07-24-2017 | On June 16, 2017, the station completed a past operability review and determined that an IsAnergency Feedwater Auto Start Actuation Signal was inoperable from November 12. 2016 until April 7. 2017. Technical Specification (TS) 3.3.2 Limiting Conditions for Operation (J,C.0) was entered due to having less than the minimum number of channels operable for Motor Driven Emergency Feedwater Pump (NIDE:MVP) actuation per TS Table 3.3-3 Functional IJnit 6.g.
'Ibis event was caused by the Low Pressure (LP) and High Pressure (HP) steam inlet valves not closing because the Secondary Operating Cylinder and associated Pilot Valve were corroded. Water intrusion into the 'C' Main Feedwater Punip (MFP) oil system had caused the corrosion of the carbon steel components within '1.1)P0022C such that the Secondary Operating Cylinder and Pilot Valve were not functional.
This condition is reportable under 10CFR50.73(a.)(2)(i)(B), an operation or condition which was prohibited by the plant's Technical Specifications. |
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LER-2017-001, C MAIN FFFDWATER PUMP FAILURE '1'0 TRIP RESUI,TS IN LOSS OF EMERGENCY FE,EDWATER AUTO START ACTUATION SIGNALVc Summer.- Unit 1 |
Event date: |
04-07-2017 |
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Report date: |
07-24-2017 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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3952017001R00 - NRC Website |
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Category:Letter
MONTHYEARML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20240112024-01-17017 January 2024 Notification of VC Summer Station Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000395/2024011 ML23361A1042023-12-21021 December 2023 Inservice Testing Program for Pumps and Valves Fifth Interval Update and Associated Relief and Alternative Requests IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letternrc Inspection Report 05000395/2023091 ML23354A1802023-12-20020 December 2023 301 Examination Report with Cover Letter ML23347A0492023-12-12012 December 2023 Technical Specification Bases Changes Updated Through November 2023 ML23334A2372023-11-30030 November 2023 (Vvsns), Unit 1 - Annual Commitment Change Summary Report ML23334A2462023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23332A1942023-11-28028 November 2023 (Vcsns), Unit 1, Correction of Typographical Error in License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23317A2242023-11-0909 November 2023 (Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23289A1152023-11-0303 November 2023 Ltr to R. Nelson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1162023-11-0303 November 2023 Ltr to W. Emerson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1172023-11-0303 November 2023 Tribal Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA IR 05000395/20230032023-11-0101 November 2023 Integrated Inspection Report 05000395/2023003 IR 05000395/20234032023-11-0101 November 2023 Material Control and Accounting Program Inspection Report 05000395/2023403 Cover ML23284A1792023-10-16016 October 2023 Subsequent License Renewal Application Online Reference Portal ML23275A0142023-10-11011 October 2023 SLRA - Acceptance and Opportunity for Hearing - Letter ML23284A1662023-10-10010 October 2023 (Vcsns), Unit 1 - Request for Regulatory Conference; (EA-23-093) IR 05000395/20230902023-10-0404 October 2023 NRC Inspection Report 05000395/2023090 and Preliminary Yellow Finding and Apparent Violation IR 05000395/20230112023-09-27027 September 2023 Focused Engineering Inspection Report 05000395/2023011 ML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23235A0432023-09-0505 September 2023 Receipt and Availability of the Subsequent License Renewal Application IR 05000395/20234012023-08-30030 August 2023 Security Baseline Inspection Report 05000395/2023401 ML23242A1192023-08-29029 August 2023 (Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 27 ML23243B0362023-08-25025 August 2023 Request for FEMA Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23233A1752023-08-17017 August 2023 Application for Subsequent Renewed Operating License IR 05000395/20230022023-08-14014 August 2023 Integrated Inspection Report - Integrated Inspection Report 05000395/2023002 and Apparent Violation IR 05000395/20230102023-08-12012 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000395/2023010 