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Category:Letter
MONTHYEARML24278A2832024-11-0707 November 2024 Letter to E. Carr Environmental Impact Statement Scoping Summary Report for Virgil C. Summer Nuclear Station Unit 1 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 ML24256A2322024-10-22022 October 2024 Relief Request RR-5-P1 Charging/Safety Injection Pumps ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves 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) 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) 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) 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) 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) 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 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 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 ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d 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 ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24088A2062024-03-26026 March 2024 Annual Operating Report ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. 2024-09-26
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000395/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-2022-001, (VCSNS) Unit 1, Manual Reactor Trip Due to Main Transformer Fault2022-01-14014 January 2022 (VCSNS) Unit 1, Manual Reactor Trip Due to Main Transformer Fault 05000395/LER-2021-001, (Vcsns), Unit 1, Condition Prohibited by Technical Specifications2021-08-26026 August 2021 (Vcsns), Unit 1, Condition Prohibited by Technical Specifications 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 RC-18-0056, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors2018-04-25025 April 2018 (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors 05000395/LER-2017-0052017-12-22022 December 2017 AUTOMATIC REACTOR TRIP DUE TO MAIN TURBINE TRIP, LER 17-005-00 for V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip 05000395/LER-2017-0062017-12-15015 December 2017 TECHNICAL SPECIFICATION ACTION NOT MET FOR INOPERABLE OXYGEN MONITOR, LER 17-006-00 for Virgil C. Summer, Unit 1, Regarding Technical Specification Action not Met for Inoperable Oxygen Monitor 05000395/LER-2017-0032017-10-26026 October 2017 FAILED LIGHTNING ARRESTER ON MAIN TRANSFORMER CAUSES REACTOR TRIP, LER 17-003-00 For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester On Main Transformer Causes Reactor Trip 05000395/LER-2017-0022017-08-25025 August 2017 Low Feedwater Flow to the 'B' Steam Generator Causes Automatic Reactor Trip, LER 17-002-00 for V.C. Summer, Unit 1, Regarding Low Feedwater Flow to the 'B' Steam Generator Causes Automatic Reactor Trip 05000395/LER-2017-0012017-07-24024 July 2017 C MAIN FFFDWATER PUMP FAILURE '1'0 TRIP RESUI,TS IN LOSS OF EMERGENCY FE,EDWATER AUTO START ACTUATION SIGNAL, LER 17-001-00 for V.C. Summer, Unit 1, Regarding C Main Feedwater Failure to Trip Results in Loss of Emergency Feedwater Auto Start Actuation Signal RC-15-0190, Special Report (Spr) 2014-005-01, Loss or Theft of License Material2015-12-16016 December 2015 Special Report (Spr) 2014-005-01, Loss or Theft of License Material RC-15-0179, Special Report (Spr) 2015-002 Regarding One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days2015-11-0303 November 2015 Special Report (Spr) 2015-002 Regarding One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days RC-15-0139, Submittal of Special Report (Spr) 2015-001 Regarding the Loose-Part Monitoring System (Lpms) Channel Number 8 Being Inoperable in Excess of 30 Days2015-08-20020 August 2015 Submittal of Special Report (Spr) 2015-001 Regarding the Loose-Part Monitoring System (Lpms) Channel Number 8 Being Inoperable in Excess of 30 Days RC-14-0084, Special Report 2014-003 for V.C. Summer, One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days2014-05-14014 May 2014 Special Report 2014-003 for