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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 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 ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves ML24250A0782024-10-22022 October 2024 Relief Request RR-5-V1 Regarding Service Water Return Header Check 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 ML24274A1942024-09-26026 September 2024 (Vcsns), Unit 1 Subsequent License Renewal Application (SLRA) First 10 CFR 54.21(b) Annual Amendment IR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public 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) 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) 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 ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24185A1902024-06-25025 June 2024 Submittal of Updated Final Safety Analysis Report, Revision 24 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 ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 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-1999-014, Re Kaowool Fire Barriers Outside 10CFR50 Appendix R Design Basis |
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3951999014R02 - NRC Website |
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text
Stephen A. Byme Senior Vice President, Nuclear Operations 803.345.4622 A SCANA COMPANY July 1, 2003 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir / Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSEE EVENT REPORT (LER 1999-014-02)
KAOWOOL FIRE BARRIERS OUTSIDE IOCFR50 APPENDIX R DESIGN BASIS Attached is a revised Licensee Event Report, LER 1999-014-02, for the Virgil C.
Summer Nuclear Station (VCSNS). This report updates the compensatory actions taken and planned in response to the testing results for KAOWOOL triple wrap fire barriers. This issue is being reported per 10 CFR 50.73(a)(2)(ii)(B).
Should you have any questions, please call Mr. Jeffrey Pease at (803) 345-4124.
Very truly yours, Stephen A. Byrne JWPISAB/dr Attachment c:
N. 0. Lorick N. S. Cams T. G. Eppink (w/o attachment)
R. J. White L. A. Reyes K. R. Cotton NRC Resident Inspector K. M. Sutton D. L. Abstance P. Ledbetter EPIX Coordinator INPO Records Center J&H Marsh & McLennan QC NSRC RTS (0-C-99-1 520)
File (818.07)
DMS (RC-03-0131)
SCE&G I Vrgil C. Summer Nuclear Station
- P. 0. Box 88. Jenkinsville, South Carolina 29065.T (803) 345.5209. www.scana.om
ARC ORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 0613012001 (6-1998) the NRC may not conduct or sponsor, and a person Is not required to respond to. the Information collection.
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~~~~~~~~~SUBMISSION Ii ii l(ifyes, complete EXPECTED SUBMISSION DATE).II DATE (IS) II II ABSTRACT (Umftto 14M spaes, Le., approxiately15singlespaoed typewrtte ons) 16)
On December 28, 1999, Virgil C. Summer Nuclear Station (VCSNS) commissioned testing on Kaowooll triple wrap fire barriers. The testing was conducted to confirm the fire resistance rating of typical plantl specific design considerations.
On December 29, 1999, engineering personnel determined, fr-om a review of preliminary test data, that somel as installed applications may not meet the current regulatory requirements for maintaining one train free of fire damage for one hour. Station Condition Evaluation Report (CER) 99-1520 was generated to documentl this event and to track actions for resolution.l As a result of this test, all surface mounted configurations, and 4" and larger conduit and 6" x 36" racewaysl suspended in open air, passed the l -hour fire rating. Some of the cables in I" conduit, 6" x 6" raceways, and air drop cables suspended in open air failed the Generic Letter (GL) 86-10, Supplement I megger whenl subjected to an ASTM E-1 19 fire test.l VCSNS has implemented compensatory actions (fire watches) as a conservative measure, for all Kaowool Fire Barriers that are needed to achieve and maintain post-fire safe shutdown in accordance withl Appendix R and I OCFR50.48. Adjustments to these compensatory actions will be based on the results ofl further engineering evaluation, and the completion of plant modifications.ll NRC FORM 366 (6-1998)U.S. NUCLEAR REGULATORY COMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAMEI DOCKET NUMBER 2 LER NUMBER 6 PAGE 3 V. C. Summer Nuclear Station 05000395 YEA NUMBER I
NUMBER 2 of 3 I
1999 014 02 TEXT (If nve space Is requhred, use addational copies of NRC Form 366A) (17)
PLANT IDENTIFICATION Westinghouse - Pressurized Water Reactor EOU3PMENT IDENTIFICATION Kaowool Fire Barrier for Electrical Cables IDENTIFICATION OF EVENT Testing of Kaowool triple wrap fire barriers demonstrates that some applications do not meet design requirements.
EVENT DATE December29, 1999 REPORT DATE January26,2000 SUPPLEMENT 1 REPORT DATE April 1,2000 REVISION 2 REPORT DATE July 1, 2003
CONDITIONS PRIOR TO EVENT
Mode 1, 100% power
DESCRIPTION OF EVENT
Virgil C. Summer Nuclear Station (VCSNS) commissioned fire-endurance testing to be performed on Kaowool triple wrap fire barriers on December 28, 1999. A large scale 1-hour test was conducted at the Omega Test Labs in San Antonio, Texas. The testing was conducted on representative sample conduits and cable trays, in typical VCSNS configurations, to confirm the fire resistance rating of these barriers and verify our existing design and licensing basis. This testing was being performed as a voluntary initiative at the request of the NRC as discussed in SECY 99-204, "Kaowool and FP-60 Fire Barriers."
Engineering personnel determined, on December 29, 1999, that preliminary results indicate that some applications may not meet the current regulatory requirements for maintaining one train free of fire damage for a one hour duration (10 CFR 50 Appendix R, Section III.G.2.)U.S. NUCLEAR REGULATORY COMMISSION (81998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 1) l DOCKET NUMBER 2 LER NUMBER 6)
PAGE (3 V. C. Summer Nuclear Station 05000395 YEAR SEIUER l
IN I
~~~I NUMBER NUMBER 3 of 3 l
l
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~~1999 014 02 TEXT (ffxmoe space Is required, use additional copies of NRC Form 3664) (17)
ANALYSIS Some limited cable failures were identified. The limited failures were experienced in small cable, conduit, and tray applications installed in open-air configurations (not running along wall or ceiling). Other applications; large conduit, tray, and surface mounted conduit performed satisfactorily, based on a preliminary review of the test data.
