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Category:Letter
MONTHYEARML25014A3082025-01-21021 January 2025 Transmittal Letter for VC Summer SE for SLRA Review ML25020A0342025-01-20020 January 2025 Special Report 2025-002 for Virgil C. Summer Nuclear Station, Unit 1, Inoperable Radiation Monitoring Instrumentation Channel ML25007A2342025-01-17017 January 2025 Limited Scope Aging Management Audit Report Regarding the Subsequent License Renewal Application Review ML25021A0612025-01-16016 January 2025 Special Report 2025-001 for Virgil Summer Nuclear Station, Unit 1, Inoperable Loose-Part Monitoring System Channel ML24344A1902024-12-23023 December 2024 Summary of Safety Inspection of the Service Water Reservoir Dam (CAC Nos. 001370/05000395; EPID L-2017-LNS-0015) (Nonproprietary Cover Letter) ML24340A1572024-12-0404 December 2024 Annual Commitment Change Summary Report ML24221A0602024-11-25025 November 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 05000395/LER-2024-003, Common Cause Inoperability of Engineered Safety Features2024-11-18018 November 2024 Common Cause Inoperability of Engineered Safety Features ML24278A2832024-11-0707 November 2024 Letter to E. Carr Environmental Impact Statement Scoping Summary Report for Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20240032024-11-0606 November 2024 – Integrated Inspection Report 05000395/2024003 ML24305A1302024-10-31031 October 2024 Submittal of 30 Day Report Per 10 CFR 26.719(c) Blind Performance Testing ML24308A0052024-10-28028 October 2024 10-28-24 NRC V.C. Summer Nuclear Station SLR Cherokee Nation Letter to USNRC ML24308A0062024-10-25025 October 2024 Subsequent License Renewal Application Area of Potential Effect (Ape) Clarification Fairfield County, South Carolina SHPO Project No. 22-EJ0147 ML24302A1442024-10-24024 October 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 4 and Requested Information Formation in Response to Limited Aging Management Audit ML24250A0782024-10-22022 October 2024 Relief Request RR-5-V1 Regarding Service Water Return Header Check Valves ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves ML24256A2322024-10-22022 October 2024 Relief Request RR-5-P1 Charging/Safety Injection Pumps 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System ML24290A1052024-10-0707 October 2024 Core Operating Limits Report VCSNS Unit 1 Cycle 29, Revision 0 IR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public ML24274A1942024-09-26026 September 2024 (Vcsns), Unit 1 Subsequent License Renewal Application (SLRA) First 10 CFR 54.21(b) Annual Amendment ML24221A2112024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0542024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0552024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0592024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0642024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) IR 05000395/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000395/2024402 IR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24190A4012024-08-19019 August 2024 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Dominion Energy Letter Dated May 30, 2024 IR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000395/20240112024-06-26026 June 2024 – Comprehensive Engineering Team Inspection Report 05000395/2024011 ML24185A1902024-06-25025 June 2024 Submittal of Updated Final Safety Analysis Report, Revision 24 ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24170A7832024-06-0606 June 2024 ISFSI, Virgil C. Summer, Unit 1, and ISFSI, North Anna, Units 1 & 2, and ISFSI, Surry, Units 1 & 2, and ISFSI - Submittal of Revision 36 of the Quality Assurance Topical Report ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter 2025-01-21
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000395/LER-2024-003, Common Cause Inoperability of Engineered Safety Features2024-11-18018 November 2024 Common Cause Inoperability of Engineered Safety Features 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System 05000395/LER-2024-001, (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator2024-04-17017 April 2024 (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator 05000395/LER-2023-001, Manual Reactor Trip Due to Loss of Main Feedwater Pump2023-05-30030 May 2023 Manual Reactor Trip Due to Loss of Main Feedwater Pump 05000395/LER-2022-001-01, (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault2022-12-15015 December 2022 (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault 05000395/LER-2022-002-01, Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator2022-12-0808 December 2022 Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator 05000395/LER-2022-002, (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.12022-04-11011 April 2022 (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.1 05000395/LER-2021-001-01, Condition Prohibited by Technical