V.C. Summer, One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days RC-14-0085, Special Report 2014-002 for V.C. Summer, Degraded Conditions Lasting Longer than Seven Days2014-05-14014 May 2014 Special Report 2014-002 for V.C. Summer, Degraded Conditions Lasting Longer than Seven Days ML12334A4432012-11-27027 November 2012 SR 12-002-00 for Virgil C. Summer, Unit 1 Regarding Meteorological Monitoring Channels Being Inoperable for More than Seven Days ML12188A5422012-07-0303 July 2012 Special Report 2012-001 ML12079A2862012-03-16016 March 2012 LER 12-01-00 for Virgil C. Summer, Unit 1 Regarding Core Exit Thermocouples Inoperable Due to an Inadequate Maintenance Procedure ML11186A9742011-06-30030 June 2011 Regarding Depressurization of the 'C' Steam Line Creating a Differential Pressure Greater than 97 PSIG Between the Steam Lines, Initiating a Safety Injection ML11117A3042011-04-25025 April 2011 V. C. Summer, Unit 1, Submittal of Special Report (Spr) 2011-001 Re Control Building Fire/Pressure Door (DRCB/102) Being Inoperable for Greater than Seven Days Prior to Completing Repair of the Door ML0614201452006-05-17017 May 2006 LER 99-014-03 for Virgil C. Summer Nuclear Station, Re Kaowool Fire Barriers Outside 10 CFR 50 Appendix R Design Basis RC-06-0051, Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours2006-03-13013 March 2006 Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours ML0527803362005-09-28028 September 2005 LER 05-S01-01 for Virgil C. Summer Nuclear Station Regarding Entry of Unauthorized Employee Into the Protected Area RC-05-0095, LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area2005-06-22022 June 2005 LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area ML0335001292003-12-11011 December 2003 LER 03-S03-00 for Virgil C. Summer Regarding Access to Protected Area by an Individual Without Proper Authorization ML0326605072003-09-16016 September 2003 LER 03-S02-00 for Virgil C. Summer Regarding Access to Protected Area by an Individual with Expired Training ML0318404692003-07-0101 July 2003 LER 99-014-02, Virgil C. Summer Re Kaowool Fire Barriers Outside 10CFR50 Appendix R Design Basis ML0308605122003-03-20020 March 2003 LER 03-S01-00 from Summer Regarding Access to Protected Area by an Individual with an Expired Badge 2024-04-17
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Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 A SCANA COMPANY May 17, 2006 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 1999-014-03)
KAOWOOL FIRE BARRIERS OUTSIDE 10CFR50 APPENDIX R DESIGN BASIS Attached is a revised Licensee Event Report, LER 1999-014-03, for the Virgil C.Summer Nuclear Station (VCSNS). This report updates the completion date for the long term corrective actions. This issue is being reported per 10 CFR 50.73(a)(2)(ii)(B).
Should you have any questions, please call Mr. Robert G. Sweet at (803) 345 -4080.Very truly yours, C)u Wr 'r34 Jeffrey B. Archie MWD/JBA/dr Attachment c: K. B. Marsh S. A. Byrne N. S. Cams J. H. Hamilton (w/o attachment)
R. J. White W. D. Travers R. E. Martin NRC Resident Inspector M. N. Browne K. M. Sutton D. L. Abstance P. Ledbetter EPIX Coordinator INPO Records Center J&H Marsh & McLennan NSRC RTS (C-99-1520)
File (818.07)DMS (RC-06-0100)
--&1-;?:'e;1 SCE&G I Virgil C. Summer Nuclear Station
- P.O. Box 88. Jenkinsville, South Carolina 29065 .T (803) 345.5209 .www.scana.com NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 0613012001 (6-1998) Estimated burden per response to comply with this mandatory information collection request: 50.0 hrs. Reported lessons learned are incorporated Into the licensing process and fed back to industry.
Forward comments regarding burden estimate to the Records Management Branch (T-6 F33), U.S. Nuclear LICENSEE EVENT REPORT (LER) R ulatory Commission, Washin on DC 20555-0001, and to the Paperwork Rugction Prec 3150- 6ffice of Management fand Budget, Washington, Dr2053. If 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.
