|
---|
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-2019-001, Regarding Condition Prohibited by Technical Specification 3.4.6.1 |
Event date: |
|
---|
Report date: |
|
---|
3952019001R01 - NRC Website |
|
text
V. C. Summer Nuclear Station Bradham Blvd & Hwy 215, Jenkinsville, SC 29065 Mailing Address:
P.O. Box 88, Jenkinsville, SC 29065 Dominion Energy.com Document Control Desk August19, 2019 U.S. Nuclear Regulatory Commission Washington, DC 20555 SOUTH CAROLINA ELECTRIC & GAS COMPANY
~
Dominion
- iiiiii" Energy Serial No. 19-171A VCS-LIC/JRB RO Docket No. 50-395 License No. NPF-12 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 LICENSEE EVENT REPORT 2019-001-01 CONDITION PROHIBITED BY TECHNICAL SPECIFICATION 3.4.6.1 Enclosed is Licensee Event Report (LER) 2019-001-01, for the Virgil C. Summer Nuclear Station. This report provides details concerning a past condition prohibited by Technical Specification (TS) 3.4.6.1. This revision to LER 2019-001-00 addresses NRC Finding 2019001-02 (CR-19-02144). This report is submitted pursuant to 10 CFR 50. 73(a)(2)(i)(B).
In a letter dated July 30, 2019 (ML19214A046), South Carolina Electric & Gas Company (SCE&G) requested a License Amendment to amend the V. C. Summer operating license to reflect the name change from SCE&G to Dominion Energy South Carolina (DESC). The amendment request is currently under review by the NRC.
Should you have any questions, please call Mr. Michael Moore at (803) 345-4752.
Sincerely, Georg A Lippard Site Vice President V.C. Summer Nuclear Station Enclosure Commitments contained in this letter: None cc:
G. J. Lindamood - Santee Cooper L. Dudes - NRC Region II S. A. Williams - NRC Project Mgr.
NRC Resident Inspector J. N. Bassett-lNPO Marsh USA, Inc.
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
Estimated burden per response ID comply with this mandato,y collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
c.J"""""~,.
LICENSEE EVENT REPORT (LER)
Reported lessoos learned are incorporated into the licensing process and fed back ID industry. Send comments regarding burden estimate to the Information Services Branch
-~~
(T-2 F43), U.S. Nudear Regulatory Commission, Washington, DC 20555-0001, or by e-mail I!
n
{See Page 2 for required number of digits/characters for each block) lo lnfocollects.Resource@nrc.gov, and lo the Desk Officer, Office of lnfonnation and 0
~
C Regulalo,y Affairs, NEOB-10202, (3150-0104), Office or Management and Budget, (See NUREG-1022, R.3 for instruction and guidance for completing this form c:.
.I Washington, DC 20503. If a means used to impose an information collection does not
,-;+..,
i-htti;i;//www.o[c,gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
display a currently valid OMS control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
3.Page V.C. Summer Nuclear Station, Unit 1 05000 395 1
OF 4
- 4. Title CONDITION PROHIBITED BY TECHNICAL SPECIFICATION 3.4.6.1
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved I
Sequential I Rev Facility Name Docket Number Month Day Year Year Number No.
Month Day Year 05000 Facility Name Docket Number 12 6
2018 2019.
001 01 8
19 2019 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply)
D 20.2201{b)
D 20.2203{a){3){i)
D 50. 73{a)(2){ii)(A)
D 50. 73(a)(2)(viii)(A)
D 20.2201{d)
D 20.2203{a){3){ii)
D 50. 73(a)(2)(ii){B)
D 50. 73{a){2)(viii){B) 1 D 20.2203{a){1)
D 20.2203{a){4)
D 50. 73(a)(2)(iii)
D 50. 73(a)(2)(ix)(A)
D 20.2203{a){2)(i)
D 50.36{c)(1 ){i)(A)
D 50. 73{a)(2)(iv)(A)
D 50. 73{a)(2)(x)
- 10. Power Level D 20.2203{a){2)(ii)
D 50.36{c)(1 )(ii){A)
D 50. 73(a)(2){v)(A)
D 73.71{a)(4)
D 20.2203{a)(2)(iii)
D 50.36{c)(2)
D 50.73{a)(2)(v)(B)
D 73.71{a)(5)
D 20.2203{a){2){iv)
D 50.46{a){3){ii)
D 50.73{a){2){v){C)
D 73.77{a)(1) 100 D 20.2203{a){2)(v)
D 50. 73{a)(2)(i)(A)
D 50. 73{a){2){v){D)
D 73. 77(a){2){i)
D 20.2203{a)(2)(vi) 0 50.73{a){2){i){B)
D 50.73{a){2){vii)
D 73. 77(a){2){ii)
D 50. 73{a)(2){i){C)
D Other (Specify in Abstract below or in
2.0 EVENT ANALYSIS
During RF24, it was identified that biological growth in the RBCU condensate drain sensing lines was obstructing flow.
Previous cleaning efforts did not include removal of RBCU condensate drain valves that collected debris and acted as flow choke points. The restricted flow of condensate created an environment that promoted algae growth. As a result, this algae and other debris within the drain sensing lines impacted flow to the RBCU condensate drain flow switches, causing inoperable flow switches (both IFS01900A and IFS01900B) during CY24, as described below. With the installation of the new RB chiller system in preparation for RF23, the industrial cooling water supplied to the RBCU coils is now colder than the original design, resulting in increased moisture removal by the RBCUs. This larger volume of condensate is thought to be a contributor to the increased amount of algae growth over the past cycle.
