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Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2 CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122 CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017 Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016 Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068 CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
[Table view] Category:Licensee 30-Day Written Event Report
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('-> DUKE Tom Simril ENERGVc. Vice President Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York . SC 29745 o: 803.701 .3340 f: 803.701 3221 Tom.Simril@duke-energy.com CNS-18-006 January 23, 2018 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Unit 2 Docket Number 50-414 Special Report 2018-01 for the Unit 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days In accordance with Required Action A.2 of the Catawba Nuclear Station Selected Licensee Commitment (SLC) 16.7-4, "Loose-Part Detection System," enclosed is Special Report 2018-01 concerning an occurrence of the Unit 2 Loose Parts Monitoring System having a Collection Region which was non-functional for a period of greater than 30 days. SLC 16.7-4 states that if all channels of one or more Loose-Part Collection Region(s) are non-functional for greater than 30 days , then prepare and submit a Special Report to the Commission outlining the cause of the malfunction and the plans for restoring the channel(s) to FUNCTIONAL status within 40 days.
This occurrence is considered to be of no significance with respect to the health and safety of the public. There are no new regulatory commitments contained in this letter.
Questions on this special report should be directed to Sherry Andrews at 803-701-3424.
Sincerely, Tom Simril Vice President, Catawba Nuclear Station
Enclosure:
Catawba Nuclear Station, Unit 2, Special Report 2018-01 www.duke-energy.com
Document Control Desk Page 2 January 23, 2018 xc:
Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Joseph D. Austin Senior Resident Inspector (Catawba)
U.S. Nuclear Regulatory Commission Catawba Nuclear Station Michael Mahoney (addressee only)
NRC Project Manager (Catawba)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop O-881A 11555 Rockville Pike Rockville, MD 20852-2738 Susan E. Jenkins, Manager S.C. DEHEC Radioactive & Infectious Waste Management jenkinse@dhec.sc.gov
Enclosure Catawba Nuclear Station, Unit 2 Special Report 2018-01 BACKGROUND Catawba Nuclear Station Units 1 and 2 each have a Loose Parts Monitoring System (LPMS) in order to meet Regulatory Guide 1.133, Rev 1, as described in the UFSAR.
The LPMS is an electronic system that monitors the Reactor Coolant System for metal-to-metal impacts in the primary coolant loop. Accelerometer sensors are mounted at various collection regions on the exterior surfaces of the upper reactor vessel, lower reactor vessel, reactor coolant pumps, and steam generators. The signal information from these sensors are amplified and then routed out of containment to the LPMS cabinet mounted in the Control Room.
Selected Licensee Commitment (SLC) 16.7-4 "Loose-Part Detection System" requires at least one channel in a Collection Region to be functional when in Modes 1 and 2. The SLC defines a Loose-Part Collection Region as "an area within the reactor coolant system where loose parts can possibly collect and which is monitored by the Loose-Part Detection System." The SLC identifies these Collection Regions as:
- 1) Lower reactor vessel (3 SLC sensor channels)
- 2) Upper reactor vessel (3 SLC sensor channels)
- 3) Primary side of steam generator A (2 SLC sensor channels)
- 4) Primary side of. steam generator B (2 SLC sensor channels)
- 5) Primary side of steam generator C (2 SLC sensor channels)
- 6) Primary side of steam generator D (2 SLC sensor channels)
The SLC states the secondary side of all the steam generator and the reactor coolant pump channels each have one non-SLC sensor channel which are not part of a Collection Region required by Regulatory Guide 1.133.
Each steam generator (S/G) has two SLC channels on the primary side and one non-SLC channel on the secondary side. The sensor channel locations are physically located close to each other, and if one detects a loose part, it is expected that the other channels in that area would also detect the loose part, regardless of the channel being SLC or non-SLC related.
Since the secondary side channel is specifically excluded from the Collection Region, there are only two channels per SIG SLC required collection region. If one SLC steam generator channel fails, only the remaining SLC channel can be used to meet the SLC.
Operators perform a channel check of each Collection Region channel every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per SLC Surveillance (TR) 16.7-4-1. Operators listen to each channel during the audio check on night shift per the Mode 1 Periodic Surveillance Items procedure.
Maintenance performs a monthly channel functional test to satisfy SLC TR 16.7-4-2, 16.7-4-3, and 16. 7-4-4. The channel functionality is verified by reviewing the preamp bias voltage trend, signal trend screens, and listening to the audio monitor. The alarm function is verified by generating a noise spike on a channel and verifying both the Control Room annunciator and plant computer alarm.
Enclosure Catawba Nuclear Station, Unit 2 Special Report 2018-01 DESCRIPTION OF OCCURRENCE The Unit 2 LPMS does not meet SLC requirements for the 2D Steam Generator Collection Region.
For the 2D Steam Generator, the sensor channels are:
Channel 20 - 2D SIG Secondary (non-SLC)
Channel 21 - 2D SIG Manway (SLC)
Channel 22 - 2D SIG Hot Leg (SLC)
Channel 22 (SLC) was declared non-functional on 1131117. Channel 22 was declared non-functional due to a failed component located inside containment (the sensor, preamp, or interconnecting wiring).
Channel 21 (SLC) was declared non-functional on 12118117. During the monthly channel functional test for the Unit 2 LPMS, the bias voltage on Channel 21 (SLC) was not a steady value as expected. The channel's bias voltage was failing intermittently. The bias voltage source is associated with the channel's preamp which is located inside containment. The preamp bias voltage is necessary for the channel to be functional (detect sound). The loss of bias voltage does not cause a control room annunciator therefore Operations does not receive indication that the channel has lost functionality.
Therefore, both channels of the 2D Steam Generator SLC required Collection Region are non-functional and cannot be repaired prior to a Unit 2 outage. Each channel's location of repair is in a high radiation dose area located inside containment that is inaccessible to personnel during online conditions. The next Unit 2 refueling outage is scheduled for March 2018.
Channel 20 (non-SLC) for the 2D SIG secondary side has been placed into single channel mode. It is expected that the Unit 2 LPMS will still detect a loose part in the 2D SG Collection Region with the non-SLC required Secondary Channel 20.
CAUSE OF THE NON-FUNCTIONALITY The non-functionality is caused by one of the components inside containment is failing or making intermittent connections for both Channels 21 and 22. The components inside containment include the sensor, the preamp, and the interconnecting wiring (terminations). The specific component failure cannot be determined until the components are accessible during the next Unit 2 outage.
CORRECTIVE ACTIONS
- 1. Channel 20 (non-SLC) for the 2D Steam Generator secondary side was placed into single channel mode (it is expected that the Unit 2 LPMS will still detect a loose part in the 2D SG Collection Region).
- 2. Repair and restore functionality for Channel 21 (SLC) for the 2D Steam Generator during the next Unit 2 refueling outage (scheduled for March 2018).
- 3. Repair and restore functionality for Channel 22 (SLC) for the 2D Steam Generator during the next Unit 2 refueling outage (scheduled for March 2018).