Specifications2022-02-0808 February 2022 Condition Prohibited by Technical Specifications 05000395/LER-2021-001, (Vcsns), Unit 1, Condition Prohibited by Technical Specifications2021-08-26026 August 2021 (Vcsns), Unit 1, Condition Prohibited by Technical Specifications 05000395/LER-2019-003-01, (Vcsns), Completion of a Technical Specification Required for Plant Shutdown2020-04-0202 April 2020 (Vcsns), Completion of a Technical Specification Required for Plant Shutdown 05000395/LER-2019-004, 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.12020-01-17017 January 2020 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.1 05000395/LER-2019-003, Completion of a Technical Specification Required Plant Shutdown2020-01-0303 January 2020 Completion of a Technical Specification Required Plant Shutdown 05000395/LER-2019-002, Regarding Condition Prohibited by Technical Specification 3.6.42019-10-0909 October 2019 Regarding Condition Prohibited by Technical Specification 3.6.4 05000395/LER-2019-001-01, Regarding Condition Prohibited by Technical Specification 3.4.6.12019-08-19019 August 2019 Regarding Condition Prohibited by Technical Specification 3.4.6.1 05000395/LER-2019-001, Condition Prohibited by Technical Specification 3.4.6.12019-04-15015 April 2019 Condition Prohibited by Technical Specification 3.4.6.1 RC-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 05000395/LER-2018-001-01, Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator2018-05-0707 May 2018 Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator 05000395/LER-2016-001-02, (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-2018-001, Valid Actuation of Emergency Diesel Generator2018-03-19019 March 2018 Valid Actuation of Emergency Diesel Generator 05000395/LER-1917-005, V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip2017-12-22022 December 2017 V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip 05000395/LER-1917-006, Regarding Technical Specification Action Not Met for Inoperable Oxygen Monitor2017-12-15015 December 2017 Regarding Technical Specification Action Not Met for Inoperable Oxygen Monitor 05000395/LER-1917-003, For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester on Main Transformer Causes Reactor Trip2017-10-26026 October 2017 For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester on Main Transformer Causes Reactor Trip 05000395/LER-1917-002, Regarding Low Feedwater Flow to the B Steam Generator Causes Automatic Reactor Trip2017-08-25025 August 2017 Regarding Low Feedwater Flow to the B Steam Generator Causes Automatic Reactor Trip 05000395/LER-1917-001, Regarding C Main Feedwater Failure to Trip Results in Loss of Emergency Feedwater Auto Start Actuation Signal2017-07-24024 July 2017 Regarding C Main Feedwater Failure to Trip Results in Loss of Emergency Feedwater Auto Start Actuation Signal 05000395/LER-2016-003-01, Regarding Steam Propagation Door Discovered Propped Open2017-02-0909 February 2017 Regarding Steam Propagation Door Discovered Propped Open 05000395/LER-2016-004-01, Regarding Steam Propagation Barrier Degrade Due to Missing Orifices2017-02-0101 February 2017 Regarding Steam Propagation Barrier Degrade Due to Missing Orifices 05000395/LER-2016-006, Regarding Circuit 1 Hot Gas Bypass Valve Failure Renders A-Train Chiller Non-functional and A-Train Charging Pump Inoperable2016-12-15015 December 2016 Regarding Circuit 1 Hot Gas Bypass Valve Failure Renders A-Train Chiller Non-functional and A-Train Charging Pump Inoperable 05000395/LER-2016-005, Regarding Steam Propagation Barrier Degraded Due to Removal of Ventilation Duct Access Panel for Surveillance Activities2016-12-0505 December 2016 Regarding Steam Propagation Barrier Degraded Due to Removal of Ventilation Duct Access Panel for Surveillance Activities 05000395/LER-2016-004, Steam Propagation Barrier Degraded Due to Missing Orifices2016-11-14014 November 2016 Steam Propagation Barrier Degraded Due to Missing Orifices 05000395/LER-2016-003, Regarding Steam Propagation Door Discovered Propped Open2016-11-14014 November 2016 Regarding Steam Propagation Door Discovered Propped Open 05000395/LER-2016-001-01, Transmittal of Low Refrigerant Renders A-Chiller Non-Functional and A-Charging Pump Inoperable2016-10-25025 October 2016 Transmittal of Low Refrigerant Renders A-Chiller Non-Functional and A-Charging Pump Inoperable 05000395/LER-2016-002, Regarding Pressurizer Heater Inoperable Longer than Technical Specification Limiting Condition for Operation 3.4.32016-09-0808 September 2016 Regarding Pressurizer Heater Inoperable Longer than Technical Specification Limiting Condition for Operation 3.4.3 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 05000395/LER-2015-002, Regarding Low Oil Level Trip Renders Chillers Non-Functional and a Train of Charging System Inoperable2015-06-0808 June 2015 Regarding Low Oil Level Trip Renders Chillers