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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20079B8591991-06-10010 June 1991
Interim Deviation/Noncompliance Rept 067 Re dry-type Insulator Cracking in Transformer Supplied by Westinghouse.Initially Reported on 910513.Util Notified Vendor on 910430 That Problem Affects Class 1E Transformer
ML20245B8701989-04-21021 April 1989
Deficiency & Part 21 Rept Re Degradation of Nonmetallic Components & Sludge Formation in Lubricating Oil.Initially Reported on 890327.Degradation of Nonmetallic Parts & Fouled Bearings Evaluated
ML20236P0061987-11-13013 November 1987
Final Part 21 & Deficiency Rept Re Failure of LPSI Pump When Energized.Initially Reported on 840523.Results of C-E Analytical & Test Program Showed That Excessive Shaft Deflection Eliminated by Use of Larger Diameter Motor Shaft
ML20214M6471987-05-27027 May 1987
Final Deficiency Rept NY-QA-8 Re Atwood & Morrill Natural Frequency ASME III Active Valves,Identified During Ebasco Engineering Review.Initially Reported on 870515.Valves Will Be Reanalyzed & Modified.Not Reportable Per 10CFR50.55(e)
ML20214E4681987-05-15015 May 1987
Deficiency Rept Re Natural Frequency of ASME III Active Valves.Initially Reported on 870413.Interim/final Rept Will Be Submitted by 870527
ML20207F1031986-12-18018 December 1986
Final Deficiency Rept Re Four Elgar Corp Static Uninterruptible Power Supply Units That Could Potentially Result in Failure of Class 1E 120-volt Vital Ac Bus. Condition Not Reportable Per 10CFR50.55(e)
ML20214W7711986-11-26026 November 1986
Interim Deficiency Rept Re Uninterruptible Power Supply Assembly Deficiencies.Initially Reported on 860708. Final Rept Will Be Provided by 870116
ML20215G5351986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20215G6801986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20212N1371986-08-25025 August 1986
Part 21 Rept Re Potentially Defective Operation of Synchro-Start Products,Inc Synchronizing Speed Switches Used in Auxiliary Generating Equipment.Initally Reported on 860820.Next Rept Will Be Submitted by 860926
ML20205G0201986-08-0808 August 1986
Interim Deficiency Rept 64 Re Uninterruptible Power Supply Assembly Defects.Initially Reported on 860708.Cracked or Stressed Fuse Blocks Will Be Replaced by Nov 1986.Final Rept Anticipated by 861201
ML20202H2271986-03-26026 March 1986
Part 21 & Final Deficiency Rept D/N 62 Re Potential Overspeed Trip in Diesel Generators Mfg by Colt Industries. Initially Reported on 860224.Vendor Forwarded Proposed Mods Whereby Air Will Be Positively Vented After Engine Started
ML20151Y8141986-02-0404 February 1986
Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder
ML20137J4601985-12-27027 December 1985
Interim Deficiency Rept Re Rejectable Suction Nozzle Weld Defect on Ingersoll-Rand HPSI Pump.Initially Reported on 851127.C-E Performing Technical Review of Defect.Final Rept Will Be Submitted Upon Receipt of C-E Review Results
ML20133E1111985-09-27027 September 1985
Final Part 21 & Deficiency Rept D/N 59 Re Possible Fractured or Cracked Welds on Louis Allis Emergency Standby Generators.Initially Reported on 850624.Item Not Reportable Per 10CFR50.55(e)
ML20209H8381985-09-0404 September 1985
Final Part 21 & Deficiency Rept 58 Re Titus Products Tension Wires.Initially Reported on 850311.Tension Wires Replaced & Air push-on Locknuts Installed to Secure Wires to Shafts of Air Deflection Blades
ML20133P1611985-07-24024 July 1985
Interim Part 21 & Deficiency Rept D/N 59 Re Cracked Welds on Diesel Generator Air Deflectors Supplied by Louis-Allis Co. Initially Reported on 850624.Corrective Actions Not Received from Vendor.Next Rept Expected by 850927
ML20128K1911985-07-0101 July 1985
Deficiency Rept D/N 52 Re LPSI Pump Failures.Pump Evaluation Necessary for Final Rept Not Yet Received.Final Rept to Be Provided as Soon as Info Received
ML20115J9201985-04-0101 April 1985
Final Deficiency Rept Re Brown Boveri Voltage Balance Relays W/Excessive Operating Time.Initially Reported on 850227. Relays Removed from Control Panels & Returned to Vendor for Replacements.Item Not Reportable Per 10CFR50.55(e)
