05-11-2017 | On March 10, 2017, during a Technical Specification surveillance, the as-found operating time of one of four undervoltage timing relays in a Safety related 4.16kV switchgear was greater than the Technical Specification allowable value. The relay was retested without making any changes to the relay timing or the test configuration.
The second test resulted in a lower value that was within the Technical Specification allowable value but outside the acceptance criteria of the procedure. A third test (and subsequent follow-up testing) resulted in values that met Technical Specification limits. The associated channel was declared Operable.
On March 14, 2017, an engineer reviewed the surveillance results and questioned the reliability of the relay based on its behavior. The Control Room was contacted and the relay was replaced. Based on the engineer's analysis, the Shift Manager determined that the relay should not have been declared Operable on March 10. The Technical Specification Action Statement required the inoperable channel to be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This Action was not met and is reportable as a condition prohibited by Technical Specifications per 10 CFR 50.73(a)(2)(i)(B). The event was of very low risk significance and no radioactive release occurred; therefore, there was no adverse effect on the health and safety of the public. |
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Category:Letter
MONTHYEARML24318C5082024-11-13013 November 2024 Condition Prohibited by Technical Specifications IR 05000498/20253012024-11-0707 November 2024 Notification of NRC Initial Operator Licensing Examination 05000498/2025301; 05000499/2025301 IR 05000498/20240032024-11-0707 November 2024 Integrated Inspection Report 05000498/2024003 and 05000499/2024003 ML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24290A1162024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal ML24249A3372024-09-0404 September 2024 Inservice Inspection Summary Report - 2RE23 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators ML24234A0912024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24213A0842024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update NOC-AE-240040, Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML24318C5082024-11-13013 November 2024 Condition Prohibited by Technical Specifications 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-004, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-02-0505 February 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water 05000499/LER-2023-002, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus2024-01-30030 January 2024 Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus 05000499/LER-2023-001, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-01-15015 January 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-01-0909 January 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open2023-07-26026 July 2023 Supplement to Pressurizer Power Operated Valve Failed to Open 05000498/LER-2023-001, Pressurizer Power Operated Relief Valve Failed to Open2023-06-12012 June 2023 Pressurizer Power Operated Relief Valve Failed to Open 05000499/LER-2021-002-01, Supplement to Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System2022-07-0505 July 2022 Supplement to Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System 05000499/LER-2022-001, From South Texas Project Unit 2, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus2022-03-0303 March 2022 From South Texas Project Unit 2, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus 05000499/LER-2021-002, Re Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System2021-12-21021 December 2021 Re Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System 05000499/LER-2021-001, Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve2021-09-0909 September 2021 Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve 05000498/LER-2021-001, Frozen Common Sensing Line Results in Loss of Two Main Feedwater Pumps Leading to Automatic Reactor Protection and Auxiliary Feedwater Systems Actuations Due to Low Steam Generator Level2021-04-15015 April 2021 Frozen Common Sensing Line Results in Loss of Two Main Feedwater Pumps Leading to Automatic Reactor Protection and Auxiliary Feedwater Systems Actuations Due to Low Steam Generator Level 05000498/LER-2020-001, Automatic Actuation of Emergency Diesel Generators Due to Lockout of Switchyard Electrical Bus2020-05-22022 May 2020 Automatic Actuation of Emergency Diesel Generators Due to Lockout of Switchyard Electrical Bus 05000498/LER-2017-0022018-01-22022 January 2018 Unit 1 Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil, LER 17-002-00 for South Texas Project, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil 05000498/LER-2017-0012017-05-11011 May 2017 Unit 1 failure of a timing relay during a Technical Specification surveillance, LER 17-001-00 for South Texas, Unit 1, Regarding Failure of a Timing Relay During a Technical Specification Surveillance 05000498/LER-2016-0022016-06-29029 June 2016 Unit 1 Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip due to Generator Lockout, LER 16-002-00 for South Texas Project, Unit 1, Regarding Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip Due to Generator Lockout 05000498/LER-2016-0012016-03-22022 March 2016 Unit 1 Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed, LER 16-001-00 for South Texas Project, Unit 1, Regarding Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed NOC-AE-05001865, LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak2005-04-0505 April 2005 LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak NOC-AE-04001681, LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B2004-02-18018 February 2004 LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B NOC-AE-00000840, 1,Unauthorized Entry Into Protected Area,Safeguards Event Report2000-05-0404 May 2000 1,Unauthorized Entry Into Protected Area,Safeguards Event Report 2024-09-19
[Table view] |
I. Description of Event
A. Reportable event classification
Since Technical Specification 3.3.2, Action 20A was not met, this event is reportable under 10 CFR 50.73(a)(2)(i)(B).