Non-Functional and a Train of Charging System Inoperable 05000395/LER-2015-001, Regarding Reactor Building Spray Isolation Valve Failure Renders Train of Reactor Building Spray Inoperable2015-05-12012 May 2015 Regarding Reactor Building Spray Isolation Valve Failure Renders Train of Reactor Building Spray Inoperable 05000395/LER-2014-004, For V. C. Summer, Unit 1 - Condensate System Bypass Valve Failure and a Procedure Deficiency Cause Loss of Feedwater and Automatic Reactor Trip2014-09-19019 September 2014 For V. C. Summer, Unit 1 - Condensate System Bypass Valve Failure and a Procedure Deficiency Cause Loss of Feedwater and Automatic Reactor Trip 05000395/LER-2014-003, Regarding Component Cooling System Emergency Makeup a Valve Failed to Stroke Open Rendering Train of Component Cooling Inoperable2014-06-24024 June 2014 Regarding Component Cooling System Emergency Makeup a Valve Failed to Stroke Open Rendering Train of Component Cooling Inoperable 05000395/LER-2014-002, Regarding Reactor Vessel Head Penetration Weld Indications Attributed to Primary Water Stress Corrosion Cracking2014-06-16016 June 2014 Regarding Reactor Vessel Head Penetration Weld Indications Attributed to Primary Water Stress Corrosion Cracking 05000395/LER-2014-001, V. C. Summer Nuclear Station Unit 1, Regarding Component Cooling System Emergency Makeup B Valve Failed to Stroke Open Rendering Train of Component Cooling Inoperable2014-06-12012 June 2014 V. C. Summer Nuclear Station Unit 1, Regarding Component Cooling System Emergency Makeup B Valve Failed to Stroke Open Rendering Train of Component Cooling Inoperable 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 05000395/LER-2013-006, Regarding Securing Control Room Ventilation Emergency Recirculation While Associated Radiation Monitor Was Out of Service2014-01-31031 January 2014 Regarding Securing Control Room Ventilation Emergency Recirculation While Associated Radiation Monitor Was Out of Service 05000395/LER-2013-005, Regarding Unfused Direct Current Ammeter Circuits in Control Room Result in 10 CFR 50 Appendix R Unanalyzed Condition2013-12-11011 December 2013 Regarding Unfused Direct Current Ammeter Circuits in Control Room Result in 10 CFR 50 Appendix R Unanalyzed Condition 05000395/LER-2013-004, Regarding Spray System Relief Valve Failure to Lift at Required Setpoint Renders the Reactor Building Spray System Inoperable2013-09-30030 September 2013 Regarding Spray System Relief Valve Failure to Lift at Required Setpoint Renders the Reactor Building Spray System Inoperable 05000395/LER-2013-003, Trip Setpoint Renders Chiller and Control Room Emergency Filtration Inoperable2013-08-21021 August 2013 Trip Setpoint Renders Chiller and Control Room Emergency Filtration Inoperable 05000395/LER-2013-002, V. C. Summer Nuclear Station, Unit 1, Regarding Component Cooling System Emergency Makeup Valve Failed to Stroke Open2013-06-19019 June 2013 V. C. Summer Nuclear Station, Unit 1, Regarding Component Cooling System Emergency Makeup Valve Failed to Stroke Open 05000395/LER-2013-001, V. C. Summer Nuclear Station, Unit 1, Regarding Grid Disturbance Results in an Engineered Safeguard Features Actuation of the a EDG2013-05-22022 May 2013 V. C. Summer Nuclear Station, Unit 1, Regarding Grid Disturbance Results in an Engineered Safeguard Features Actuation of the a EDG 05000395/LER-2012-003, Regarding Reactor Vessel Head Penetrations Not Meeting Requirements of 10 CFR50.55(g)(6)(ii)(D)2012-12-0606 December 2012 Regarding Reactor Vessel Head Penetrations Not Meeting Requirements of 10 CFR50.55(g)(6)(ii)(D) 2024-04-17
[Table view] |
LER-2016-004, Regarding Steam Propagation Barrier Degrade Due to Missing Orifices |
Event date: |
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Report date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i) |
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3952016004R01 - NRC Website |
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text
George A. Lippard Vice President, Nuclear Operations 803.345.4810 February 1, 2017 A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS), UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSEE EVENT REPORT (LER 2016-004-01)
STEAM PROPAGATION BARRIER DEGRADED DUE TO MISSING ORIFICES Attached is Licensee Event Report (LER) 2016-004-01, for the Virgil C. Summer Nuclear Station. This revised report supplements LER 2016-004-00. This report describes an event that was identified based on an extent of condition review for LER 2016-003-00 Steam Propagation Door (DRIB/107) Discovered Propped Open. The station identified orifices that were not installed in the correct drain lines as specified in a design change package. The station has completed an evaluation of the impacted areas if a High Energy Line Break (HELB) event occurred. This report is submitted in accordance with 10CFR50.73(a)(2)(v)(D) and 10CFR50.73(a)(2)(i)(B).
