7-29-2016 | On June 2, 2016, St. Lucie Units 1 and 2 were in Mode 1 at 100% power. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> FPL declared the containment high range radiation monitors (CHRRMs) inoperable on both Units. FPL determined that the resolution of the-.NRC Information Notice (IN) 97-45 industry Operating Experience ( OE) concerning CHRRMs cabling was less than adequate. The assumed CHRRMs design accuracy could not be assured during some postulated design basis accidents due to the errors introduced by thermal induced currents and water intrusion/cable blistering within the associated detectors' cabling, resulting in inoperable CHRRMs. The Technical Specifications (TSs) require pre- planned alternate means for containment radiation monitoring for inoperable CHRRMs; these requirements were not implemented until June 2016. FPL also submitted a TS 6.9.2 Special Report for two channels of inoperable CHRRMs.
This legacy event was caused by the inadequate evaluation and improper tracking of actions required to fully close the nonconformance identified in the 1997 Information Notice. CHRRMs are used for information, they are not used to control radioactive releases or mitigate accidents. Their inoperability had no significant impact on the health and safety of the public.
FPL plans to replace the CHRRMs cabling susceptible to the phenomenon identified in NRC Information Notice 97-45 and its supplement 1. |
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LER-2016-001, Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical SpecificationsSt. Lucie Unit 1 |
Event date: |
6-2-2016 |
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Report date: |
7-29-2016 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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3352016001R00 - NRC Website |
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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000335/LER-2016-0032017-08-15015 August 2017 Generator Lockout Relay Actuation During Power Ascension Results in Reactor Trip, LER 16-003-01 for St. Lucie, Unit 1, Regarding Generator Lockout Relay Actuation During Power Ascension Results in Reactor Trip 05000389/LER-2017-0012017-04-27027 April 2017 Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements, LER 17-001-00 for St. Lucie, Unit 2 Regarding Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements 05000335/LER-2016-0012016-07-29029 July 2016 Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical Specifications, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical.... L-2016-152, LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Te2016-07-29029 July 2016 LER 16-001-00 for St. Lucie Units 1 and 2 Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Tech L-2010-255, Letter St. Lucie, Unit 2, Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel Failed2010-11-0101 November 2010 Letter St. Lucie, Unit 2, Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel Failed ML0414104442004-05-18018 May 2004 Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel ML18127A6421978-09-22022 September 1978 LER 1978-032-00 for St. Lucie Unit 1, on 08/30/78 Concerning Daily Calibration of Nuc & ^T PWR (Technical Specification 4.3.1.1.1) Was Inadvertently Missed During One Surveillance Interval Encompassing Short Maintenance Outage & Subsequent ML18127A6431978-09-18018 September 1978 LER 1978-031-00 for St. Lucie Unit 1, on 08/16/78 Concerning the Ginca Code Operator Used Incorrect Flux Inputs in Arriving at the Incore Setpoints ML18127A6461978-09-0808 September 1978 LER 1978-030-00 for St. Lucie Unit 1, on 08/10/78 Concerning. the Surveillance