ML20115D0491985-03-29029 March 1985
Interim Deficiency Rept (D/N 58) Re Titus Model 272 Grille Tension Wire Failing to Remain in Place.Initially Reported on 850311.Existing Tension Wires Will Be Replaced
ML20112E6631985-03-0707 March 1985
Interim Deficiency Rept Re Failure of Borg-Warner 2-inch HPSI Header Isolation Valves.Initially Reported on 850204. Opening Torque Switch Light Bypassed & Valve Yoke Tack Welded to Valve Body
ML20113A5381984-12-27027 December 1984
Final Part 21 & Deficiency Rept Re Damaged Wires on Westinghouse Ds/Dsl Circuit Breakers.Initially Reported on 841012.Damaged Wires Will Be Replaced & Addl Wire Ties Installed
ML20101B1571984-12-0303 December 1984
Corrected Final Deficiency Rept (D/N 55) Re Foxboro N-2AC Module Fuse Pin Damage.Fabrication Dates for Defective Modules Should Be May 1981 - Jul 1982
ML20100F9111984-11-21021 November 1984
Final Deficiency Rept (D/N 55) Re Foxboro N-2AC Module Fuse Pin Damage.Initially Reported on 841026.Defective Modules Will Be Replaced Prior to Startup
ML20100H5991984-11-16016 November 1984
Deficiency Rept (D/N 54) Re Defective Westinghouse Ds/Dsl Circuit Breakers.Field Insp of All Applicable Class 1E Circuit Breakers in Progress to Determine Extent of Problem. Next Rept Will Be Submitted by 841228
ML20099H1961984-11-13013 November 1984
Part 21 & Final Deficiency Rept (D/N 53) Re Rockbestos Cable Insulation Damage.Initially Reported on 841012.Four Installed Cables Having Reworked Areas Will Be Identified & Either Removed or Abandoned
ML20099F4911984-11-0606 November 1984
Interim Deficiency Rept D/N 51 Re Potential Defect in Reactor Coolant Pump.Initially Reported on 830927.Final Rept Will Be Submitted Upon Receipt of C-E Specific Repair Program
ML20094Q8041984-08-0707 August 1984
Part 21 Rept Re Tension Wires on Titus Grille,Model 272, Not Remaining in Place When Deflection Blades Closed. Affected Job Sites Identified in Encl.Products Being Tested Provide Acceptable Fix for Retention
ML20094Q8281984-08-0707 August 1984
Part 21 Rept Re Failure of Tension Wires Used for Adjustment of Blades on Grille Model 272.Testing to Identify Rework Methods to Be Utilized in Progress
ML20092M7991984-06-22022 June 1984
Interim Deficiency Rept D/N 52 Re LPSI Pump Failures. Initially Reported on 840523.Corrective Action Will Be Proposed Upon Completion of Investigation.Final Rept Will Be Provided by 850630
ML17325B6701984-06-20020 June 1984
Final Deficiency Rept (D/N#49) Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Initially Reported on 830624.Total of 1,442 Beam Assemblies Examined,Including 3,318 Coped Corners.All Physical Repair Activities Completed
ML20197H1741984-06-0404 June 1984
Interim Deficiency Rept Re C-E Sys 80 Reactor Coolant Pump Hydraulic Defect.Initially Reported on 830927.Design Problems Identified & Corrected.Next Rept Will Be Submitted by 841101
ML20080G5361984-01-31031 January 1984
Interim Deficiency Rept D/N 49 Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Cb&I Will Complete Investigation & Forwards Results to Ebasco by Apr 1984.Final Rept Expected by 840615
ML20083B6811983-12-0606 December 1983
Final Deficiency Rept Re Main Steam & Feedwater Penetration Anchors.Initially Reported on 830426.No Addl Deficiencies Found.Ebasco Procedures Revised
ML20082E6451983-11-0808 November 1983
Interim Deficiency Rept D/N 49 Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Initially Reported on 830722.Similar Deficiencies May Have Occurred in Jet Impingement Barrier Matls.Final Rept Will Be Submitted by 840215
ML20082E3611983-10-31031 October 1983
Interim Deficiency Rept 51 Re Reactor Coolant Pump Defect. Initially Reported on 830927.Cause Under Investigation. Existing Design Will Be Retested W/Addl Instrumentation. Final Rept Will Be Provided by 840601
ML20076L5951983-09-0202 September 1983
Final Deficiency Rept 50 Re Cracked Weld & Loose Parts in C-E Steam Generators.Initially Reported on 830801.Documented Missing,Damaged or Defective Parts & Loose Parts Tightened
ML20080D3261983-08-17017 August 1983
Interim Deficiency Rept NY-QA-5 Re Main Steam & Feedwater Penetration Anchors.Addl Time Required to Complete Comprehensive Evaluation.Final Rept Submittal Anticipated by 831205