I VCSNS completed RF23 on June 1, 2017 and entered normal power operations. On September 16, 2017, RBCU condensate flow switch 'A' (IFS01900A) was declared inoperable and removed from service. IFS01900A had experienced a locked in HI alarm without condensate flow present due to algae and other debris in the RBCU drain sensing line, which could not be corrected during power operation. VCSNS credited IFS01900B to meet TS LCO 3.4.6.1 for the remainder of the cycle.
RBCU condensate flow switch 'B' (IFS01900B) was discovered inoperable on October 29, 2018, during RF24.
IFS01900B was found to not respond when flow was introduced to the switch using the demineralized water system, due to algae and other debris present in the RBCU drain sensing line. A past operability determination was performed and on December 6, 2018, it was concluded that the switch could not have been relied on to actuate during the previous cycle.
Therefore, it was conservatively determined to consider IFS01900B inoperable during the past cycle (June 1, 2017 to October 6, 2018).
As a result of the past operability determination for IFS01900B and the concurrent inoperability of IFS01900A, VCSNS did not have an operable RBCU condensate flow rate monitor, as required by TS LCO 3.4.6.1, from September 16, 2017 to October 6, 2018.
Evaluation of station compliance with LCO 3.4.6.1 and associated TS Actions initially determined that the required actions were implemented by normal operations procedures, including Surveillance Test Procedure STP-114.002, Operational Leakage Calculation. However, further review determined that VCSNS did not comply with TS 3.4.6.1 Action c for short periods of time between September 16, 2017 and October 6, 2018. Consequently, the plant operated in a I
condition prohibited by TS, which is reportable under 10 CFR 50. 73(a)(2)(i)(B).
During RF24, VCSNS Unit 1 implemented new cleaning and maintenance practices, restored operability of both IFS01900A and IFS01900B, and has exited TS 3.4.6.1 Action c.
Since the submittal of LER 2019-001-00, IFS01900B has been removed from service. During performance of a routinely-performed Reactor Building Cooling Unit Functional and Iodine Removal System Test on May 25, 2019, IFS01900B came into alarm, but did not clear when the test was complete as was expected. This condition was documented in CR-19-01939. While IFS01900A is still operable, VCSNS has elected to conservatively implement TS 3.4.6.1 Action c requirements until operability of IFS01900B is restored.
VCSNS is pursuing opportunities to improve reliability during RF25.
3.0 SAFETY SIGNIFICANCE
There was no quantified risk impact from this event. The Probabilistic Risk Assessment does not model the RBCU condensate drain flow switches or credit the function. Two diverse methods of leak detection were operable at the time of the missed action. Channel checks of the RB atmospheric radiation monitor were performed approximately I every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with satisfactory results. RB sump level instrumentation was available without interruption.
4.0 PREVIOUS OCCURRENCE There have been no other instances of TS violations related to leak detection systems in containment during the past three (3) years.
It is noted that this event is similar to LER 2007-003-01, which documents a previous TS violation due to clogging of IFS01900A and IFS01900B due to inorganic foreign material within the drain lines. CR-19-02143 is evaluating the ineffectiveness of the corrective actions associated with the event documented by LER 2007-003-01 in preventing this event.
5.0 CORRECTIVE ACTIONS
VCSNS implemented corrective actions during RF24 following discovery of the obstructed condensate drain line and is investigating opportunities for improved reliability to be implemented during RF25.
During RF24, inspection and cleaning techniques were refined and utilized to restore both RBCU condensate flow switches. Station procedure MMP-460.038, Revision 1 "Inspection, Cleaning, and Lubrication of Reactor Building Cooling Units XAA0001A/B and XAA0002A/B" has been updated to include the added cleaning techniques of the flow switches. MMP-460.038, Revision 1 added a new section, Section 7.3 and Attachment II for cleaning RBCU drain lines. This technique includes ensuring the inside of all piping around IFS01900A and IFS01900B is scrubbed to remove the buildup, soaked with hydrogen peroxide, and flushed with demineralized water multiple times. The lines are then inspected to verify cleanliness and to ensure that there are no obstructions remaining.
In addition to the refined techniques used, the pipe cleaning boundary upstream of the flow switches has been expanded to areas that were not previously included in the inspection or cleaning. This includes physical and chemical cleaning of the drain line trap and sensing lines that direct flow to the RBCU condensate flow switches.
Plant engineers developed the new expanded cleaning boundary and techniques.
I Implementation of the expanded and refined inspection and cleaning techniques cleared the drain sensing line obstruction. Testing performed confirmed flow switch operability for both IFS01900A and IFS01900B, indicating that both would have operated as expected if the line had not been obstructed.
In preparation for the upcoming RF25 outage (Spring 2020), VCSNS is investigating opportunities to improve RBCU I
condensate flow monitoring. Page 4
of 4
|
---|
|
|
|
05000395/LER-2019-001-01, Regarding Condition Prohibited by Technical Specification 3.4.6.1 | Regarding Condition Prohibited by Technical Specification 3.4.6.1 | | 05000395/LER-2019-001, Condition Prohibited by Technical Specification 3.4.6.1 | Condition Prohibited by Technical Specification 3.4.6.1 | 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)(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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) | 05000395/LER-2019-002, Regarding Condition Prohibited by Technical Specification 3.6.4 | Regarding Condition Prohibited by Technical Specification 3.6.4 | 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)(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-2019-003-01, (Vcsns), Completion of a Technical Specification Required for Plant Shutdown | (Vcsns), Completion of a Technical Specification Required for Plant Shutdown | | 05000395/LER-2019-003, Completion of a Technical Specification Required Plant Shutdown | Completion of a Technical Specification Required Plant Shutdown | 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) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii)(A) | 05000395/LER-2019-004, 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.1 | 4-00 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Condition Prohibited by Technical Specification 3.6.1.1 | 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)(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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
|