safe shutdown equipment could be affected by this condition.
The cause of the condition is that the original plant design, prior to 10 CFR 50 Appendix R, did not include overcurrent protection for DC motor shunt field cables in all applicable Safe Shutdown Analysis circumstances.
Compensatory actions were established for the affected Fire Zones and modifications were completed for the affected circuits.
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
(See Page 3 for required number of digits/characters for each block)
LICENSEE EVENT REPORT (LER)
=
Background===
The James A. FitzPatrick Nuclear Power Plant (JAF) 10 CFR 50 Appendix R Safe Shutdown Analysis is based on the occurrence of a single fire. The only failures that are considered are those directly attributable to the fire, and spurious operations that can be postulated to occur as a result of the fire. No other concurrent failures are assumed to occur (i.e., single failure).
Fire areas are established to meet the separation requirements of Section III.G of Appendix R for safe shutdown systems. The fire areas at JAF are further sub-divided into fire zones.
It is postulated that a fire in one fire area could cause a short-circuit, cause overcurrent and overheat cables, then produce secondary damage to adjacent cables in other fire areas where the cables are routed. Fuses in electrical circuits prevent this type of propagation.
Secondary cable failures are outside the assumptions of the 10 CFR 50 Appendix R Safe Shutdown Analysis.
In a direct current (DC) shunt motor, the armature and field (shunt) windings are connected in parallel. The shunt (field) windings of a DC shunt motor are made of smaller gauge wire, but they have many more turns than a series-wound DC motor. The high number of turns allows a strong magnetic field to be generated, but the smaller gauge wires provide a high resistance and limit the current flowing through the shunt coil.
Event Description On August 24, 2021, an extent of condition evaluation from the condition reported by LER: 2020-002, identified three additional circuits, vulnerable to a potential hot short condition impacting secondary fire areas.
The three circuits identified are associated with DC Motors with field shunt cables that transverse multiple fire areas. The feeder breaker protects the armature cables but the smaller 12 AWG (American Wire Gauge) field shunt cables are inadequately protected by the feeder breaker. In the event of a fire-induced hot short, the potential exists, based on the available fault current, cable size, and characteristics of the protective device, for the shunt cable to be overheated.
This situation has the potential to cause secondary cable failures that are outside the assumptions of the 10 CFR 50 Appendix R Safe Shutdown Analysis. This condition was reported to the NRC on August 24, 2021 (ENS 55427) per 10 CFR 50.72(b)(3)(ii)(B). The required actions of the Technical Requirement Manual (TRM) 3.7.M, Fire Barrier Penetrations, were established for the affected fire areas. U.S. NUCLEAR REGULATORY COMMISSION (08-2020)
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023
- 3. LER NUMBER James A. FitzPatrick Nuclear Power Plant 05000 - 333 YEAR SEQUENTIAL NUMBER REV N0.
2021
- - 001
- - 01 Page 3 of 4 (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
Event Analysis This condition identified the smaller gauge cables connected to the DC motor shunt field. The cables connected to the armature and series field are of sufficient size to be protected by a 40 or 70 ampere (A) breaker at the Motor Control Center (MCC) and the control circuits are protected by 15 A fuses in series with the breaker.
The 12 AWG shunt field cables were evaluated using the guidance of NUREG-1805 and NUREG/CR-5384.
For thermoset insulated cable failures to impact adjacent cables, the temperature that the conductor reaches at given specified current, for a specified time duration, needs to be conducive to this type of damage propagation. At higher fault currents, the DC motor breaker would likely trip prior to cable ignition. However, under some fault current circumstances, the evaluation discovered that these 12 AWG cables are vulnerable to this type of failure. The evaluation further identified that the vulnerable cables were within common enclosures with other equipment cables required for safe shutdown in secondary fire areas.
The following DC motor field shunt cables may impact credited safe shutdown equipment for fires initiated in the following areas:
Cable Equipment Noncompliant Fire Area 1PCPARK107 71BMCC-1 to 27MOV-123 Torus exhaust isolation valves 27AOV-117 and 27AOV-118 outbound bypass valve 09 - Reactor Building Eastside 11 - South Cable Tunnel 1HPIBBK006 71BMCC-2 to 23MOV-14 HPCI turbine steam inlet isolation valve 18 - Reactor Building West Crescent 1HPIBBK024 71BMCC-4 to 23MOV-24 HPCI Full Flow test return to condensate storage downstream isolation valve 18 - Reactor Building West Crescent Since the degree of separation for redundant safe shutdown trains is lacking, the event is reportable as an unanalyzed condition that significantly degraded plant safety. Therefore, this report is being submitted in accordance with 10 CFR 50.73(a)(2)(ii)(B), a condition that resulted in the plant being in an unanalyzed condition that significantly degraded plant safety.
Cause The overcurrent protection is not sufficient in all applicable DC shunt field cables which can impact the 10 CFR 50 Appendix R Safe Shutdown Analysis. This condition has existed since original plant design. U.S. NUCLEAR REGULATORY COMMISSION (08-2020)
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023
- 3. LER NUMBER James A. FitzPatrick Nuclear Power Plant 05000 - 333 YEAR SEQUENTIAL NUMBER REV N0.
2021
- - 001
- - 01 Page 4 of 4 (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
Similar Events FitzPatrick, LER: 2013-003-00, Unfused DC Ammeter Circuits Result in Unanalyzed Condition, JAFP-13-0158, dated December 26, 2013.
FitzPatrick, LER: 2020-002-00, Unanalyzed Condition due to Unprotected Control Circuits Running through Multiple Fire Areas, JAFP-20-0032, dated April 14, 2020.
The condition being reported in this report was identified during a Corrective Action Program (CAP) extent of condition review from LER: 2020-002-00. These two LER and the condition reported address unprotected cables which may potentially cause secondary fires such that the safe shutdown analysis is impacted.
Corrective Actions Compensatory actions for the affected fire areas were established in accordance with TRM 3.7.M.
Modifications to add protective devices (i.e, fuses) to the affected circuits was completed in October 2021 (Engineering Change (EC) 634899).
Other DC Motor shunt field cables that were evaluated to not affect safe shutdown analysis are being addressed in the corrective action process (IR 04442380).
An alternating current (AC) extent of condition evaluation concluded that no AC circuit affects the safe shutdown analysis. Circuits evaluated as not fully protected is addressed in CAP.
Safety Significance Nuclear safety - There were no actual consequences caused by this condition. The potential consequence of a hot short condition is for a fire damage in one fire area to damage other cables in more than one fire area.
This may cause a loss of safe shutdown capability outside the analysis of the Safe Shutdown Analysis. The risk of fire damage is mitigated by fire protection equipment and the availability of Fire Brigade members trained to respond to fire accident scenarios.
References JAF Issue Report IR 04442380, August 24, 2021 JAF-RPT-FPS-01975, Revision 5, 10CFR50 Appendix R Safe Shutdown Analysis Report (SSAR)