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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
[Table view] 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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ACCELERATED DOCUMENT DISTRIBUTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)-
ACCESSION NBR:9406290336 DOC.DATE: 94/06/21 NOTARIZED: YES DOCKET FACIE:50-315 Donald C. Cook Nuclear Power, Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana- M 05000316 AUTH. NAME AUTHOR AFFILIATION FITPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele R RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
I
SUBJECT:
Submits response to violations noted in Insp Repts 50-315/94-07 & 50-316/94-07.Corrective actions:seal leakoff D problems led to raising CCW temp corrected during Unit 1 1994 refueling outage.
S DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response /
NOTES:
RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 1 1
'D RECIPIENT CODE/NAME HICKMAN,J COPIES LTTR ENCL 1 1 D
D INTERNAL: AEOD/DEIB 1 1 AEOD/DSP/ROAB 1 1 AEOD/DSP/TPAB 1 '
AEOD/TTC 1 1 DEDRO 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/PMAS/ILPB1 1 1 1 1 NUDOCS-ABSTRACT 1 1 1 1 OGC/HDS2 1 1 Cg~F'xr,z 02 1 1 RES/HFB 1 1 1 1 EXTERNAL EG&G/BRYCEiJ AH 1 1 NRC PDR 1 1 NSIC 1 1 D
D NOTE TO ALL "RIDS" RECIPIENTS PI'" " 'LP US TO REDUCE WASTE! CQNTACI'THE DOCUMENT CONTROL DESK, ROOM Pi-s7 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 20
indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 INDIANA
'ICHIGAN PolVkR AEP:NRC:1212D Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NRC INSPECTION REPORT NOS. 50-315/94007 (DRS); 50-316/94007 (DRS)
REPLY TO NOTICE OF VIOLATION U. S. Nuclear Regulatory Commission Control Desk 'ocument Washington, D.C. 20555 Attn: Mr. J. B, Martin June 21, 1994
Dear Mr. Martin:
This letter is in response to a USNRC letter dated May 27, 1994, that forwarded a notice of violation to Indiana Michigan Power Company. The notice of violation contained a violation identified during an inspection conducted by Messrs. K. Salehi and C. Gill from April 11 through April 22, 1994. The violation is associated with the operating temperature of the Component Cooling Water (CCW) system, Our reply to the notice of violation is provided in the attachment to this letter.
This letter is submitted pursuant to 10 CFR 50.54(f) and, as such, an oath statement is attached.
Sincerely, EF~p~)
E. E. Fitzpatrick Vice President dr Attachment cc: A. A. Blind G. Charnoff W. T. Russell, NRC - Washington, D.C.
NRC Resident Inspector NFEM Section Chief J. R. Padgett F ~
8 ~
9P0b29033b 9<0b>>
PDR 8
ADOGK 05000315 PDR pal I
STATE OF OHIO)
COUNTY OF FRANKLIN)
E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing Response to NRC INSPECTION REPORT NOS. 50-315/94007 (DRS); 50-316/94007 (DRS)
REPLY TO NOTICE OF VIOLATION and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed and sworn to before me this .) IS/
day of NOTAR PUBLI,
+~~>S'zr c~
ATTACHMENT TO AEP:NRC:1212D REPLY TO NOTICE OF VIOLATION
ATTACHMENT TO AEP 'NRC: 1212D Page 1
Background
A routine safety inspection was conducted by Messrs. C. Gill and K. Salehi from ll April through April 22, 1994. The inspection was to determine if design'hanges, engineering support, and corrective actions were effectively controlled and implemented. The inspection identified one violation. The violation was for failure to perform a require'd safety evaluation of a proposed change in the facility, as described in the Updated Final Safety Analysis Report (UFSAR), to ascertain whether the proposed change involved an unreviewed safety question. The violation is that the UFSAR temperature of 95'F for the Component Cooling Water (CCW) supply was authorized to be increased to 105 F for Unit 1 by the Operations Department Superintendent without a requfred safety evaluatfon and without /',
a revision to the CCW operating procedure, which specified a 95 F limitation. Subsequently, the CCW supply temperature increased to 110 F during a transient induced by intermittent boric acid evaporator operation on January 27 and 28, 1994. A contributing factors to exceeding CCW specified supply temperature was the failure of the operations department to reset the CCW supply (heat exchanger outlet) temperature alarm setpoint from 95 F to 105 F.
This violation was set forth in a letter containing the notice of violation dated May 27, 1994, from Mr. Mark A. Ring, Chief, Operations Branch. The letter was received June 6, 1994. Our response to the notice of violation is contained within this document.
NRC Violation "10 CFR 50.59 requires, in part, that changes made to the facility as described in the safety analysis report, be evaluated in accordance with 50.59(a) to determine, in part, if an unreviewed safety question exists.
Section 9.5.3 of the D. C. Cook Nuclear Plant Updated Safety Analysis Report (USAR) states that the Component Cooling Water (CCW) system component design data are listed in Table 9.5-3.
Table 9.5-3 states that the shell side CCW heat exchanger outlet design water temperature is 95 F.
Contrary to the above, the Unit 1 CCW heat exchanger outlet water temperature as described in Table 9.5-3 of the USAR was authorized to be exceeded, and was actually exceeded, on January 27, 1994, without the required evaluation to determine question existed.
if an unreviewed safety Specifically, the Operations Department Superintendent authorized increasing the temperature limit to 105'F at 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> on January 27, 1994, and subsequently, the operator increased the temperature above 95'F. The temperature was allowed to increase to 110 F. e This is a Severity Level IV violation (Supplement I)."