Requirement of Specification 4.4.8 Which Requires an Isotopic Analysis for Iodine in the Primary Coolant, Was Inadvertently Missed ML18127A6471978-08-30030 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/31/78 Concerning Containment Vacuum Relief Valve (FCV-25-8) Instrument Air Supply Low Pressure Alarm Was Received. Cause Was Diaphragm Leak in Solenoid Valve Which Controls Instrument Air Supply ML18127A6481978-08-28028 August 1978 LER 1978-026-00 for St. Lucie Unit 1, on 07/30/78 Concerning During PWR Operation Digital Data Processing System Malfunctioned Resulting in Loss of CEA Backup Position Indication & Incore Flux Detector System Used to Monitor Flux D ML18127A6491978-08-25025 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/28/78 Concerning Notification by Applicant'S Vendor of Potential Problem with Certain Motor Operated Valves ML18127A6501978-08-0808 August 1978 LER 1978-011-01 for St. Lucie Unit 1, Update Concerning When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core ML18127A6511978-08-0707 August 1978 LER 1978-025-00 for St. Lucie Unit 1, on 07/24/78 Concerning an Error in the Analysis for the Cask Drop Accident Which Makes the Technical Specification 3.9.14 Non-Conservative ML18127A6521978-07-24024 July 1978 LER 1978-024-00 for St. Lucie Unit 1, on 06/25/78 Concerning During Plant Startup from a Short Maintenance, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8.A Limit of 1.0 Uci/Gram Dose Equivalent ML18127A6531978-07-14014 July 1978 LER 1978-010-00 for St. Lucie Unit 1, One Channel of Steam Generator Low Pressure Measurement for Main Steam Isolation Signal Failed Requiring Action in Accordance with Technical Specification 3. 3. 2. I. B ML18127A6551978-07-13013 July 1978 LER 1978-022-00 for St. Lucie Unit 1, on 06/15/78 Concerning During PWR Operation, the Digital Data Processing System Malfunctioned Due to Malfunctioning Multiplexer Card ML18127A6541978-07-13013 July 1978 LER 1978-023-00 for St. Lucie Unit 1, on 05/15/78 Concerning During Testing Humidity Control Heaters on the Shield Bldg Ventilation System (B Train) Tripped on High Temperatures Due to High Temperature Caused by Low Flow ML18127A6561978-07-0808 July 1978 LER 1978-021-00 for St. Lucie Unit 1, on 06/08/78 Concerning During PWR Ascension Testing Following Refueling Outage CEA #65 Dropped Four Times Due to Failure of One or More of Its Coil PWR Programmer Timing Module, Integral Timer ML18127A6581978-07-0707 July 1978 LER 1978-020-00 for St. Lucie Unit 1, on 06/07/78 Concerning Pwer Ascension Physics Testing Following a Refueling Outage, CEA #65 Dropped ML18127A6601978-06-28028 June 1978 LER 1978-019-00 for St. Lucie Unit 1, on 05/30/78 Concerning During Special Low Pier Feedwater Control System Test a 15% Feedwater Bypass Control Valve Inadvertently Opened Fully Causing Excessive Cooling of 1A Steam Generator ML18127A6611978-06-26026 June 1978 LER 1978-018-00 for St. Lucie Unit 1, on 05/26/78 Concerning CEA #19 Dropped for No Apparent Reason ML18127A6621978-06-13013 June 1978 LER 1978-017-00 for St. Lucie Unit 1, on 05/14/78 Concerning Improper Switching at Pratt & Whitney Substation Combined with Incorrect Wiring of Protective Relays at Midway Substation Led to Deenergization of Midway Substation Resulting in L ML18127A6641978-06-0909 June 1978 LER 1978-016-00 for St. Lucie Unit 1, on 05/26/78 Concerning Containment Pressure-High Trip Setpoint (Table 2.2-1) Appeared to Be in Error During the Refueling Outage ML18127A6651978-05-23023 May 1978 LER 1978-015-00 for St. Lucie Unit 1, on 04/23/78 Concerning Operator Blew Down 1B Bamt Level Instrument to Prevent Sensing Line Blockage, Causing Instrument to Fail