ML20077Q5131983-08-0101 August 1983
Interim Deficiency Rept NY-QA-5 Re Main Steam & Feedwater Penetration Anchors.Initially Reported on 830609.Pipe Rupture Analysis & Seismic Analyses Conducted.Final Rept Expected by 830915
ML20024D1711983-07-22022 July 1983
Interim Deficiency Rept Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Initially Reported on 830624.Cause & Extent of Burn Cuts & Nonconforming Weld Problem Investigated.Final Rept Scheduled for 840215
ML20024A4381983-06-0909 June 1983
Interim Deficiency Rept NY-QA-5 Re Main Steam & Feedwater Penetration Anchor Stress Analyses.Initially Reported on 830426.Engineering Procedure Revised & Analyses Performed. Final Rept Expected by 830729
ML20069M4371983-04-20020 April 1983
Final Deficiency Rept Re Rockbestos Insulated Cable Type D60-1.Initially Reported on 821203.Dented Cable to Be Reworked to Restore Cable to Original Specified Thickness. Deficiency Determined Not Reportable Under 10CFR50.55(e)
ML20074A7571983-04-0606 April 1983
Supplemental Final Deficiency Rept Re Safety Injection Tank safe-end Indications (D/N 23).Safe-end-to-nozzle-welds for Injection Tanks Reradiographed,Approved & Accepted Per Spec & ASME Code Requirements
ML20072R0151983-03-25025 March 1983
Part 21 Rept Re Deviation in Quality of Shielded Instrumentation Cables.Initially Reported on 820412.Problem Determined Not to Be Reportable Per Part 21
ML20069E6951983-03-14014 March 1983
Final Deficiency Rept Re Failure of Structural Welds to Meet Aws Min Weld Size Requirements.Initially Reported on 821124. Condition Not Reportable Per 10CFR50.55(e) Based on Satisfactory Completion of Qualification Testing
ML20071D3671983-03-0202 March 1983
Final Deficiency Rept Re Safety Injection Tank safe-end Indications (D/N 23).All Linear Indications Found in safe-end-to-nozzle Welds of Safety Injection Tanks 3 & 4 Removed & Rewelded Per ASME Section XI Plan
ML20071D7141983-03-0202 March 1983
Final Deficiency Rept Re Safety Injection Tanks - safe-end Indications.All Linear Indications in safe-end-to-nozzle- Welds in Safety Injection Tanks 3 & 4 Removed & Rewelded Per ASME Section XI Plan.Final Radiographs Verified Repairs
ML20065B5841983-02-11011 February 1983
Final Deficiency Rept D/N 44 Re Compressible Matl - Embedded Containment Penetrations.Initially Reported on 820921.Load Case Test Results Confirm Subj Deficiency Not Reportable Per 10CFR50.55(e)
ML20065B5071983-02-0808 February 1983
Final Deficiency Rept D/N 46 Re Diffuser Retaining Cap Screws on Reactor Coolant Pumps.Initially Reported on 821105.Cap Screw Matl Heat Treatment Changed So Matl Not Susceptible to Hydrogen Corrosion Cracking
ML20070V9801983-02-0808 February 1983
Final Deficiency Rept Re Failed Diffuser Retaining Cap Screws to Sys 80 Reactor Coolant Pumps.Cap Screw Matl Heat Treatment Will Be Changed to Prevent Hydrogen Embrittlement/ Stress Corrosion Cracking.Not Reportable Per 10CFR50.55(e)
1991-06-10
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Category:TEXT-SAFETY REPORT
MONTHYEARML20202C8081999-01-22022 January 1999
Safety Evaluation Supporting Order Terminating Construction Permit CPPR-154
ML17292B4791998-12-31031 December 1998
Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr
ML17292B2121997-12-31031 December 1997
Washington Public Power Supply Sys Annual Rept for 1997. W/980108 Ltr
ML17292A6361996-12-31031 December 1996
Washington Public Power Supply Sys Annual Rept for 1996. W/961212 Ltr
ML17291B1501995-12-31031 December 1995
Washington Public Power Supply Sys Annual Rept 1995. W/ 951201 Ltr
ML17291A6761994-12-31031 December 1994
Washington Public Power Supply Sys 1994 Annual Rept. W/ 950302 Ltr
ML17290A9581993-12-31031 December 1993
Washington Public Power Supply Sys Annual Rept,1993. W/940209 Ltr
ML17289B1231992-12-31031 December 1992
Washington Public Power Supply Sys 1992 Annual Rept. W/930119 Ltr
ML17289A2761991-12-31031 December 1991
Washington Public Power Supply Sys 1991 Annual Rept. W/ 920128 Ltr
ML17286B2761991-07-31031 July 1991
Rev 0 to Washington Nuclear Plant 3 Seismic Design Basis Model Validation,Soil Variation Studies.