Should you have any questions, please call Mr. Bruce Thompson at (803) 931-5042.
Very truly yours BAB/GAL/ts Attachment c:
K. B. Marsh S. A. Williams S. A. Byrne NRC Resident J. B. Archie Inspector N. S. Cams L. W. Harris J. H. Hamilton Paulette Ledbetter S. M. Shealy J. C. Mellette W. M. Cherry ICES Coordinator C. Haney K. M. Sutton Marsh USA, Inc.
Maintenance Rule Engineer NSRC RTS (CR-16-04716 & CR-16-04801)
File (818.07)
PRSF (RC-17-0021)
INPO Records Center V. C. Summer Nuclear Station
NRC FORM 366 (06-2016)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nureas/staff/sr1022/r3/)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME VC SUMMER-UNIT 1
- 2. DOCKET NUMBER 05000 395
- 3. PAGE 1 OF
- 4. TITLE STEAM PROPAGATION BARRIER DEGRADE DUE TO MISSING ORIFICES
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR Y
SEQUENTIAL REV NUMBER NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 09 14 2016 2016 -
004 01 02 01 2017 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 l l 20.2201(b) 20.2203(a)(3)(i) 50.73(a) (2) (ii)(A) 50.73(a) (2)(viii)(A) 1
]
20.2201(d) 7] 20.2203(a)(3)(ii) 50.73(a) (2)(ii)(B) 50.73(a) (2)(viii)(B) 1 Q 20.2203(a)(1) l l 20.2203(a)(4) 50.73(a) (2)(iii) 50.73(a)(2)(ix)(A) 1 3] 20.2203(a)(2)(i) 50.36(c)(1 )(i)(A) 50.73(a) (2)(iv)(A) 50.73(a)(2)(x)
- 10. POWER LEVEL 100
]
20.2203(a)(2)(ii) 50.36(c)(1 )(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(4)
- 10. POWER LEVEL 100
]
20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5)
- 10. POWER LEVEL 100
] 20.2203(a)(2)(iv) 50.46(a)(3)(H) 50.73(a)(2)(v)(C) 73.77(a)(1)
- 10. POWER LEVEL 100 2 20.2203(a)(2)(v) 50.73(a)(2)(i)(A)
\\7\\ 50.73(a)(2)(v)(D) 73.77(a) (2) (i)
- 10. POWER LEVEL 100
] 20.2203(a)(2)(vi)
[7] 50.73(a)(2) (i) (B) 50.73(a) (2) (vii) 73.77(a) (2) (ii)
- 10. POWER LEVEL 100 50.73(a)(2)(i)(C)
~l OTHER Specify in Abstract below or in =
Root Cause (RC02): The work order steps for installing the orifice plates were classified as non-nuclear safety related work. When QC reviewed the work order, they determined that no QC was necessary based on the work order safety classification. However, the ECR classified this work as Quality Related. This resulted in the orifice installation being performed without QC verification. No guidance existed at the time the work orders were planned that would have instructed QC inspectors to review ECR packages for safety classification during the QC work order routing reviews.
Potential Root Cause (RC03): The potential exists that the information (ECR section) included in the work package was not sufficient to provide adequate work instruction. If the ECR instructions were not included in the work package, the information available to the workers for the orifice plate installation locations was inadequate. The detailed drawing, included in the work package, was incorrect for the "A" Chiller orifice plate location. Due to this occurring over seven years previous, the workers could not recall what led up to or contributed to the orifice plates being located in the wrong location. Neither the planner nor the workers could recall whether or not the ECR section was included in the work package.