High ML18127A6691978-04-28028 April 1978 LER 1978-011-00 for St. Lucie Unit 1, When Upper Guide Structure Was Removed (Refueling Shutdown), 3 (of 45) Incore Instrument Thimbles Remained in the Core ML18127A6681978-04-28028 April 1978 LER 1978-012-00 for St. Lucie Unit 1, on 04/16/78 Concerning Eddy Current Testing Performed on Fuel Assembly CEA Guide Tubes at Unit 1 Showed Near in Guide Tubes Where Tips of Fully Withdrawn CEAs Were Located ML18127A6701978-04-27027 April 1978 LER 1978-013-00 for St. Lucie Unit 1, on 03/28/78 Concerning During Shutdown for Refueling, Dose Equivalent Iodine Exceeded Technical Specification 3.4.8 ML18127A6711978-04-25025 April 1978 LER 1978-010-00 for St. Lucie Unit 1, One Channel of Steam Generator Low Pressure Measurement for the Main Steam Isolation Signal Failed Requiring Action in Accordance with Technical Specification 3.3.2.1.B ML18127A6731978-03-30030 March 1978 LER 1978-009-00 for St. Lucie Unit 1, During PWR Operation Digital Data Processing System Malfunctioned. Apparent Momentary Memory Failure Caused Ddps to Halt ML18127A6741978-03-24024 March 1978 LER 1978-008-00 for St. Lucie Unit 1, Due to an Administrative Error During a Procedure Revision Instructions for Documenting Surveillance of Volume in Diesel Generator Engine Mounted Fuel Tanks Were Omitted ML18127A6781978-02-17017 February 1978 LER 1978-007-00 for St. Lucie Unit 1, Technical Specification 4.3.1.1.3 RTD Response Time ML18127A6791978-02-17017 February 1978 LER 1978-007-00 for St. Lucie Unit 1, Technical Specification 4.3.1.1.3 RTD Response Time ML18144A8051977-12-15015 December 1977 12/15/1977 Memo Reportable Occurrence 335-77-50 ML18110A8681977-10-24024 October 1977 LER 1977-335-39 for St. Lucie, Unit 1 on Refueling Water Tank Piping ML18110A8691977-09-26026 September 1977 LER 1977-335-35 for St. Lucie, Unit 1 on Intake Cooling Water Pump ML18110A8711977-09-15015 September 1977 LER 1977-335-34 for St. Lucie, Unit 1 on Containment Spray Header Valve ML18110A8731977-09-13013 September 1977 LER 1977-335-31 for St. Lucie, Unit 1 on Repair of Leaking Shaft Mechanical Seal of Component Cooling Water Pump ML18110A8741977-09-0909 September 1977 LER 1977-335-33 for St. Lucie, Unit 1 on Steam Driven Auxiliary Feedwater Pump ML18110A8751977-08-31031 August 1977 LER 1977-335-32 for St. Lucie, Unit 1 on Refueling Water Tank Level Setpoint Drift ML18110A8761977-07-14014 July 1977 LER 1977-335-30 for St. Lucie, Unit 1 on Detector Calibration ML18110A8781977-07-0808 July 1977 LER 1977-335-28 for St. Lucie, Unit 1 on Containment Isolation Valve ML18110A8771977-07-0808 July 1977 LER 1977-335-03 for St. Lucie, Unit 1 on Diesel Generator 1A, Update Report No. 1 ML18110A8791977-06-27027 June 1977 LER 1977-335-27 for St. Lucie, Unit 1 on Dropped Control Element Assembly No. 39 Initiating a Turbine Runback ML18110A8801977-06-16016 June 1977 LER 1977-335-26 for St. Lucie, Unit 1 on Off-Site Power ML18110A8821977-06-0303 June 1977 LER 1977-335-25 for St. Lucie, Unit 1 Setpoint of Bistable Trip Unit for Steam Generator Pressure Found Inadequately Conservative ML18110A8831977-05-24024 May 1977 LER 1977-335-29 for St. Lucie, Unit 1 Safety Injection Line Weld ML18110A8841977-05-19019 May 1977 LER 1977-335-29 for St. Lucie, Unit 1 Pressure Boundary Leakage ML18110A8851977-05-15015 May 1977 LER 1977-335-20 for St. Lucie, Unit 1 Ginca Code ML18110A8811977-05-13013 May 1977 LER 1977-335-23 for St. Lucie, Unit 1 on RCS Flow 2017-08-15
[Table view] |
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 Internet 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, and a person is not required to respond to, the information collection.
