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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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ef~DUKE Tom Simril
~JENERGY~ Vice President Catawba Nuclear Station Duke Energy CN01 VP I 4800 Concord Road York, SC 29745 o: 803. 701.3340 f: 803. 701.3221 Tom.Simril@duke-energy.com CNS-17-021 April 20, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Special Report 2017-01 for the Units 1 and 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," attached is Special Report 2017-01 concerning an occurrence of the Units 1 and 2 Loose Parts Monitoring System having Collection Regions which were 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,
-iOYY\~
Tom Simril Vice President, Catawba Nuclear Station Attachment
Document Control Desk Page 2 April 20, 2017 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 0-8H4A 11555 Rockville Pike Rockville, MD 20852-2738 S.E. Jenkins Manager Radioactive and Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201
,i.
Attachment Catawba Nuclear Station, Units 1 and 2 Special Report 2017-01 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" states the requirements of the LPMS. SLC 16.7-4 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 lists the Collection Regions:
- 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 s_ensor channels)
- 6) Primary side of steam generator D (2 SLC sensor channels)
The SLC states the secondary side of all the steam generators and reactor coolant pumps channels (each having 1 non-SLC sensor channel) are not in a Collection Region required by Regulatory Guide 1.133.
Each steam generator has two SLC and one non-SLC sensor channels. The sensor channel locations are 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. Because the steam generator channels located on secondary side are excluded from the Collection Region, if one SLC steam generator channel fails, orily the remaining SLC channel can be used to meet the SLC.
As described in the LPMS User Manual, the LPMS uses a feature called Single Channel Alarm Inhibit (SCA lnh) to reduce false alarms on the system. This feature prevents an event from being reported if only a single channel alarms. This method is based on the assumption that any true loose part would trigger more than one sensor. This feature requires more than one channel to meet the alarm criteria at the same time in order for the LPMS to generate a Control Room alarm. This feature can be activated or overridden on a per channel basis by user-specified settings. The default is that SCA lnh is active. Therefore, if only one SLC channel is active in a Collection Region, in order for the channel to be considered functional per the SLC, that channel's SCA lnh Override must be selected so that the LPMS will trigger an alarm with only one SLC channel alarm from that Collection Region.
A channel check is performed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per SLC Surveillance 16.7-4-1 of each Collection Region channel. The audio check is performed each night shift per the Mode 1 Periodic Surveillance Items procedure.
DESCRIPTION OF OCCURRENCE The Unit 1 LPMS did not meet SLC requirements for the 1C Steam Generator Collection Region from 12123115 to 3116117.
For the 1C Steam Generator, the sensor channels are:
Channel 7 - 1C SIG Manway (SLC)
Channel 8 - 1C SIG Hot Leg (SLC)
Channel 16 - 1C SIG Secondary (non-SLC)
Channel 8 (SLC) for the 1C SIG region was disabled on 12123115 due to a problem on the channel. This resulted in the 1C SIG region having one SLC and one non-SLC channel active.
While this is sufficient for the Unit 1 LPMS to detect a loose part in this region, this does not meet SLC requirements. Channel 7 (SLC) would need the SCA lnh Override setting enabled to meet SLC requirements to allow the single active SLC channel to alarm. This was performed on 3116117. During this time, it is expected that the Unit 1 LPMS would have detected a loose*
part in that area due to the non-SLC required Secondary Channel 16 in the area remaining functional. Also, the nightly audio channel checks did not observe any unusual noises during this time.
The Unit 1 LPMS did not meet SLC requirements for the 1A Steam Generator Collection Region from 2118116 to 3116117.
For the 1A Steam Generator, the sensor channels are:
Channel 9 - 1A SIG Manway (SLC)
Channel 10 - 1A SIG Hot Leg (SLC)
Channel 18 - 1A SIG Secondary (non-SLC)
Channel 9 (SLC) for the 1A SIG region was disabled on 2118116 due to a problem on the channel. Channel 18 (non-SLC) for the 1A SIG region was also disabled during this time due to a previous modification to a circuit card. With both of these channels disabled, only Channel 10 (SLC) was active for the 1A SIG region, and required the SCA lnh Override setting ~nabled to be able to detect loose parts in the region. The Override setting was enabled on 3116117.
During this time, the nightly audio checks did not detect any unusual noises. Additionally, the LPMS has not detected a loose part on Channel 10 after activation of the SCA lnh Override on 3116117. Therefore, there is no concern of an unidentified loose part in this region.
The Unit 2 LPMS did not meet SLC requirements for the 2D Steam Generator Collection Region from 11114116 to 3116117.
For the 20 Steam Generator, the sensor channels are:
Channel 20 - 2D SIG Secondary (non-SLC)
Channel 21 - 2D SIG Manway (SLC)
Channel 22 - 20 SIG Hot Leg (SLC)
On 11/14/16, Channel 21 (SLC) developed a problem which was discovered 11/16/16 during monthly channel functional test. The channel was disabled per procedure. On 3/7/17, Channel 22 (SLC) developed a field problem and was disabled per procedure. On 3/9/17, the problem on Channel 21 cleared, and the channel was re-enabled. When both of these channels were disabled, the system was not able to detect loose parts in the 20 SIG region. When only one of these channels was disabled, the system could detect a loose part in this region, but the SCA lnh Override setting would need to be enabled to meet SLC requirements. The Override setting was enabled on 3/16/17. With the exception of the time period between 3/7/17 and 3/9/17, it is expected that the Unit 2 LPMS would have detected a loose part in the 20 SG Collection Region due to the non-SLC required Secondary Channel 20 in the area remaining functional.
Also, the nightly audio channel checks did not observe any unusual noises.
CAUSE OF THE NON-FUNCTIONALITY For both Units 1 and 2, a legacy deficiency was identified with the Loose Parts Monitoring System Channel Functional Test procedure on 3/14/17. The procedure did not provide guidance to activate the Single Channel Alarm Inhibit (SCA lnh) Override in the case of only one SLC channel active in a region. In addition, the procedure allowed all SLC channels in a region to be disabled (Unit 2 SLC Channels 21 and 22 were both disabled from 3/7/17 to 3/9/17).
CORRECTIVE ACTIONS
- 1) The Loose Parts Monitoring System Channel Functional Test procedure was updated to include instructions for the following:
- a. Direction to activate Single Channel Alarm Inhibit Override, if the channel in question is the only SLC channel in a region, or when disabling a collection channel.
- b. Steps to prevent all SLC channels in a region from being inadvertently disabled.
- c. Additional guidance for monthly testing to ensure that if a channel has its SCA lnh Override enabled, it remains enabled after testing is complete. Testing currently enables and disables SCA lnh Override as part of the testing, and the new instructions prevent this setting from accidentally being changed.
- 2) Restore Units 1 and 2 LPMS to functionality:
- a. After the Loose Parts Monitoring System Channel Functional Test procedure was updated, the SCA lnh Override feature was enabled for Unit 1 Channels 7 and 10, and Unit 2 Channel 21 on 3/16/17.
- b. Portions of the procedure were used as a functional test to ensure the channels would alarm as expected.