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000395/20234412023-07-17017 July 2023 95001 Supplemental Inspection Report 05000395/2023441 and Follow Up Assessment Letter ML23190A0012023-07-0909 July 2023 Special Report 2023-003 Inoperable Radiation Monitoring Instrumentation Channel ML23187A5092023-07-0606 July 2023 Request for Federal Emergency Management Agency Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23173A1052023-06-22022 June 2023 Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23159A2332023-06-0808 June 2023 License Amendment Request - Emergency Response Organization Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML23156A3092023-06-0505 June 2023 Requalification Program Inspection Virgil C. Summer Nuclear Station Unit 1 - 05000395/2023003 2024-02-07
[Table view] Category:Licensee Event Report (LER)
MONTHYEARRC-18-0049, LER 2018-001-01 Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator2018-05-0707 May 2018 LER 2018-001-01 Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator RC-18-0056, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors2018-04-25025 April 2018 (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors 05000395/LER-2017-0052017-12-22022 December 2017 AUTOMATIC REACTOR TRIP DUE TO MAIN TURBINE TRIP, LER 17-005-00 for V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip 05000395/LER-2017-0062017-12-15015 December 2017 TECHNICAL SPECIFICATION ACTION NOT MET FOR INOPERABLE OXYGEN MONITOR, LER 17-006-00 for Virgil C. Summer, Unit 1, Regarding Technical Specification Action not Met for Inoperable Oxygen Monitor 05000395/LER-2017-0032017-10-26026 October 2017 FAILED LIGHTNING ARRESTER ON MAIN TRANSFORMER CAUSES REACTOR TRIP, LER 17-003-00 For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester On Main Transformer Causes Reactor Trip 05000395/LER-2017-0022017-08-25025 August 2017 Low Feedwater Flow to the 'B' Steam Generator Causes Automatic Reactor Trip, LER 17-002-00 for V.C. Summer, Unit 1, Regarding Low Feedwater Flow to the 'B' Steam Generator Causes Automatic Reactor Trip 05000395/LER-2017-0012017-07-24024 July 2017 C MAIN FFFDWATER PUMP FAILURE '1'0 TRIP RESUI,TS IN LOSS OF EMERGENCY FE,EDWATER AUTO START ACTUATION SIGNAL, LER 17-001-00 for V.C. Summer, Unit 1, Regarding C Main Feedwater Failure to Trip Results in Loss of Emergency Feedwater Auto Start Actuation Signal RC-15-0190, Special Report (Spr) 2014-005-01, Loss or Theft of License Material2015-12-16016 December 2015 Special Report (Spr) 2014-005-01, Loss or Theft of License Material RC-15-0179, Special Report (Spr) 2015-002 Regarding One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days2015-11-0303 November 2015 Special Report (Spr) 2015-002 Regarding One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days RC-15-0139, Submittal of Special Report (Spr) 2015-001 Regarding the Loose-Part Monitoring System (Lpms) Channel Number 8 Being Inoperable in Excess of 30 Days2015-08-20020 August 2015 Submittal of Special Report (Spr) 2015-001 Regarding the Loose-Part Monitoring System (Lpms) Channel Number 8 Being Inoperable in Excess of 30 Days RC-14-0084, Special Report 2014-003 for V.C. Summer, One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days2014-05-14014 May 2014 Special Report 2014-003 for V.C. Summer, One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days RC-14-0085, Special Report 2014-002 for V.C. Summer, Degraded Conditions Lasting Longer than Seven Days2014-05-14014 May 2014 Special Report 2014-002 for V.C. Summer, Degraded Conditions Lasting Longer than Seven Days ML12334A4432012-11-27027 November 2012 SR 12-002-00 for Virgil C. Summer, Unit 1 Regarding Meteorological Monitoring Channels Being Inoperable for More than Seven Days ML12188A5422012-07-0303 July 2012 Special Report 2012-001 ML12079A2862012-03-16016 March 2012 LER 12-01-00 for Virgil C. Summer, Unit 1 Regarding Core Exit Thermocouples Inoperable Due to an Inadequate Maintenance Procedure ML11186A9742011-06-30030 June 2011 Regarding Depressurization of the 'C' Steam Line Creating a Differential Pressure Greater than 97 PSIG Between the Steam Lines, Initiating a Safety Injection ML11117A3042011-04-25025 April 2011 V. C. Summer, Unit 1, Submittal of Special Report (Spr) 2011-001 Re Control Building Fire/Pressure Door (DRCB/102) Being Inoperable for Greater than Seven Days Prior to Completing Repair of the