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05000338/LER-2012-00124 March 2012North AnnaDegraded Reactor Coolant System Piping Due To Primary Water Stress Corrosion Cracking
05000341/FIN-2011003-0330 June 2011 23:59:59FermiMethodology Used in the HI-STORM/HI-TRAC Stack-up and Evaluation May Be Inadequate
05000346/LER-2015-00111 February 2015Davis BesseBorated Water Storage Tank (BWST) Rendered Inoperable due to Use of Non-Seismic Purification System
05000361/FIN-2010002-0631 March 2010 23:59:59San OnofreFailure to Perform an Adequate Postmaintenance Test
05000361/LER-2010-001Docket NumberBroken Manual Valve Prevents Timely Condensate Storage Tank Isolation
05000361/LER-2012-00217 March 2012Docket NumberEmergency Diesel Generator Vibration Trip Not Bypassed For Non-Accident Condition
05000362/LER-2006-00615 December 2006Docket NumberOne train of Component Cooling Water considered inoperable for longer than allowed by Technical Specification 3.7.7 due to gas entrainment.
05000364/LER-2009-0016 October 2009Service Water Pump Seismic Supports Degraded
05000366/LER-2016-00113 April 2016
8 June 2016		Hatch2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability
LER 16-001-00 for E.I. Hatch, Unit 2, Regarding 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability
05000373/FIN-2010006-0131 March 2011 23:59:59LaSalleSupporting Structure for Standby Liquid Control System Test Tank Non-Functional During Postulated Design Basis Earthquake (DBE)
05000373/LER-2010-003Lasalle County StationStandby Liquid Control Test Tank Seismic Analysis
05000388/LER-2002-00216 March 2002Susquehanna Steam Electric Station - Unit 21 OF 4
05000395/LER-2012-00117 January 2012Docket NumberVice President, Nuclear Operations
803.345.4342
August 3, 2012SCE~r .so
A SCANA COMPANY
Document Control Desk
U. S. Nuclear Regulatory Commission
Washington, DC 20555
Dear Sir / Madam:
Subject:VVIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1
DOCKET NO. 50-395
OPERATING LICENSE NO. NPF-12
LICENSEE EVENT REPORT (LER 2012-001-01)
CORE EXIT THERMOCOUPLES & REACTOR WATER LEVEL INDICATION
SYSTEM INOPERABLE DUE TO AN INADEQUATE MAINTENANCE
PROCEDURE
Attached is Licensee Event Report (LER) No. 2012-001-01 for the Virgil C. Summer Nuclear
Station Unit 1. This revised report describes a condition where Core Exit Thermocouples and
Reactor Water Level Indication System would not be operable for accident monitoring. This
report is submitted in accordance with 10 CFR 50.73(a)(2)(i)(B).
This letter and attached LER contain no new commitments and no revisions to existing
commitments.
Should you have any questions, please call Bruce Thompson at (803) 931-5042.
Very truly yours,
Dal
Thomas D. Gatlin
TS/TDG/jw
Attachment
c: K. B. Marsh P. Ledbetter
S. A. Byrne J. C. Mellette
J. B. Archie EPIX Coordinator
N. S. Carps K. M. Sutton
J. H. Hamilton INPO Records Center
R. J. White Marsh USA, Inc.
W. M. Cherry R. J. Schwartz
V. M. McCree NSRC
R. E. Martin RTS (CR-11-01807)
NRC Resident Inspector FileV(818.07)
M. N. Browne PRSF (RC-12-0116)
V fALVirgil C. Summer Station • Post Office Box 88 .Jenkinsville, SC • 29065 • F (803) 345-5209
1
NRC FORM 366
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013
(10-2010) Estimated burden per response to comply with this mandatory collection
request: 80 hours.0Reported lessons learned are incorporated into the
licensing process and fed back to industry. Send comments regarding burden
estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, or by Internet e-mail to
infocollects.resource@nrc.gov, and to the Desk Officer, Office of Information
and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management andLICENSEE EVENT REPORT (LER) Budget, Washington, DC 20503. If a means used to impose an information(See reverse for required number of 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, thedigits/characters for each block) information collection.