B. Plant operating conditions prior to event
Prior to the event at 1045 on March 10, 2017, Unit 1 was operating in Mode 1 at 100 percent power.
D. Narrative summary of the event
During a Technical Specification surveillance, the as-found operating time (3.295 seconds) of a timing relay (Undervoltage Agastat Timing Relay, model number ETR14D3A004, made by TE Connectivity, system identifier EB, component identifier 62), installed in a safety related 4160 kV switchgear, was greater than the Technical Specification allowable value equal to or less than 1.93 seconds. The performers of the surveillance measured the as-found test value and it was greater than the Technical Specification allowable value. The Control Room Unit Supervisor consulted with the Electrical Maintenance Supervisor and directed the performers to adjust the relay component as allowed by the procedure, and continue with the test.
C. Status of structures, systems, and components (SSCs) that were inoperable at the start of the event and that contributed to the event Before continuing the surveillance, an inspection of the testing equipment was performed to ensure the equipment was functioning correctly. No issues were found and no changes were made to the testing equipment. The maintenance personnel retested the relay timing, without adjustment, and the result was 1.902 seconds. Due to the change in value, an additional test was performed with a result of 1.766 seconds, which was within the prescribed as-left procedure acceptance criteria of 1.715 to 1.785 seconds. Additional re-tests were performed with the same results, (i.e., a value of 1.766 seconds) obtained. Contrary to Control Room Unit Supervisor's directions, during relay retesting, no adjustments were made to the timing relay.
The Surveillance Test was completed and logged as satisfactory at 1202 on March 10, 2017, and the component was declared Operable.
Other than the undervoltage relay being tested, there were no other systems, structures, or components that were inoperable at the start of the event that contributed to the event.
comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
The failed relay was determined to be inoperable per Technical Specifications for approximately 99 hours0.00115 days <br />0.0275 hours <br />1.636905e-4 weeks <br />3.76695e-5 months <br /> prior to discovery. The failed component was discovered as a result of reviewing surveillance test results. Following discovery, the relay was replaced and the channel declared operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Based on the last successful surveillance test, the last time the equipment was determined to be capable of performing its safety function is September 22, 2016.
E. Method of discovery
On March 14, 2017, an STP engineer completed a review of the condition report documenting the surveillance test for the relay and determined that the relay reliability was questionable. This was based on the relay timing found outside Technical Specification limits and returned to Operable status with no adjustments. The Control Room was contacted and, based on the System Engineer's analysis, the Unit 1 Shift Manager determined that the relay should not have been declared Operable on March 10 and declared it inoperable on March 14, 2017 at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />. Technical Specification 3.3.2, Action 20A, was entered.
C. Safety Consequences and Implications of the Event During the event, the condition of the system was in a 2 out of 4 logic scheme. Protection for an under voltage condition remained intact for a 2 out of 3 logic, and thus maintained the safety function of the system. If an actual undervoltage condition occurred, the other relays would have performed as designed.
The Shift Manager determined that the relay should have remained Inoperable on March 10 until replaced. Technical Specification 3.3.2, Action 20A, requires the channel to be placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The failed undervoltage timing relay was subsequently replaced, satisfactory completion of surveillance test was performed, and the component was declared Operable.
The event was of very low risk significance and no radioactive release occurred; therefore, there was no adverse effect on the health and safety of the public.
comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
III. Cause of the Event
Based on the conditions identified and using information collected during discussions with the relay manufacturer subject matter expert, the cause of the component failure is not known. The relay was retained following the event, and inspected with satisfactory results. The failure could not be recreated, and the failure mode and mechanism is not known.