ML20079B8591991-06-10010 June 1991
Interim Deviation/Noncompliance Rept 067 Re dry-type Insulator Cracking in Transformer Supplied by Westinghouse.Initially Reported on 910513.Util Notified Vendor on 910430 That Problem Affects Class 1E Transformer
ML17286B2681991-05-0707 May 1991
Justification for Revised Tornado Design Criteria.
ML17286A5541990-12-31031 December 1990
WPPSS,1990 Annual Financial Rept. W/910115 Ltr
ML17285A9891989-12-31031 December 1989
WPPSS,1989 Annual Rept. W/900129 Ltr
ML20245B8701989-04-21021 April 1989
Deficiency & Part 21 Rept Re Degradation of Nonmetallic Components & Sludge Formation in Lubricating Oil.Initially Reported on 890327.Degradation of Nonmetallic Parts & Fouled Bearings Evaluated
ML20154D3231988-05-16016 May 1988
Safety Evaluation Supporting Util 841102 & 860310 Requests for Extension of Plant Const Completion Date from 850101 to 990701
ML20147D3921988-02-29029 February 1988
Seismic Hazards Assessment for Washington Nuclear Plant-3, Satsop,Wa Contract C-20453, Final Rept
ML17279A7641987-12-31031 December 1987
WPPSS,1987 Annual Rept. W/880108 Ltr
ML20236P0061987-11-13013 November 1987
Final Part 21 & Deficiency Rept Re Failure of LPSI Pump When Energized.Initially Reported on 840523.Results of C-E Analytical & Test Program Showed That Excessive Shaft Deflection Eliminated by Use of Larger Diameter Motor Shaft
ML20215C3061987-06-11011 June 1987
Safety Evaluation Supporting Application of Modified Itt/ Grinnell Stiff Clamps for Use in safety-related Piping Sys
ML20214M6471987-05-27027 May 1987
Final Deficiency Rept NY-QA-8 Re Atwood & Morrill Natural Frequency ASME III Active Valves,Identified During Ebasco Engineering Review.Initially Reported on 870515.Valves Will Be Reanalyzed & Modified.Not Reportable Per 10CFR50.55(e)
ML20214E4681987-05-15015 May 1987
Deficiency Rept Re Natural Frequency of ASME III Active Valves.Initially Reported on 870413.Interim/final Rept Will Be Submitted by 870527
ML17278B1731986-12-31031 December 1986
Wppss Annual Rept 1986.
ML20207F1031986-12-18018 December 1986
Final Deficiency Rept Re Four Elgar Corp Static Uninterruptible Power Supply Units That Could Potentially Result in Failure of Class 1E 120-volt Vital Ac Bus. Condition Not Reportable Per 10CFR50.55(e)
ML20214W7711986-11-26026 November 1986
Interim Deficiency Rept Re Uninterruptible Power Supply Assembly Deficiencies.Initially Reported on 860708. Final Rept Will Be Provided by 870116
ML20215G5351986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20215G6801986-10-10010 October 1986
Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing
ML20211A8421986-09-0808 September 1986
Final Rept of Earthwork Module C3-01 of Facility Const Assurance Program of Facility Readiness Review Program
ML20212N1371986-08-25025 August 1986
Part 21 Rept Re Potentially Defective Operation of Synchro-Start Products,Inc Synchronizing Speed Switches Used in Auxiliary Generating Equipment.Initally Reported on 860820.Next Rept Will Be Submitted by 860926
ML20205G0201986-08-0808 August 1986
Interim Deficiency Rept 64 Re Uninterruptible Power Supply Assembly Defects.Initially Reported on 860708.Cracked or Stressed Fuse Blocks Will Be Replaced by Nov 1986.Final Rept Anticipated by 861201
ML20203E6321986-06-30030 June 1986
Validation of Ebasco Foundation Spring Modeling for Elastic Half-Space Seismic Model
ML20198N5431986-05-31031 May 1986
Addendum to CEN-315 Summary of Diversity Between Reactor Trip Sys & Auxiliary Feedwater Actuation Sys for C-E Plants
ML20202H2271986-03-26026 March 1986
Part 21 & Final Deficiency Rept D/N 62 Re Potential Overspeed Trip in Diesel Generators Mfg by Colt Industries. Initially Reported on 860224.Vendor Forwarded Proposed Mods Whereby Air Will Be Positively Vented After Engine Started
ML20140A7621986-02-28028 February 1986
Informs of Plans for Implementing Severe Accident Policy Statement & Regulatory Use of New source-term Info
