RC-99-0066, Submits Rept of Status of Decommissioning Funding (RR-1950), for Vsns Per 10CFR50.75
RC-99-0078, Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e)
ML20205G418
ML20205T231
ML20205M043
ML20206P502
RC-99-0090, Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b
ML20206E168
RC-99-0092, Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI
RC-99-0080, Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective
ML20206P577
ML20206L512
RC-99-0105, Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station
RC-99-0104, Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy
ML20207D188
ML20207H524
ML20195H586
RC-99-0114, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation
ML20210B711
RC-99-0131, Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld
RC-99-0129, Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist
RC-99-0127, Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-02
ML20210E377
ML20210B745
RC-99-0147, Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-1988
RC-99-0156, Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm
ML20210Q485
ML20210R550
RC-99-0164, Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d)
RC-99-0152, Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G
RC-99-0171, Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors
ML20211H248
ML20211L518
RC-99-0177, Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.11
RC-99-0173, Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr
ML20211Q891
ML20211N430
ML20212A834
ML20212A695
ML20212C509
RC-99-0184, Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety
RC-99-0181, Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment
RC-99-0192, Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models
RC-98-0207, Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment
RC-98-0189, Provides Assessment Results of GL 98-02, Loss of Rc Inventory & Associated Potential for Loss of Emergency Mitigation Functions While in Shutdown Condition, Per 10CFR50.54f
RC-98-0216, Requests Extension of Response Period to 990115 to Respond to NRC 980908 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Util Intends to Utilize Industry Generic RAI Response
RC-98-0225, Forwards Rev 41 to EP-100, Radiation Emergency Plan. List of Changes by Page Number Affected by Rev 41 Also Encl
RC-98-0226, Forwards Amend 42 to Psp.Changes Do Not Degrade Safeguards Effectiveness in PSP or Safeguards Contingency Plan,As Described in 10CFR50.54(p).Without Encl
RC-99-0005, Responds to 980908 RAI Re GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations
RC-99-0015, Forwards Amend 16 to Training & Qualification Plan,Per 10CFR50.54(p).Summary of Changes,Encl
RC-99-0023, Informs That in Response to GL 97-06,SCE&G Informed NRC of Plan to Perform Secondary Side Examination Scheduled for Refueling Outage RF-11.SCE&G Has Decided to Defer Secondary Side Insp of Sg.Reasons for Change of Plan Listed
RC-99-0026, Provides Response to NRC RAI Re TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear
ML20207J566
RC-99-0048, Informs That Util Has Implemented Policy That Requires All Personnel Granted Unescorted Access to Vsns Satisfactorily Complete Test on Site Specific Info
RC-99-0054, Forwards Rev 2 to VC Summer Nuclear Station Training Simulator Quadrennial Certification Rept,1996-99, Per 10CFR55.45(b)(5)(ii)
RC-99-0053, Requests That Implementation Date of Proposed TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear (Beacon) Be Extended. Util Requests 120 Day Time Frame to Perform Initial Beacon Calibrs During Cycle 12
ML20205B998
RC-99-0066, Submits Rept of Status of Decommissioning Funding (RR-1950), for Vsns Per 10CFR50.75
RC-99-0078, Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e)
RC-99-0090, Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b
RC-99-0092, Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI
RC-99-0080, Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective
RC-99-0105, Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station
RC-99-0104, Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy
RC-99-0114, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation
RC-99-0127, Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-02
RC-99-0129, Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist
RC-99-0131, Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld
RC-99-0147, Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-1988
RC-99-0156, Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm
RC-99-0164, Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d)
RC-99-0152, Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G
RC-99-0171, Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors
ML20211H248
RC-99-0177, Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.11
RC-99-0173, Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr
RC-99-0184, Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety
ML20212C509
RC-99-0181, Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment
RC-99-0192, Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models
POST OFFIC. 764 COLUMBIA SOUTH CAaOLINA 29218 o. w. oixos. Ja.