ATTACHMENT TO AEP:NRC:1212D Page 2 Response to Violation In the cover letter to the notice of violation the NRC requested that we address in our response the safety significance of the event, the identified concerns and contributing factors, and the conclusions of an ongoing root cause team investigation. The following provides the requested information:
Safety Significance The operation at 105 F with subsequent CCW supply temperatures as high as 110'F because of a transient induced by intermittent boric acid evaporator operation on January 27 and 28, 1994 was of no safety s ignificance. The maximum Component Cooling Water (CCW) temperature for the Donald C. Cook Nuclear Plants Unit 1 and 2 is 120'F for Westinghouse supplied equipment. The reactor coolant pump thermal barriers are the limiting component for the CCW maximum temperature, and the limiting modes of operation occur during the plant cooldown or post-LOCA. The other Westinghouse supplied components have limits greater than 120 F.
Concerns and Contributing factors There were two concerns and two contributing factors identified in the NRC cover letter. The concerns are: 1) the authorization by the Operations Department Superintendent to increased CCW temperature from the 95'F to 105 F without a required safety evaluation and without a revision to the CCW 'operating procedure; and '2) the subsequent CCW supply temperature increased to 110 F during a transient induced by intermittent boric acid evaporator operation.
The two contributing factors identified in the NRC cover letter are:
- 1) inadequate communications between the CCW system engineer and the operations department; and 2) failure of the operations department to reset the CCW supply temperature alarm setpoint,from 95 F to 105oF The Operations Department Superintendent authorization to increase CCW temperature above the temperature of 95'F was made in response to an RCP seal leakoff concern and was not based on direction received through a formal process. The authorization did not result in an unsafe condition; however, it was not within the established plant controls for performance of such an, activity. The NRC states the contributing factor to this can be attributed to inadequate communications. The Operations Department, the System Engineer and the Columbus Engineering staff discussed the ability of= the system to operate at a higher temperature, however none of the parties recognized the need for a safety review, before allowing the CCW system to be operated above 95'F. This issue will be addressed through the development of an instruction to establish controls on technical guidance.
ATTACHMENT TO AEP:NRC:1212D Page 3 The CCW supply temperature increase to 110'F during a .transient induced by intermittent boric acid evaporator operation resulted from the failure of the procedure governing the actions required for blocked alarms to address a situation where conditions which cause a standing High/Low alarm are intentionally created. The guidance for blocked alarms will be revised to cover such conditions.
Conclusions of Root Cause Team Investigation As referenced in section 2.3 of inspection report 50-315/94007 (DRS); 50-316/94007 (DRS} Condition Report No. 94-0779 was initiated to investigate the concerns and take corrective actions as needed based on unresolved item 315/94002-12 (DRP). The investigation was not confined to the specific CCW concerns but included relative related events beginning with the September 1993 RCP-14 lower oil pot annunciator alarm.
The root cause investigation was conducted by a multi-disciplinary team and looked generically'at the control room command and control process and the use of engineering judgement in making unit operational decisions. The conclusions of the root cause team investigation are as follows:-
As a result of the events two Operating Philosophy and Practices (OPP) were revised. OPP 1, Control Board Monitoring During Non-
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Emergency Operational Conditions, was revised and.became effective May 16, 1994. The document specifically requires that when controlling processes in manual, the Unit Supervisor will specify the range at which the variable should be controlled. The entire control room team should be aware of the values. Changes to the control range will be announced to the team. The, standard also states that the control room team will monitor applicable parameters on an increased frequency when a process controller is in manual.
The Unit Supervisor will specify parameters to be monitored and the frequency at which the parameters are to be monitored. Finally the standard requires the Unit Supervisor to'be informed when off normal trends or conditions are identified. The second Operating Philosophy and Practices to be revised was OPP.7, Annunciator Response. This OPP was revised and became effective May 25, 1994.
The document directs that any significant unexpected alarms are to be logged in the control room log as determined by the Unit Supervisor, and that annunciator response procedures are to be consulted to verify, that automatic actions occurred as expected and to check for applicable necessary subsequent actions.
ATTACHMENT TO AEP:NRC: 1212D Page 4 In the area of engineering judgement, the investigation concluded that the engineering judgement applied throughout the period included management review and approval and proved to be accurate based on the subsequent evaluation and maintenance of RCP-, 14 during the refueling outage. It was'oncluded based on the CCW 'event that a mechanism was required to control activities that affect quality as is noted in the corrective actions taken to avoid further violations.
The response to the Notice of Violation is as follows:
- l. Adm ssion or Denial o the Alle ed Violatio Indiana Michigan Power admits to the violation as cited in the NRC .,
Notice of Violation.
Reasons fo t e V o atio The root cause for this event was the use of an informal process to obtain technical guidance on increasing Component Cooling Water (CCW} temperature to mitigate excessive RCP seal leak off. This resulted in the failure of the efforts to develop a strategy for dealing with increased RCP seal leak off which included all of the necessary actions to increase CCW temperature. The operations department should 'have been aware that although engineering judgement indicated that 105 F CCW supply water would not significantly damage the CCW system or the equipment it cooled, this temperature was beyond the source document temperature of 95'F.
- 3. Corrective Actions Taken and Results Achieved On February 13, 1994 the Component Cooling Water (CCW) temperature was restored below 95 F. The seal leakoff problems which led to raising the CCW temperature were corrected during the Unit 1 1994 refueling outage.
- 4. Corrective etio s Taken to Avoid Further V o atio s Interim and long term instructions will be developed on acceptable methods to obtain technical direction for activities affecting quality where the direction is not derived from approved source documents. The interim instruction will be in place by 7/29/94. The long term instruction will be in place by 12/30/94.
ATTACHMENT TO AEP:NRC: 1212D Page 5 5, Date When Full Com liance wil be Achieved Full 'compliance was achieved on February 13, 1994 when the Component Cooling Water temperature was restored to a condition below 95 F'.