1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE
Virgil C. Summer Nuclear Station Unit 1 05000 395 1 OF 5
4. TITLE
Core Exit Thermocouples & Reactor Water Level Indication System Inoperable due to Inadequate Maintenance Procedure
05000456/FIN-2013002-0631 March 2013 23:59:59BraidwoodCurrent Licensing Basis Requirements for RCS Pressure Control Function During a Postulated Seismic Event in Reference to NRC RSB BTP 5-1
05000528/FIN-2009008-0230 September 2009 23:59:59Palo VerdeFailure to Perform an Adequate Operability Evaluation for the Condensate Storage Tank
0CAN011601, Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Bdbees)12 January 2016Arkansas NuclearNotification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Bdbees)
0CAN020803, Notification of Submission of Final Supplemental Response within 90 Days of Completion of Generic Letter 2004-02 Actions28 February 2008Arkansas NuclearNotification of Submission of Final Supplemental Response within 90 Days of Completion of Generic Letter 2004-02 Actions
0CAN021302, Units 1 and 2 - Overall Integrated Plan in Response to March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)28 February 2013Arkansas NuclearUnits 1 and 2 - Overall Integrated Plan in Response to March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
0CAN022102, Unit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping8 February 2021Arkansas NuclearUnit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping
0CAN049501, Application for Amends to Licenses DPR-51 & NPF-6,revising TS Associated W/Control Room Ventilation Sys4 April 1995Arkansas NuclearApplication for Amends to Licenses DPR-51 & NPF-6,revising TS Associated W/Control Room Ventilation Sys
0CAN090801, GL 2004-02 Final Supplemental Response15 September 2008Arkansas NuclearGL 2004-02 Final Supplemental Response
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0CAN092301, Emergency Plan Implementing Procedure Revision5 September 2023Arkansas NuclearEmergency Plan Implementing Procedure Revision
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07201007		Request for Exemption from Requirements of 10 CFR 72.212(b)(3)
0CAN128213, Forwards Final Response to NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, Addressing Overhead Handling Sys in Vicinity of Fuel Storage Pools & Containment & Safe Load Paths22 December 1982Arkansas NuclearForwards Final Response to NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, Addressing Overhead Handling Sys in Vicinity of Fuel Storage Pools & Containment & Safe Load Paths
0CAN129603, Submits Proposed TS Change Request Re Control Room Ventilation Sys19 December 1996Arkansas NuclearSubmits Proposed TS Change Request Re Control Room Ventilation Sys
1CAN040302, License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.32 April 2003Arkansas NuclearLicense Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.3
1CAN041501, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Level (SFP) Instrumentation14 April 2015Arkansas NuclearCompletion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Level (SFP) Instrumentation
1CAN058608, Responds to Open Items Noted in 860331 Safety Sys Functional Insp Rept 50-313/86-01 Re Emergency Feedwater Sys.Corrective Actions:Change Made to FSAR Sections to Expand & Upgrade Discussion of Postulated high-energy Line Breaks23 May 1986Arkansas NuclearResponds to Open Items Noted in 860331 Safety Sys Functional Insp Rept 50-313/86-01 Re Emergency Feedwater Sys.Corrective Actions:Change Made to FSAR Sections to Expand & Upgrade Discussion of Postulated high-energy Line Breaks
1CAN070603, License Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool27 July 2006Arkansas NuclearLicense Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool
1CAN078611, Forwards Addl Info Re seismically-qualified,partially tornado-protected Condensate Storage Tank for Info Only & Not for Review & Approval of 860521 Tech Spec Change for Tank Design31 July 1986Arkansas NuclearForwards Addl Info Re seismically-qualified,partially tornado-protected Condensate Storage Tank for Info Only & Not for Review & Approval of 860521 Tech Spec Change for Tank Design
1CAN078903, Forwards Partial Response to Questions Re Seismically Qualified,Partially Tornado Protected Condensate Storage Tank.Final Response to Be Submitted by 90011510 July 1989Arkansas NuclearForwards Partial Response to Questions Re Seismically Qualified,Partially Tornado Protected Condensate Storage Tank.Final Response to Be Submitted by 900115
1CAN109502, Forwards 10CFR50.59 Summary Rept for 1994,containing Brief Description of Changes in Procedures & in Facility as Described in SAR25 October 1995Arkansas NuclearForwards 10CFR50.59 Summary Rept for 1994,containing Brief Description of Changes in Procedures & in Facility as Described in SAR
2CAN010304, Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions29 January 2003Arkansas NuclearArkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions
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2CAN030706, Arkansas, Unit 2 - License Amendment Request to Support a Partial Re-Rack and Revised Loading Patterns in the Spent Fuel Pool30 March 2007Arkansas NuclearArkansas, Unit 2 - License Amendment Request to Support a Partial Re-Rack and Revised Loading Patterns in the Spent Fuel Pool
2CAN038604, Requests NRC Approval to Utilize ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Piping, for Response Spectrum Analysis of Selected Piping.Planned Use of Code Case Listed.Fee Paid28 March 1986Arkansas NuclearRequests NRC Approval to Utilize ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Piping, for Response Spectrum Analysis of Selected Piping.Planned Use of Code Case Listed.Fee Paid
2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 45 April 2023Arkansas NuclearLicense Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
2CAN050303, Emergency Diesel Generator (EDG) Allowed Outage Time (AOT) Request for Additional Information (RAI) Response6 May 2003Arkansas NuclearEmergency Diesel Generator (EDG) Allowed Outage Time (AOT) Request for Additional Information (RAI) Response
2CAN071202, Supplemental to License Amendment Request to Adopt NFPA-805 Performance - Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)10 July 2012Arkansas NuclearSupplemental to License Amendment Request to Adopt NFPA-805 Performance - Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)
2CAN081401, Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8057 August 2014Arkansas NuclearResponse to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
2CAN101601, License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications27 October 2016Arkansas NuclearLicense Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications
3F0208-05, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.29 February 2008Crystal RiverSupplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
3F0385-14, Documents Results of Assessment of Impact of Capacity Re IE Bulletin 79-02 Wej-it Concrete Anchors Installed on Large Bore safety-related Piping Sys.Followup to Outstanding Issues Identified in Insp Rept 50-302/84-32 Provided14 March 1985Crystal RiverDocuments Results of Assessment of Impact of Capacity Re IE Bulletin 79-02 Wej-it Concrete Anchors Installed on Large Bore safety-related Piping Sys.Followup to Outstanding Issues Identified in Insp Rept 50-302/84-32 Provided
3F0817-03, Rev. 0, Defueled Safety Analysis Report31 August 2017Crystal RiverRev. 0, Defueled Safety Analysis Report
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3F0988-16, Forwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe Breaks27 September 1988Crystal RiverForwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe Breaks
A03831, Forwards Addl Info Re IE Bulletin 80-11, Masonry Wall Design, in Response to NRC 840224 Request.Final Response to Question 4 Will Be Provided by 8501032 November 1984MillstoneForwards Addl Info Re IE Bulletin 80-11, Masonry Wall Design, in Response to NRC 840224 Request.Final Response to Question 4 Will Be Provided by 850103
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