Door ML0614201452006-05-17017 May 2006 LER 99-014-03 for Virgil C. Summer Nuclear Station, Re Kaowool Fire Barriers Outside 10 CFR 50 Appendix R Design Basis RC-06-0051, Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours2006-03-13013 March 2006 Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours ML0527803362005-09-28028 September 2005 LER 05-S01-01 for Virgil C. Summer Nuclear Station Regarding Entry of Unauthorized Employee Into the Protected Area RC-05-0095, LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area2005-06-22022 June 2005 LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area ML0335001292003-12-11011 December 2003 LER 03-S03-00 for Virgil C. Summer Regarding Access to Protected Area by an Individual Without Proper Authorization ML0326605072003-09-16016 September 2003 LER 03-S02-00 for Virgil C. Summer Regarding Access to Protected Area by an Individual with Expired Training ML0318404692003-07-0101 July 2003 LER 99-014-02, Virgil C. Summer Re Kaowool Fire Barriers Outside 10CFR50 Appendix R Design Basis ML0308605122003-03-20020 March 2003 LER 03-S01-00 from Summer Regarding Access to Protected Area by an Individual with an Expired Badge 2018-05-07
[Table view] |
comments regarding burden estimate to the Informa':on Services Branch (T-2 F43), U.S. Nucicur Regulatory Commission, Washington. DC 70555 0001, or by e-mat to Infocollects.Resource©,nrc.gov, and to the Desk Officer, Office of Infornati
- on and Regulatory Affa:rs, NEOB-10202, (3150-0104), Offior.: of Manage:nen'. airs Budget. Washington, BC 20503. Ifs means used to impose en information collection does not disp'ay a current!y vad OMB control number: the NRC may not conduct or sponsor, and a person is not required to respond to. the information colection.
05000- VC SUMMER - UNIT 1 395 I 1.0 EVENT DESCRIPTION On June 16, 2017, the station completed a past operability review and determined that an Emergency Feedwater Auto Start Actuation Signal was inoperable from November 12, 2016 until April 7, 2017. Technical Specification (TS) 3.3.2 Limiting Conditions for Operation (LCO) was entered due to there being less than the minimum number of channels operable for Motor Driven Emergency Feedwater Pump (MDEFWP) actuation per TS Table 3.3-3 Functional Unit 6.g.
'C' MFP (TPP0022C) failed to trip when given a trip signal from the Main Control Board (MCB), Digital Control System (DCS), and the local trip pull handle. Indications did not change when an attempt to trip was made from the MCB. The attempt to trip from DCS resulted in the DCS indicating "tripped" with no change in the 'C' MFP. Indications did not change when attempting to trip 'C' MFP locally. 'C' MFP was tripped by using an alternative method of starting the Emergency Lube Oil Pump and removing power from the Main and Auxiliary Lube Oil Pumps. There was no impact to the station as a result of this condition.
There were no issues with the feedwater isolation signal nor were there any issues with securing 'A' and 'B' MFPs during the RF23 downpower.
2.0 EVENT ANALYSIS As described in Virgil C. Summer Nuclear Station's Final Safety Analysis Report (FSAR) Section 10.4.7.2, the Feedwater System is designed to pump feedwater from the deaerator storage tank through two stages of high pressure heaters to the steam generators during normal operation, startup, and before shutdown. To perform this function, three 50% capacity, non-safety, variable speed, turbine driven feedwater pumps are included in the system. In the event of a loss of one feedwater pump, a power reduction may be necessary to prevent reactor trip, but the MFP turbines can be operated at runout capacity temporarily. There are no further specific criteria described for the MFP turbines in Section 10.4.7.2 of the FSAR.
FSAR Section 7.3.2.3 lists the automatic initiations of a MDEFWP. One of the five methods that provides an automatic MDEFWP initiation is a trip of all three MFPs.
TS 3/4.3.2 states that the Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
Action Statement 3.3.2.c states that with an ESFAS instrument channel or interlock inoperable take the ACTION shown in Table 3.3-3.
Table 3.3-3 Functional Unit 6.g states that Emergency Feedwater ESFAS instrumentation requires the Trip of MFPs to start Motor-Driven Pumps. In Modes 1 and 2 there must be three total channels (one per pump) of this trip present or Action 19 must be taken.