ML20151Y8141986-02-0404 February 1986
Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder
ML17278A6141985-12-31031 December 1985
Wppss 1985 Annual Rept. W/860225 Ltr
ML20137J4601985-12-27027 December 1985
Interim Deficiency Rept Re Rejectable Suction Nozzle Weld Defect on Ingersoll-Rand HPSI Pump.Initially Reported on 851127.C-E Performing Technical Review of Defect.Final Rept Will Be Submitted Upon Receipt of C-E Review Results
ML20138D7281985-11-30030 November 1985
Draft SER Re Status of Staff Review of FSAR & Associated Submittals Until Const Delay Announced in 1983
ML20133E1111985-09-27027 September 1985
Final Part 21 & Deficiency Rept D/N 59 Re Possible Fractured or Cracked Welds on Louis Allis Emergency Standby Generators.Initially Reported on 850624.Item Not Reportable Per 10CFR50.55(e)
ML20209H8381985-09-0404 September 1985
Final Part 21 & Deficiency Rept 58 Re Titus Products Tension Wires.Initially Reported on 850311.Tension Wires Replaced & Air push-on Locknuts Installed to Secure Wires to Shafts of Air Deflection Blades
ML20132H0331985-07-31031 July 1985
Rev 1 to Evaluation of Itt/Grinnel Figure 215 Stiff Clamp Application on Safety-Related Piping Sys
ML20133P1611985-07-24024 July 1985
Interim Part 21 & Deficiency Rept D/N 59 Re Cracked Welds on Diesel Generator Air Deflectors Supplied by Louis-Allis Co. Initially Reported on 850624.Corrective Actions Not Received from Vendor.Next Rept Expected by 850927
ML20128K1911985-07-0101 July 1985
Deficiency Rept D/N 52 Re LPSI Pump Failures.Pump Evaluation Necessary for Final Rept Not Yet Received.Final Rept to Be Provided as Soon as Info Received
ML20115J9201985-04-0101 April 1985
Final Deficiency Rept Re Brown Boveri Voltage Balance Relays W/Excessive Operating Time.Initially Reported on 850227. Relays Removed from Control Panels & Returned to Vendor for Replacements.Item Not Reportable Per 10CFR50.55(e)
ML20115D0491985-03-29029 March 1985
Interim Deficiency Rept (D/N 58) Re Titus Model 272 Grille Tension Wire Failing to Remain in Place.Initially Reported on 850311.Existing Tension Wires Will Be Replaced
ML20112E6631985-03-0707 March 1985
Interim Deficiency Rept Re Failure of Borg-Warner 2-inch HPSI Header Isolation Valves.Initially Reported on 850204. Opening Torque Switch Light Bypassed & Valve Yoke Tack Welded to Valve Body
ML20129A0631985-02-20020 February 1985
Rev 2 to Preservation of Assets Preventative Program
ML17277B6301984-12-31031 December 1984
1984 Annual Rept. W/850222 Ltr
ML20113A5381984-12-27027 December 1984
Final Part 21 & Deficiency Rept Re Damaged Wires on Westinghouse Ds/Dsl Circuit Breakers.Initially Reported on 841012.Damaged Wires Will Be Replaced & Addl Wire Ties Installed
ML20101B1571984-12-0303 December 1984
Corrected Final Deficiency Rept (D/N 55) Re Foxboro N-2AC Module Fuse Pin Damage.Fabrication Dates for Defective Modules Should Be May 1981 - Jul 1982
1999-01-22
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Text
ACCELERATEDDOCUMENTDISTRIBUTIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)-ACCESSIONNBR:9406290336DOC.DATE:94/06/21NOTARIZED:YESDOCKETFACIE:50-315DonaldC.CookNuclearPower,Plant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana-M05000316AUTH.NAMEAUTHORAFFILIATIONFITPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAME-RECIPIENTAFFILIATIONRDocumentControlBranch(DocumentControlDesk)I
SUBJECT:
SubmitsresponsetoviolationsnotedinInspRepts50-315/94-07&50-316/94-07.Correctiveactions:sealleakoffDproblemsledtoraisingCCWtempcorrectedduringUnit11994refuelingoutage.SDISTRIBUTIONCODE:IE01DCOPIESRECEIVED:LTRENCLSIZE:TITLE:General(50Dkt)-InspRept/NoticeofViolationResponse/NOTES:RECIPIENTIDCODE/NAMEPD3-1PDCOPIESRECIPIENTLTTRENCL'DCODE/NAME11HICKMAN,JCOPIESLTTRENCL11DDINTERNAL:AEOD/DEIBAEOD/DSP/TPABDEDRONRR/DRCH/HHFBCg~F'xr,z02EXTERNALEG&G/BRYCEiJAHNSIC111'1111111111111111AEOD/DSP/ROABAEOD/TTCNRR/DORS/OEABNRR/PMAS/ILPB1NUDOCS-ABSTRACTOGC/HDS2RES/HFBNRCPDR1111111111111111DDNOTETOALL"RIDS"RECIPIENTSPI'""'LPUSTOREDUCEWASTE!CQNTACI'THEDOCUMENTCONTROLDESK,ROOMPi-s7(EXT.504-2065)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR20ENCL20 indianaMichiganPowerCompanyP.O.Box16631Columbus,OH43216INDIANA'ICHIGANPolVkRAEP:NRC:1212DDonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74NRCINSPECTIONREPORTNOS.50-315/94007(DRS);50-316/94007(DRS)REPLYTONOTICEOFVIOLATIONU.S.NuclearRegulatoryCommission'ocumentControlDeskWashington,D.C.20555Attn:Mr.J.B,MartinJune21,1994
DearMr.Martin:
ThisletterisinresponsetoaUSNRCletterdatedMay27,1994,thatforwardedanoticeofviolationtoIndianaMichiganPowerCompany.ThenoticeofviolationcontainedaviolationidentifiedduringaninspectionconductedbyMessrs.K.SalehiandC.GillfromApril11throughApril22,1994.TheviolationisassociatedwiththeoperatingtemperatureoftheComponentCoolingWater(CCW)system,Ourreplytothenoticeofviolationisprovidedintheattachmenttothisletter.Thisletterissubmittedpursuantto10CFR50.54(f)and,assuch,anoathstatementisattached.Sincerely,EF~p~)E.E.FitzpatrickVicePresidentdrAttachmentcc:A.A.BlindG.CharnoffW.T.Russell,NRC-Washington,D.C.NRCResidentInspectorNFEMSectionChiefJ.R.PadgettF~8~9P0b29033b9<0b>>PDRADOGK050003158PDRpalI STATEOFOHIO)COUNTYOFFRANKLIN)E.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingResponsetoNRCINSPECTIONREPORTNOS.50-315/94007(DRS);50-316/94007(DRS)REPLYTONOTICEOFVIOLATIONandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief..)IS/SubscribedandsworntobeforemethisdayofNOTARPUBLI,+~~>S'zrc~
ATTACHMENTTOAEP:NRC:1212DREPLYTONOTICEOFVIOLATION ATTACHMENTTOAEP'NRC:1212DPage1BackgroundAroutinesafetyinspectionwasconductedbyMessrs.C.GillandK.SalehifromAprilllthroughApril22,1994.Theinspectionwastodetermineifdesign'hanges,engineeringsupport,andcorrectiveactionswereeffectivelycontrolledandimplemented.Theinspectionidentifiedoneviolation.Theviolationwasforfailuretoperformarequire'dsafetyevaluationofaproposedchangeinthefacility,asdescribedintheUpdatedFinalSafetyAnalysisReport(UFSAR),toascertainwhethertheproposedchangeinvolvedanunreviewedsafetyquestion.TheviolationisthattheUFSARtemperatureof95'FfortheComponentCoolingWater(CCW)supplywasauthorizedtobeincreasedto105FforUnit1bytheOperationsDepartmentSuperintendentwithoutarequfredsafetyevaluatfonandwithout/',arevisiontotheCCWoperatingprocedure,whichspecifieda95Flimitation.Subsequently,theCCWsupplytemperatureincreasedto110FduringatransientinducedbyintermittentboricacidevaporatoroperationonJanuary27and28,1994.AcontributingfactorstoexceedingCCWspecifiedsupplytemperaturewasthefailureoftheoperationsdepartmenttoresettheCCWsupply(heatexchangeroutlet)temperaturealarmsetpointfrom95Fto105F.ThisviolationwassetforthinalettercontainingthenoticeofviolationdatedMay27,1994,fromMr.MarkA.Ring,Chief,OperationsBranch.TheletterwasreceivedJune6,1994.Ourresponsetothenoticeofviolationiscontainedwithinthisdocument.NRCViolation"10CFR50.59requires,inpart,thatchangesmadetothefacilityasdescribedinthesafetyanalysisreport,beevaluatedinaccordancewith50.59(a)todetermine,inpart,ifanunreviewedsafetyquestionexists.Section9.5.3oftheD.C.CookNuclearPlantUpdatedSafetyAnalysisReport(USAR)statesthattheComponentCoolingWater(CCW)systemcomponentdesigndataarelistedinTable9.5-3.Table9.5-3statesthattheshellsideCCWheatexchangeroutletdesignwatertemperatureis95F.Contrarytotheabove,theUnit1CCWheatexchangeroutletwatertemperatureasdescribedinTable9.5-3oftheUSARwasauthorizedtobeexceeded,andwasactuallyexceeded,onJanuary27,1994,withouttherequiredevaluationtodetermineifanunreviewedsafetyquestionexisted.Specifically,theOperationsDepartmentSuperintendentauthorizedincreasingthetemperaturelimitto105'Fat1915hoursonJanuary27,1994,andsubsequently,theoperatorincreasedthetemperatureabove95'F.Thetemperaturewasallowedtoincreaseto110F.eThisisaSeverityLevelIVviolation(SupplementI)."