Potential Root Cause (RC04): The potential exists that the workers failed to follow work (ECR) instructions if it had been included in the work package. The ECR written instructions provided sufficient detail for the orifice plates to be installed in the correct locations. If the ECR was included in the work package, the workers would have had adequate work instructions, but failed to follow it. The Work Order instructions available to the workers did not include the room numbers.
Due to this occurring over seven years previous, the workers could not recall what led up to or contributed to the orifice plates being located in the wrong location. Neither the planner nor the workers could recall whether or not the ECR section was included in the work package.
Contributing Cause (CC1): The interface review comments were provided but were not resolved in a manner to aid in determining proper installation locations per the drawings. There were two comments made during the ECR interface review that would have clarified the orifice plate installation locations. A promissory resolution was given to an incorrect drawing and the second comment on the clarity of the orifice plate locations was dismissed with no resolution. There was no formal tracking in place for the resolution of interface review comments. As a result, the information provided in the ECR lacked clarity.
Contributing Cause (CC2): No guidance existed at the time the work orders were planned that would have directed the planner to base safety classification on ECR information. This resulted in the planner basing the non-nuclear safety classification on the CMMS system listing for floor drains instead of the quality related classification of the ECR.
The root cause analysis determined that the causes associate with this event did not reflect current performance.
Corrective actions to address the causes in RCA-16-04801 are addressed in CR-16-04801.
The VU System provides cooling to safety related areas (TS Table 3.7-7) as an attendant cooling system and supports the comfort requirements for the Control Room Emergency Filtration Systems (CREFS). The VU System is needed to ensure that equipment located within these areas can withstand the environmental effects of a postulated FSAR Chapter 15 event. With a nonfunctional chiller unit, its associated VU train will become nonfunctional, thereby affecting room temperatures and the reliability of the train's associated equipment. The most limiting area for temperature limits has been identified as the charging pump rooms. Per TS 3/4.5.2, one charging pump has to be operable per train of Emergency Core Cooling System (ECCS) during Mode 1-3.
Corrective Actions to address the causes in RCA-16-04801 are addressed in CR-16-04801.
5.0 CORRECTIVE ACTIONS
Immediate action taken: On September 14, 2016, stopped all associated VU chiller work and ensured all steam propagation doors were closed. Station Order 16-05 was issued that directs that no work can be performed in the chiller rooms that would require the door(s) to be propped open. The Station Order was in place until the orifice installations in the sumps was corrected.
Interim action taken: On September 21, 2016, Nonconformance (NC)-16-04716-005 Repair Disposition #1 was issued to correctly install the orifice plates. This work was completed on October 6, 2016. Page 6
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05000395/LER-2016-001-02, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors | (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-001-01, Transmittal of Low Refrigerant Renders A-Chiller Non-Functional and A-Charging Pump Inoperable | Transmittal of Low Refrigerant Renders A-Chiller Non-Functional and A-Charging Pump Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-002, Regarding Pressurizer Heater Inoperable Longer than Technical Specification Limiting Condition for Operation 3.4.3 | Regarding Pressurizer Heater Inoperable Longer than Technical Specification Limiting Condition for Operation 3.4.3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-003-01, Regarding Steam Propagation Door Discovered Propped Open | Regarding Steam Propagation Door Discovered Propped Open | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-003, Regarding Steam Propagation Door Discovered Propped Open | Regarding Steam Propagation Door Discovered Propped Open | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-004-01, Regarding Steam Propagation Barrier Degrade Due to Missing Orifices | Regarding Steam Propagation Barrier Degrade Due to Missing Orifices | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-004, Steam Propagation Barrier Degraded Due to Missing Orifices | Steam Propagation Barrier Degraded Due to Missing Orifices | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-005, Regarding Steam Propagation Barrier Degraded Due to Removal of Ventilation Duct Access Panel for Surveillance Activities | Regarding Steam Propagation Barrier Degraded Due to Removal of Ventilation Duct Access Panel for Surveillance Activities | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000395/LER-2016-006, Regarding Circuit 1 Hot Gas Bypass Valve Failure Renders A-Train Chiller Non-functional and A-Train Charging Pump Inoperable | Regarding Circuit 1 Hot Gas Bypass Valve Failure Renders A-Train Chiller Non-functional and A-Train Charging Pump Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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