J)E C 13 A10 : 3 q vie.
a..... r December 8,1932 uvet aa o. aario~s Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street, N.W.
Summer Nuclear Station Docket No. 50/.)5 Operating License No. NPF-12 Thirty Day Written Report LER 82-038
Dear Mr. O'Reilly:
Please find attached Licensee Event Report #82-038 for Virgil C. Summer Nuclear Station.
This Thirty Day Report is required by Technical Specification 6.9.1.13.(b) as a result of entry into Action Statement 6 of Technical Specification 3 3 1,
" Reactor Trip System Instrumentation" and Action Statement 15 of Technical Specification 3.3 2, " Engineered Safety Feature Actuation System Instrumentation," on November 14, 1982.
Should there be any questions, please call us at your convenience.
b Mr. James P. O'Reilly LER No.82-038 Page Two December 8, 1982 DETAILED DESCRIPTION OF EVENT On November 14, 1982 with the Plant in Mode 2, the Main Control Board Indication for Steam Generator "A" Steam Flow (PT-474).
f ailed to indicate system flow.
The inoperable channel was placed in the tripped condition within one (1) hour in accordance with Technical Specification 3.3.1, Action Statement 6, and Technical Specification 3.3.2, Action Statement 15 PROBADLE CONSEQUENCES There were no adverse consequences as the minimum number of channels per loop identified in Tables 3.3-1 and 3.3-3 remained operable while the tripped channel was under test.
CAUSE(S) 0F THE OCCURRENCE The cause of this failure is attributed to the indicator needle sticking to the lower stop.
IMMEDIATE CORRECTIVE ACTIONS TAKEN The channel for Steam Generator "A" Steam Flow was placed in the tripped condition within one (1) hour.
A channel calibration was performed on all components per the appropriate surveillance test procedure with satisfactory results.
Indicator operation was normal when the channel was returned to service on November 15, 1982.
ACTION TAKEN TO PREVENT RECURRENCE The Licensee plans no further action other than normal surveillance testing.
/03L-0:on 820813,while Performing Test on Feeder Breaker for Control Room Train B Normal Ventilation Fan, Breaker Would Not Manually Reset.Caused by Random Failure of Square D Breaker (Fhl 36050-15M).Breaker Replaced
/03L-0:on 820818,after Calibr Pressure Transmitter for RHR Train a Suction Isolation Valve,Valve Operator re-energized & Suction Isolation Valve Shut.Caused by Switch Being Left in Test Position.Personnel Reinstructed
/03L-0:on 820820,isolation Valve in Fire Svc Sys Found Closed,Rendering Fire Suppression Sys Inoperable for Control Bldg Cable Spreading Rooms & Chases.Caused by Header Valve Being Tagged Prior to Entering Mode 6
/03L-0:on 820915,test Signal Generated Causing B Train RHR Header Isolation Valve to Shut & Isolate Suction. Pump Manually Tripped.Surveillance Test Procedure Revised to Line Up Alternate RHR Train W/Valve Locked Out
/03L-0:on 820916,five Smoke Detectors at 400-ft & 412-ft Elevations of Control Bldg Disabled,Rendering Preaction Sprinkler Sys Automatic Actuation Capability Inoperable.Caused by Need to Perform Welding in 400-ft Area
/03L-0:on 820922,several High Range Monitors Failed High.Caused by Moisture Accumulation in Detector Preamp Connections.Plant Completed Initial Fuel Load But Was Not Critical.Monitors Replaced Except RM-G19B
/03L-0:on 820929,svc Water Pond Level Indication Not Verified for Modes 1,2,3 & 4 from 820922-29.Caused by Pond Level Entry Omitted from Operator Logs Due to Personnel Error.Logs Reviewed & Revised