ATTACHMENTTOAEP:NRC:1212DPage2ResponsetoViolationInthecoverlettertothenoticeofviolationtheNRCrequestedthatweaddressinourresponsethesafetysignificanceoftheevent,theidentifiedconcernsandcontributingfactors,andtheconclusionsofanongoingrootcauseteaminvestigation.Thefollowingprovidestherequestedinformation:SafetySignificanceTheoperationat105FwithsubsequentCCWsupplytemperaturesashighas110'FbecauseofatransientinducedbyintermittentboricacidevaporatoroperationonJanuary27and28,1994wasofnosafetysignificance.ThemaximumComponentCoolingWater(CCW)temperaturefortheDonaldC.CookNuclearPlantsUnit1and2is120'FforWestinghousesuppliedequipment.ThereactorcoolantpumpthermalbarriersarethelimitingcomponentfortheCCWmaximumtemperature,andthelimitingmodesofoperationoccurduringtheplantcooldownorpost-LOCA.TheotherWestinghousesuppliedcomponentshavelimitsgreaterthan120F.ConcernsandContributingfactorsThereweretwoconcernsandtwocontributingfactorsidentifiedintheNRCcoverletter.Theconcernsare:1)theauthorizationbytheOperationsDepartmentSuperintendenttoincreasedCCWtemperaturefromthe95'Fto105FwithoutarequiredsafetyevaluationandwithoutarevisiontotheCCW'operatingprocedure;and'2)thesubsequentCCWsupplytemperatureincreasedto110Fduringatransientinducedbyintermittentboricacidevaporatoroperation.ThetwocontributingfactorsidentifiedintheNRCcoverletterare:1)inadequatecommunicationsbetweentheCCWsystemengineerandtheoperationsdepartment;and2)failureoftheoperationsdepartmenttoresettheCCWsupplytemperaturealarmsetpoint,from95Fto105oFTheOperationsDepartmentSuperintendentauthorizationtoincreaseCCWtemperatureabovethetemperatureof95'FwasmadeinresponsetoanRCPsealleakoffconcernandwasnotbasedondirectionreceivedthroughaformalprocess.Theauthorizationdidnotresultinanunsafecondition;however,itwasnotwithintheestablishedplantcontrolsforperformanceofsuchan,activity.TheNRCstatesthecontributingfactortothiscanbeattributedtoinadequatecommunications.TheOperationsDepartment,theSystemEngineerandtheColumbusEngineeringstaffdiscussedtheabilityof=thesystemtooperateatahighertemperature,howevernoneofthepartiesrecognizedtheneedforasafetyreview,beforeallowingtheCCWsystemtobeoperatedabove95'F.Thisissuewillbeaddressedthroughthedevelopmentofaninstructiontoestablishcontrolsontechnicalguidance.