The causes for the event were the following:
The Electrical Maintenance Supervisor did not exhibit sufficient questioning attitude when consulted on this task. The relay did not exhibit the reliability to perform within limits through the next surveillance interval, and this was not recognized. Though the electricians did request clarification from the supervisor as expected, a proper questioning attitude from the supervisor would have determined that further expertise was needed to proceed. In addition, a misinterpretation of the procedure allowed the actions as performed, but the procedure intent was not maintained.
The start of this event consisted of the undervoltage relay as-found operating time being outside the Technical Specification required value. After retesting, the surveillance test timing improved as observed in subsequent retests. The failed condition could not be recreated upon further testing.
In addition, the Control Room staff displayed an inadequate questioning attitude regarding the adverse performance of the relay. When the information was shared with the Control Room that no adjustment was made to the timing relay, both individuals should have confirmed adequate information was collected to ensure that it was appropriate to proceed with closing out the surveillance rather than simply agreeing with the results of the completed test.
1. Unidentified Material Condition with the failed component (i.e. relay) 2. Less than adequate questioning attitude by Electrical Maintenance Personnel 3. Less than adequate questioning attitude by Operations Personnel - 00 2017 - 001
CONTINUATION SHEET
(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/) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
IV. Corrective Actions
The Table 1 below contains the corrective actions planned as a result of the event:
Table 1: Corrective Actions Corrective Actions Description Status 1 Relay was replaced and Surveillance Test completed Satisfactory. (Relay replaced by PM WAN 560042) Complete 2 Perform one on one sessions with EM personnel involved in this event to determine the reason for the shortfall on questioning the reliability of the subject relay device and any other corrective actions required to include coaching opportunities.
Complete 3 Perform coaching session with individuals involved to ensure clear understanding of 0POP01- ZO-0011 procedure requirements In process 4 Discuss event and refresh on procedure requirements of 0POP01-ZO-0011 with all Licensed Operations Personnel In process comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
V. Previous Similar Events
A review of similar events at STP was performed by reviewing the STP Corrective Action Program and Licensee Event Reports submitted for the previous 10 years. The review concluded that there have been many occurrences where the as-found condition of this or similarly functioning timing relays were found out of acceptance criteria or outside Technical Specification criteria. However all events involved the old model E7000 timers. It is important to note that the older model relays are diaphragm type designs, while the new relay timers are solid state designs. Since these timers were replaced (starting in 2012) this condition is the first case of its kind. In all occasions identified, the proper notifications and corrective actions were performed.
VI. Additional Information
The discovery date is March 14, 2017 when Unit 1 discovered the need to perform a reportability evaluation on the event. The event date is March 10, 2014, the date when the relay failed to pass the surveillance test. The report date is May 11, 2017, within 60 days after discovery of the event, as required per 10 CFR 50.73(a)(1).
Dates and approximate times of occurrences:
3/10/17: Electrician requested Control Room staff to log surveillance as Satisfactory. Discussion held on steps performed. All involved were aware that no adjustment was made.
3/10/17 1045: Surveillance Test commenced for the Unit 1 E1B undervoltage relay (Relay declared inoperable for planned testing).
3/10/17: Electrician's initial as-found measurement (3.295 Seconds) of the timing relay was found outside Technical Specification and Acceptance Criteria (1.715 to 1.785 seconds) per procedure.
3/10/17: Electrician notification and discussion with Unit 1 Control Room Supervisor. Direction given to continue in accordance with procedure and make adjustments to within band (acceptance criteria).
3/10/17: Electrician's discussion with Electrical Maintenance Supervisor. Direction given to continue with test and document findings in Condition Report.
3/10/17: Electrician's retest of timing relay was performed. (Retest 1: 1.902 seconds, retest 2-9:
1.766 seconds). No adjustment was made. No issues identified with test equipment.
A search for License Event Reports was performed that focused on events deemed similar reportable under 50.73(a)(2)(i)(B). Several events were found to meet this criteria, but none were directly applicable to this event.
- 00 2017 - 001
CONTINUATION SHEET
(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/) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.