/03L-0:on 820929,Surveillance Test Procedure 128.007 Performed Instead of 128.017 Which Implements Tech Spec to Verify Position of Locked Closed Fire Doors.Caused by Personnel/Numerical Error.Personnel Counseled
/03L-0:on 821001,PORV Block Valve MVG-8000A Would Not Reopen at Conclusion of Reactor Vessel O-ring Leak Test. Caused by Wear in Valve Stem Packing Which Contributed to Overtorque Condition.Stem Packing Replaced
/03L-0:on 820930,Mode 3 Entered W/Pressurizer Relief Tank Level Indication LI-470A Inoperable at Control Room Evacuation Panel.Caused by Transmitter Not Calibr Properly,Due to Defective Amplifier & Calibr Circuit Card
/03L-0:on 820928,reactor Bldg high-range Radiation Monitor RM-G7 Had Problems W/Spiking That Caused High Radiation Alarms.Spikes Caused by Electrical Interference in Detection Cable.Monitor Tested & Returned to Svc
/03L-0:on 821001,differential Pressure Level Transmitter Accumulator Tank a Level Found Below Tech Specs by Approx 7% Following Recalibr.Caused by Transmitter Showing Incorrect Level Indication.Transmitter Recalibr
/03L-0:on 821002,air Pressure Equalizing Valves Would Not Cycle in Proper Sequence,Rendering Reactor Bldg Airlock Inoperable.Caused by Chain Drive Sprocket Shearing Key,Allowing Sprocket to Slip Into Associated Drive Shaft
/03L-0:on 821003,sample Pumps on Reactor Bldg Air Sample Radiation Monitor RMA-2 Tripped Due to Overheating in Cabinet.Caused by Inadequate Cabinet Ventilation.Pumps Cooled & Restarted After Approx 4-h
/03L-0:on 821003,main Control Board Pressure Indicator 0950 for Reactor Bldg Discovered Reading Low & Declared Inoperable.Maint Work Request Initiated to Determine Cause
/03L-0:on 821006,controlled Leakage Exceeded Tech Specs During Surveillance Test Procedure.Caused by Improperly Set Needle Valves Located in Reactor Coolant Pump Seal Injection Line.Valves Positioned Correctly
/03L-0:on 821008,during Surveillance Test Procedure 303.006,pressure Bistable Failed to Change Output State.Caused by Failure of Printed Circuit Logic Card.Card Replaced & Test Procedure Performed Satisfactorily
/03L-0:on 821010,during Initial Startup in Mode 3, Pressurizer PORV Block Valve Mvg 8000C in RCS Found Leaking in Open Position.Caused by Worn Valve Packing.Packing Replaced.Valve Tested & Returned to Operable Status
/03L-0:on 821011,reactor Bldg Base Mat Seismic Monitoring Instrument IYA-1780 Tested Unsatisfactorily. Caused by Battery Charger Failure Resulting in Battery Discharge.Battery Replaced & Surveillance Performed
/03L-0:on 821011,steam Line Pressure Dropped Below Tech Spec Min.Caused by Safety Valve 2806P Inadvertently Lifting After Being Freed from stuck-closed Position.Valve & Power Range Neutron Flux High Setpoint Reset
/03L-0:on 821012,circuit Breaker for Reactor Bldg Cooling Unit Fan XFN-62B Discovered Open & in Discharged Position.Cause Undetermined.All 480-volt Safeguard Switchgear Checked.Procedures Revised to Verify Position
/03L-0:on 821014,while in Mode 3,B Train Control Room Ventilation Sys Declared Inoperable for Maint Due to Failure of Pressure Regulator for Damper Actuator.Caused by Ruptured Regulator Diaphragm.Diaphragm Replaced
/03L-0:on 821018,plant Went Into Mode 4 W/O Performing Surveillance Test Procedure 114.002, Operational Leak Test. Caused by Procedural Inadequacies.Procedure Revised to Comply W/Tech Spec Requirements
/03L-0:on 821020,during Performance of Surveillance Test Procedure,Porv PCV-445A Found Leaking. Caused by Degraded Seat/Disk Interface Due to Steam Impingement.Valves Will Be Repaired