ATTACHMENTTOAEP:NRC:1212DPage3TheCCWsupplytemperatureincreaseto110'Fduringa.transientinducedbyintermittentboricacidevaporatoroperationresultedfromthefailureoftheproceduregoverningtheactionsrequiredforblockedalarmstoaddressasituationwhereconditionswhichcauseastandingHigh/Lowalarmareintentionallycreated.Theguidanceforblockedalarmswillberevisedtocoversuchconditions.ConclusionsofRootCauseTeamInvestigationAsreferencedinsection2.3ofinspectionreport50-315/94007(DRS);50-316/94007(DRS}ConditionReportNo.94-0779wasinitiatedtoinvestigatetheconcernsandtakecorrectiveactionsasneededbasedonunresolveditem315/94002-12(DRP).TheinvestigationwasnotconfinedtothespecificCCWconcernsbutincludedrelativerelatedeventsbeginningwiththeSeptember1993RCP-14loweroilpotannunciatoralarm.Therootcauseinvestigationwasconductedbyamulti-disciplinaryteamandlookedgenerically'atthecontrolroomcommandandcontrolprocessandtheuseofengineeringjudgementinmakingunitoperationaldecisions.Theconclusionsoftherootcauseteaminvestigationareasfollows:-AsaresultoftheeventstwoOperatingPhilosophyandPractices(OPP)wererevised.OPP~1,ControlBoardMonitoringDuringNon-EmergencyOperationalConditions,wasrevisedand.becameeffectiveMay16,1994.Thedocumentspecificallyrequiresthatwhencontrollingprocessesinmanual,theUnitSupervisorwillspecifytherangeatwhichthevariableshouldbecontrolled.Theentirecontrolroomteamshouldbeawareofthevalues.Changestothecontrolrangewillbeannouncedtotheteam.The,standardalsostatesthatthecontrolroomteamwillmonitorapplicableparametersonanincreasedfrequencywhenaprocesscontrollerisinmanual.TheUnitSupervisorwillspecifyparameterstobemonitoredandthefrequencyatwhichtheparametersaretobemonitored.FinallythestandardrequirestheUnitSupervisorto'beinformedwhenoffnormaltrendsorconditionsareidentified.ThesecondOperatingPhilosophyandPracticestoberevisedwasOPP.7,AnnunciatorResponse.ThisOPPwasrevisedandbecameeffectiveMay25,1994.ThedocumentdirectsthatanysignificantunexpectedalarmsaretobeloggedinthecontrolroomlogasdeterminedbytheUnitSupervisor,andthatannunciatorresponseproceduresaretobeconsultedtoverify,thatautomaticactionsoccurredasexpectedandtocheckforapplicablenecessarysubsequentactions.
ATTACHMENTTOAEP:NRC:1212DPage4Intheareaofengineeringjudgement,theinvestigationconcludedthattheengineeringjudgementappliedthroughouttheperiodincludedmanagementreviewandapprovalandprovedtobeaccuratebasedonthesubsequentevaluationandmaintenanceofRCP-,14duringtherefuelingoutage.Itwas'oncludedbasedontheCCW'eventthatamechanismwasrequiredtocontrolactivitiesthataffectqualityasisnotedinthecorrectiveactionstakentoavoidfurtherviolations.TheresponsetotheNoticeofViolationisasfollows:l.AdmssionorDenialotheAlleedViolatioIndianaMichiganPoweradmitstotheviolationascitedintheNRC.,NoticeofViolation.ReasonsfoteVoatioTherootcauseforthiseventwastheuseofaninformalprocesstoobtaintechnicalguidanceonincreasingComponentCoolingWater(CCW}temperaturetomitigateexcessiveRCPsealleakoff.ThisresultedinthefailureoftheeffortstodevelopastrategyfordealingwithincreasedRCPsealleakoffwhichincludedallofthenecessaryactionstoincreaseCCWtemperature.Theoperationsdepartmentshould'havebeenawarethatalthoughengineeringjudgementindicatedthat105FCCWsupplywaterwouldnotsignificantlydamagetheCCWsystemortheequipmentitcooled,thistemperaturewasbeyondthesourcedocumenttemperatureof95'F.3.CorrectiveActionsTakenandResultsAchievedOnFebruary13,1994theComponentCoolingWater(CCW)temperaturewasrestoredbelow95F.ThesealleakoffproblemswhichledtoraisingtheCCWtemperaturewerecorrectedduringtheUnit11994refuelingoutage.4.CorrectiveetiosTakentoAvoidFurtherVoatiosInterimandlongterminstructionswillbedevelopedonacceptablemethodstoobtaintechnicaldirectionforactivitiesaffectingqualitywherethedirectionisnotderivedfromapprovedsourcedocuments.Theinteriminstructionwillbeinplaceby7/29/94.Thelongterminstructionwillbeinplaceby12/30/94.
ATTACHMENTTOAEP:NRC:1212DPage55,DateWhenFullComliancewilbeAchievedFull'compliancewasachievedonFebruary13,1994whentheComponentCoolingWatertemperaturewasrestoredtoaconditionbelow95F'.