EsIlmated burden per response to comply vt,11h this mandatory collection request 00 boors. Reported lessons learned are incorporated into tbe licensing process and led back to industry. Send comments regarding burden estimate to tile Information Services Branch (T-2 F43), U.S. Nuclee Regu'atory COMMiSS.01, Washington. DC 20555-0001. or by e-mail to Infocollects.Resource(CMT.gov. and to the Desk Ofrcer. Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104). Office of Management and Budget. Washington, DC 20503. If a means used In impose an information collection does no: disp:ay a curren:.y valid OMB control number, the NRC way rot concoct or sponsor, and a person is not required to respond to, the information coloction.
05000- VC SUMMER - UNIT 1 395 Action 19 states that with the number of OPERABLE channels one less than the Total Number of Channels. STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a. The inoperable channel is placed in the tripped condition within one hour.
b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to two hours for surveillance testing of other channels per Specification 4.3.2.1.
When the electronic and manual trips were attempted on April 7, 2017, no indication was received that the MFP turbine had tripped (i.e. stop valve closure, speed reduction, local indicator lights). Because the trip system would not actuate, one of three channels for MFP trip under TS 3/4.3.2 was inoperable.
LCO for TS 3.3.2 was entered at 21:15 on April 7, 2017, requiring the operable channel be placed in the trip condition within an hour. At 22:09, 'C' MFP was secured and LCO for TS 3.3.2 was exited. Therefore, Action 19 under TS 3.3.2 was satisfied as 'C' MFP was able to be placed in the tripped condition by securing the Lube Oil Pumps that supplied high pressure oil to the stop valves ultimately satisfying Emergency Feedwater ESFAS instrumentation requirements.
An evaluation found that water intrusion into the 'C' MFP oil system resulted in the corrosion of its carbon steel components such that the Secondary Operating Cylinder and Pilot Valve were bound. This bound condition would not allow the steam inlet valves to close resulting in the inoperable ESFAS.
The past adverse condition leading to the Emergency Feedwater ESFAS instrumentation channel being inoperable was the inability of the 'C' MFP to trip as a result of the Secondary Operating Cylinder and associated Pilot Valve being corroded. Review of MFP oil samples, which are taken on a monthly basis, indicated that possible water contamination began November 12, 2016. Since there is no evidence suggesting that the trip signals would have changed state from November 12, 2016 to April 7, 2017, 'C' MFP input to the Emergency Feedwater Auto Start Signal was determined to be inoperable for that period of time.
3.0 SAFETY SIGNIFICANCE This event has no impact on the Probabilistic Risk Analysis (PRA) model. The PRA model includes start signals for Emergency Feedwater from: Low Steam Generator Level, Manual, Load Sequencer, and Anticipated Transient Without SCRAM Mitigation System Actuation Circuitry (AMSAC). Loss of Feedwater is not modeled as a separate actuation.
4.0 PREVIOUS OCCURRENCE No previous occurrence within the last three years.
commrmts regarding burden estimate to the Information Services B'anch (T-2 F43). U.S. Nuclear Regulatory Commission, Washing-on, DC 20555-00Y.. or by e-mail to In'.3colle:As.ResourcegnT.gov, and to the Desk Officer, Office o' Inkymation and Reg:Ilalnry Affairs, NE013.10202, (3150 0104): OTce of Management and Butget, Wash'Von, DC 20503. If a means used to impose an information collection does rot display a currently yard OMB control mumbo-. the NRC May rot conduct or sponsor, and a person is rot required to respond to, the information collection.
05000- VC SUMMER - UNIT 1 395 5.0 CORRECTIVE ACTIONS 'C' MFP was tripped by starting the Emergency Lube Oil Pump and removing power from the Main and Auxiliary Lube Oil Pumps.
'C' MFP was repaired under Work Orders (WOs) 1704018, 1616104, and 1603349.
The WOs inspected the SV-12 Stern and Cylinder for damage and replaced parts as appropriate. It also inspected and cleaned the front standard trip assembly and other components as required. Leak detection for tube and tubesheet joint leaks on 'C' Main Feed Pump Lube Oil Cooler was also performed. Tube to tubesheet joints that were found to have leaks were rolled and the seals were tested to confirm that no further leakage was present.