VCSNS has a total of 30 Kaowool triple wrap applications that are required for Appendix R The 30 Kaowool applications are limited to 18 separate fire areas/zones. Of the 18 fire areas, 14 have fire loads less than the current designed fire rating of the enclosure with the other four located in cable chases that have automatic fire suppression. Additionally, 16 of the affected fire areas, have acceptable core damage frequency, as calculated during Phase 1 of the IPEEE evaluation, with the remaining 2 found acceptable during Phase 2 by fire modeling. In four instances the air drop cables required an additional (2) layers of 1" Kaowool wrap and modifications (ECR-50205) to provide thermal masses above the tested configurations to protect these individual cables.
IMMEDIATE ACTIONS VCSNS has implemented compensatory actions (roving fire watches) for all 30 Appendix R Kaowool triple wrap applications (18 fire areas/zones) as a conservative and precautionary measure.
LONG TERM CORPECTIVE ACTIONS VC Summer has implemented modifications (ECR 50205), based on the results of the engineering evaluations to address affected areas by providing additional protection for exposed silicone foam barriers, exposed supports (potential thermal shorts), and the air drop cables. This change included evaluations resulting in 11 of the 30 Kaowool triple wrap applications meeting all design and licensing basis.
VC Summer is also pursuing additional modifications to address the remaining 19 Kaowool applications, which include re-routing cables, adding suppression, and using a qualified fire wrap material. These changes are intended to bring VCSNS into compliance with existing design and licensing bases. These modifications are scheduled to be completed by December 31, 2005.
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05000395/LER-1999-001, :on 990311,missed Surveillance Test for Electrical Equipment Protective Devices Was Noted.Caused by Inadequate Surveillance Tps.Fire Watches Were Posted Per TS 3.8.4.3 LCO Requirements.With |
- on 990311,missed Surveillance Test for Electrical Equipment Protective Devices Was Noted.Caused by Inadequate Surveillance Tps.Fire Watches Were Posted Per TS 3.8.4.3 LCO Requirements.With
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | 05000395/LER-1999-003, :on 990412,surveillance on Manipulator Crane Load Cell Was Missed.Caused by Lack of Familiarity with VCSNS TS Srs.Core Alterations Were Suspended.With |
- on 990412,surveillance on Manipulator Crane Load Cell Was Missed.Caused by Lack of Familiarity with VCSNS TS Srs.Core Alterations Were Suspended.With
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 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)(iii) 10 CFR 50.73(a)(2)(viii) | 05000395/LER-1999-004, :on 990413,fuel Assembly Top Nozzle Holddown Spring Failure Was Noted.Caused by Failure of Holddown Spring Attaching Screws.Replaced Top Nozzles on 28 twice- Burned Fuel Assemblies.With |
- on 990413,fuel Assembly Top Nozzle Holddown Spring Failure Was Noted.Caused by Failure of Holddown Spring Attaching Screws.Replaced Top Nozzles on 28 twice- Burned Fuel Assemblies.With
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | 05000395/LER-1999-007, :on 990511,missed Surveillance Re Tadot Was Noted.Caused by Conflict in Requirements Between Surveillance Frequency & Actual Mode Requirment for Tadot. Revised Procedure STP-142.005.With |
- on 990511,missed Surveillance Re Tadot Was Noted.Caused by Conflict in Requirements Between Surveillance Frequency & Actual Mode Requirment for Tadot. Revised Procedure STP-142.005.With
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | 05000395/LER-1999-008, :on 990518,manual RT Initiated Due to Main Turbine High Vibration.Caused by Light Rubbing within New Monoblock Turbine Rotor.Reactor Power Was Reduced.With |
- on 990518,manual RT Initiated Due to Main Turbine High Vibration.Caused by Light Rubbing within New Monoblock Turbine Rotor.Reactor Power Was Reduced.With
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | 05000395/LER-1999-009, :on 990604,plant Experienced Reactor Trip Due to Spurious High Flux Trip Signal in Power Range Nuclear Instrument Drawer N43.Defective Meter Was Replaced & Plant Was Returned to Svc on 990606.With |
- on 990604,plant Experienced Reactor Trip Due to Spurious High Flux Trip Signal in Power Range Nuclear Instrument Drawer N43.Defective Meter Was Replaced & Plant Was Returned to Svc on 990606.With
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | 05000395/LER-1999-010, :on 990730,discovered That UHS Dependent Components Were Potentially Outside Design Basis of Plant. Caused Indeterminate.Blank Flanges Were Subsequently Not Reinstalled.With |
- on 990730,discovered That UHS Dependent Components Were Potentially Outside Design Basis of Plant. Caused Indeterminate.Blank Flanges Were Subsequently Not Reinstalled.With
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | 05000395/LER-1999-014-03, Re Kaowool Fire Barriers Outside 10 CFR 50 Appendix R Design Basis | Re Kaowool Fire Barriers Outside 10 CFR 50 Appendix R Design Basis | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i) | 05000395/LER-1999-014-02, Re Kaowool Fire Barriers Outside 10CFR50 Appendix R Design Basis | Re Kaowool Fire Barriers Outside 10CFR50 Appendix R Design Basis | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
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