FACILITY NAME (1) lDOCKET NUMBER (2) PAGE (3)Virgil C. Summer Nuclear Station 0 5 0 0 0 3 9 5 1 of 3 TITLE (4)Kaowool Fire Barriers Outside 1OCFR50 Appendix R Design Basis EVENT DATE (5) LER NUMBER (6 REPORT DAT7E mI OTHER FACILITIES INVOLVED (8)SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR I 05000 FACILITY NAME DOCKET NUMBER 12 29 99 1999-- 014 -- 03 5 17 2006 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 4: (Check one or more) (11)MODE (9) 1 l20.2201(b)
I 20.2203(aX2Xv)
I 50.73(aX2X)I 50.73(aX2#01)
POWER 20.2203(a)(1)
I j20.2203(aX3X1)
X 150.73(a)(2XII) 50.73(a)(2)(i)
LEVEL (10) 100 -20.2203(aX2Xi)
_20.2203(aX3Xii) 1 50.73(a)(2Xiii) 73.71 4 0.2203(a)(2)(ii)
..J20.2203(a)X4) 50.73(aX2Xiv)
OTHER 20.2203(aX2)(;;)
l 50.36(CXI) l 50.73(aX2Xv)
Soecifv In Abstract below I 20.2203(aX2)(Iv)
- 50.36(cX2) 50.73(aX2Xv1i) orInf NRC FORM 366A LICENSEE CONTACT FOR THIS LER (12)NAME ITELEPHONE NUMBER (Include Area Code)R. G. Sweet I Manager, Nuclear Licensing l (8 0 3) 3 4 5 -4 0 8 0 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) _ I CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX MA CAUSE SYSTEM COMPONENT MANUFACTURER EP ROEPORTBL ITIEPORTBL B KP CBL5 BO15 l YES A IIII_ I SUPPLEMENTAL REPORT EXPECTED (14) j EXPECTED IMONTH DAY YEAR I YES omltNO E SUBMISSION A I Il(if yes, complete EXPECTED SUBMISSION DATE). I XII DATE (I5) IIII I ABSTRACT (Umit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines) (16)On December 28, 1999, Virgil C. Summer Nuclear Station (VCSNS) commissioned testing on Kaowool triple wrap fire barriers.
The testing was conducted to confirm the fire resistance rating of typical plant specific design considerations.
On December 29, 1999, engineering personnel determined, from a review of preliminary test data, that some 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 document this event and to track actions for resolution.
As a result of this test, all surface mounted configurations, and 4" and larger conduit and 6" x 36" raceways suspended in open air, passed the 1 -hour fire rating. Some of the cables in 1 " conduit, 6" x 6" raceways, and air drop cables suspended in open air failed the Generic Letter (GL) 86-10, Supplement I megger when subjected to an ASTM E-1 19 fire test.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 with Appendix R and 1OCFR50.48.
Adjustments to these compensatory actions will be based on the results of fiurther engineering evaluation, and the completion of plant modifications.
NRC FORM 366 (6-1998)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)V. C. Summer Nuclear Station 05000395 NSEQUENTIR REVISION 2 of 3 1 1999 014 03 l TEXT (if more space is required, use additional copies of NRC Form 366A) (17)PLANT IDENTIFICATION Westinghouse
-Pressurized Water Reactor EQUIPMENT 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 December 29, 1999 REPORT DATE January 26, 2000 SUPPLEMENT 1 REPORT DATE April 1, 2000 REVISION 2 REPORT DATE July 1, 2003 REVISION 3 REPORT DATE May 17,2006 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 ll.G.2.)NRC Form 366A (6-1998)
I NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)V. C. Summer Nuclear Station 05000395 SUMEN NRE 3 of 3 I II 1999 014 03I TEXT (If more space is required, use additional copies of NRC Form 366A) (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 CORRECTIVE ACTIONS VCSNS 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 currently implementing modifications to address the remaining 19 Kaowool applications.
Re-routing cables, adding suppression, and using qualified fire wrap material have been substantially implemented to address these applications.
These modifications are expected to be completed by December 31, 2006.NRC Form 366A (6-1998)