2016 - 001 0
Description of the Event
On June 2, 2016, St. Lucie Units 1 and 2 were in Mode 1 at 100% power. As discussed in the NRC design basis inspection report 05000335/2016010 and 05000389/2016010, FPL's 1997 evaluation of previous containment high range radiation monitor (CHRRM) [ElISAL:RM] industry Operating Experience (OE) had incorrectly evaluated the impact of thermally induced currents (TIC) and moisture intrusion/cable blistering on Rockbes,tos/Raychem coaxial cable [EllS:IL:CBL1] and their effect on CHRRMs operability. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />; FPL declared the CHRRMs inoperable and entered the appropriate action statements for each Unit. The limiting condition for operation (LCO) for Technical Specification (TS) 3.3.3.1, Action b, Table 3.3-6, Action 15 (Unit 1) and Action 27 (Unit 2), are essentially the same and state that:
"With the number of channels OPERABLE [OPERABLE Channels — Unit 2] less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
1) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and 2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
On June 4, 2016 the preplanned alternate methods for monitoring containment radiation levels were implemented in accordance with operator night orders and enhancements made to plant procedure EPG-08, "Monitoring Plant Equipment Important to the Radiological Emergency Plan," Attachment 2, "Alternate Monitoring Method with the CHRRM Channels Inoperable.
The CHRRMs are used as one of several diverse methods for evaluating emergency action levels (EALs) for the Loss of Fuel Clad Barrier and for the Potential Loss of Primary Containment Barrier in the St. Lucie Emergency Plan (EPlan). Unit differences necessitate different strategies for the Loss of Fuel Clad Barrier EAL determined by CHRRMs indication. These preplanned alternate methods use:
- the containment isolation radiation monitors (Unit 1), or
- the diverse indications as defined in the EAL table to evaluate the loss of the fuel clad barrier (Unit 2) (e.g.
core exit thermocouples, Dose Equivalent 1-131, loss of the core heat removal safety function and entry into emergency operating procedure EOP-15) The Potential Loss of Primary Containment Barrier EAL determined by CHRRMs indication will be provided in part by the use of the post-LOCA radiation monitors with outside containment radiation levels that correlate to the radiation levels inside containment.
Two inoperable CHRRMs require that the NRC be notified of this condition in accordance with TS 6.9.2. FPL submitted the special report on July 16, 2016, in FPL letter L-2016-127.
Cause of the Event
In 1997 and 1998, NRC Information Notice (IN) 97-45 and its supplement 1 notified the industry that the CHRRMs were subject to erratic behavior and possible failure because the expected post-accident environmental conditions within containment could adversely affect the cabling system. FPL's initial disposition of the issue considered the CHRRMs operable due to the short time period the effects lasted, the bounded containment LOCA temperature profiles, and the consideration of the diverse means available for accomplishing post-accident dose assessment, core damage assessment, and emergency plan (EPlan) actions. FPL intended St. Lucie Unit 1 05000335 to close out the potential cabling noncompliance issue as recommended by the Nuclear Utility Group on Equipment Qualification (NUGEQ). However, this intent was not effectively followed through by FPL and the associated tracking action was inappropriately closed by utility personnel. Failure to appropriately track actions to restore compliance is considered a 1997 legacy issue; the corrective action program (CAP) requirements for operability/functionality have been significantly enhanced in the intervening years. FPL plans to replace the subject cabling with alternates resistant to the effects noted in the IN.
Analysis of the Event
This event is reportable under 10 CFR 50.73(a)(2)(i)(B) as "Any operation or condition which was prohibited by the plant's Technical Specifications..." The CHRRMs are designed for accuracy within a factor of 2 over the entire range for post-accident monitoring. However, this design requirement would not have been met during postulated design basis accidents (DBAs). From 1997 until June 2016, this noncompliance resulted in inoperable CHRRMs without the implementation of the required TS pre-planned alternate containment radiation monitoring methods.
The Rockbestos/Raychem coaxial cabling used with the CHHRM detectors in containment is susceptible to the TIC phenomenon that can introduce transient signal errors in excess of the system's design factor of 2 accuracy requirement during short duration large temperature transients, such as those anticipated following a design basis main steam line break (MSLB) inside containment or loss of coolant accident (LOCA). These transient signal errors are directly proportional to the rate of temperature change (positive and negative) and are only functionally significant in the initial seconds to minutes of a DBA. ,The TIC error induced during the initial temperature ramp of some DBAs was calculated to be in excess of 6000 Rem/hr, and quickly decayed to near zero within the first 100 seconds. As the containment cools down post-DBA, the error response will transition to a negative bias. For St. Lucie, the negative bias is expected to be less than -60 Rem/hr at 500 seconds to -8.5 Rem/hr at 3500 seconds.
Cable moisture intrasion/blistering and other phenomenon described in IN 97-45 are driven in part from the temperature peak inside containment, and could lead to a permanent signal bias or cable failure.
FPL performed an extent of condition by reviewing the other radiation monitors at St. Lucie for susceptibility to the effects noted in the IN, and no other components relied for long-term post-accident monitoring' were identified.
Safety Significance
There are no automatic functions provided by CHRRMs on either Unit other than annunciation. The CHRRMs are one of the methods utilized in the St. Lucie Emergency Plan to determine EAL entry conditions, dose assessment, and core damage assessment.
Although the postulated TIC signal error in the first 100 seconds post-DBA results in indicated radiation levels inside containment meeting the EPlan EALs for both the Loss of Fuel Clad and the Potential Loss of Containment, that early in the event there would be no confirmatory evidence to support escalation of the emergency classification beyond the Alert Level. Based on emergency procedure sequence and licensed Operator training for event diagnosis and response, it is considered highly improbable that Operations would declare a Site Area Emergency based solely on the application of the initial containment radiation spike within the Fission Product Barrier EALs.
During the postulated post-DBA containment cooldown, the magnitude of the negative bias introduced by the TIC would be overcome by the actual radiation levels in containment, should fuel damage occur. After approximately one hour, the magnitude of the negative bias is insignificant as compared with any substantive accident dose. In addition, during a DBA with fuel damage, diverse indication for entry into higher EALs which are proceduralized and trained upon would result in licensed operators and members of the Emergency Response Organization to make the correct emergency declaration.
Moisture instrusion/cable blistering is a concern during the higher peak temperatures inside containment associated with DBAs. FPL originally concluded that this was not a concern because of the assumption that the phenomon would only occur at the higher temperatures associated with MSLB. However, the lower temperatures associated with LOCAs do not preclude this degradation mechanism and could result in a long- term erroneous signal bias.
Regardless, the diverse indications as defined in the EAL tables to evaluate the loss of the fuel clad barrier are also available and provide information on the health of the fuel clad barrier. These pre-existing diverse indication independent from CHRRMs include the core exit thermocouples, dose equivalent 1-131, loss of the core heat removal safety function, and entry into the emergency operating procedure Safety Function Staus Checks.
In addition to directing EPlan EAL entry conditions as described above, the CHRRMs also support Emergency Preparedness dose and core damage assessment capabilities. However, dose and core damage assessment continue to be functional without reliance on CHRRMs as the pre-existing procedures and training for members of the Emergency Response Organization and Operations provide diverse means (i.e., core exit thermocouples, reactor vessel water level monitoring system, reactor coolant system activity, and safety function status checks) for obtaining the required information.
Even though the CHRRMs were inoperable during of the time period of concern, diverse indication provides similar information. Therefore this event had no significant impact on the health and safety of the public.
Corrective Actions
1. Alternate pre-planned means for monitoring containment radiation levels were implemented on June 4, 2016.
2. The 14-day TS Special Report for two inoperable CHRRMs channels was submitted on June 16, 2016.
The licensee planned actions listed below have been entered into the site corrective action program. Any changes to the actions will be managed under the corrective action program:
3. FPL is conducting constructability reviews inside containment for cable replacement during the next refueling outages.
4. Based on the constructability reviews and material availability, an implementation schedule will be developed and the more robust coaxial cable design will be installed within the next two refueling outages for each unit.
Failed Component(s) Unit 1: Cable; Manufacturer: Rockestos; Model: RSS-6-104/LD Unit 2: Cable; Manufacturei': Raychem; Model: Flamtrol (XLPE) Similar Events None.