Similar Documents at Cook |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999 Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21 IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20217D9241999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML20196K5961999-06-30030 June 1999 Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021 ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML20207A9201999-05-21021 May 1999 Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML20205P0591999-04-14014 April 1999 Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed ML17325B5141999-03-30030 March 1999 Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML17325B5191999-03-29029 March 1999 Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed ML20204F6401999-03-19019 March 1999 Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage ML17325B4751999-03-18018 March 1999 Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed ML17325B4721999-03-18018 March 1999 Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal ML17325B4641999-03-17017 March 1999 Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation 1999-09-30
[Table view] |
Text
ACCESSION NBR:9807130177 CATEGORY 2 I
REGULATORY INFORMATIONhDISTRIBUTION SYSTEM (RIDS)
DOC.DATE: 98/06/26 NOTARIZED: NO '
DOCKET ¹ FACIL: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 AFFIL1ATION LIPARULO,N.J. Westinghouse Electric Company, Div of CBS Corp.
RECIP . NAME RECIPXENT AFFILIATION PETTIS,R.L.
SUBJECT:
Responds to request for addi status re issues raised during insp on 980615-17 pertaining to ice condenser basket screws.
Preliminary schedule for completion of potential issue investigation is listed.
DISTRIBUTION CODE: IE19T COPIES RECEIVED:LTR ENCL SIZE: E TITLE: Part 21 Rept (50 DKT)
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD STANG, J INTERNA FILE CENT 01 NRR/DRPM/PECB NRR DRP /PECB/B PDR WARD, M.
RES/DET/EIB RGN1 RGN2 RGN3 RGN4 EXTERNAL: INPO RECORD CTR 1 NOAC SILVER,E 1 NRC PDR 1 NUDOCS FULL TXT 1 QE,c.dA'3 QhQ R L'Sd
< i (0g e 'bs NOTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 h
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPTES REQUTRED: LTTR 15 ENCL
Westinghouse Electric Company, Box 355 a division ot CBS Corporation ~ Pittsburgh Pennsylvania 152304355 NSD-NRC-98-5728 June 26, 1998 Mr. Robert L. Pettis Senior Reactor Engineer Of6ce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC
Subject:
Supplemental Information Regarding the NRC Inspection of Westinghouse, June 15-17, 1998
Dear Mr. Pettis:
The following information is in response to your request for additional status regarding the issues raised during your inspection pertaining to ice condenser basket cracked screws.
I. Ice Condenser Basket Sheet Metal Screws Westinghouse is investigating this situation as a Potential Issue (PI) within our 10 CFR Part 21 program as delineated in Westinghouse procedure ESBU-21. This investigation will include a review of both the TVA Central Laboratory Services report produced in June 1995 and the Gelles Laboratories report produced for American Electric Power in May 1998 and provided to Westinghouse in June 1998. Westinghouse has further committed to inform our utility customers whose plants incorporate ice condensers of the interactions between Westinghouse and the NRC on this issue.
A preliminary schedule for completion of the Potential Issue (PI) Investigation is as follows:
Com letion Tar et
- l. Perform metallurgical evaluation of~D. C. C tngheet Metal 7/1/98 Screws (200 supplied by utility)
- Preliminary results: 100 screws evaluated. Only two screws contained cracks: one was indication of a quench crack and one had cracks at the apex of the thread. Approximately ten (10) screws with screw heads broken off indicated failure due to overtorquing. No service induced failures were apparent.
.)gLog 4
i41r. Robert L. Pettts 2. Review screw design including coatings. 7/15/98
- 3. Investigation and confirmation of the failure mechanism and 7/15/98 root cause.
- 4. Review of available reports and draft W technical position. 7/22/98 Includes:
- Evaluation of Gelles Report supplied by D. C. Cook.
- Review 1995 Westinghouse Evaluation of TVA Central Lab Services Report 95-1021 (Preliminary and Final).
- Interface with Duke Power Company and TVA regarding previous metallurgical work.
- 5. Investigate consequences of having cracked screws. 7/22/98
- CAR 98-1157, "Design Documentation to assure correct screws specified".
i) Review Vendor Purchase Order Documentation.
ii) Revise Ice Basket Dwg./Spec to include screw required mechanical properties.
iii) Issue report.
- CAR 98-1170 'W Report MSE-REE-1371 i) Address TVA Central Lab Services Report 95-1021 ii) Address consequences of ejected ice baskets hitting air handling units.
iii) Address potential presence of additional cracked sheet metal screws.
- 6. Conduct Test Program to establish load carrying capacity of 8/14/98 Screws (ifdetermined to be necessary). (7/31 Preliminary)
- 2. Additional Information on the Evaluation of the TVA Central Laboratory Services Report, Jun 1995 Westinghouse is continuing to assess the circumstances and decisions made in 1995 regarding the TVA report and the potential impact on ice condenser equipment. However, we do note that the issue of ice basket screw cracking was given a broad dissemination at the time of its discovery in 1995 and at various times thereafter. For example, the issue of ice basket sheet metal screw failures was discussed at length at the "International Ice Condenser UtilityGroup Symposium" held from June 26-28, 1995. This symposium, hosted by American Electric Power at their Cook Nuclear Plant facility in Bridgman, Michigan was attended by all three domestic ice condenser utilities. We also note that the NRC may have reviewed sheet metal screws issues during the course of its oversight activities prior to issuing the Watts Bar OL in 1995 and again as a part of an inspection at TVA in 1997 (NRC Inspection Report 97-04).
, -i, Mr. Robert L. Pettis 3. D. C. Cook Gelles Report, June 1998 Finally, we would like to reiterate our position that, at the time of the NRC's recent inspection, the issue of ice basket screws cracked at D. C. Cook was being assessed by our cognizant engineering organization to reach the necessary engineering conclusions that are a prerequisite to determining whether to institute a Part 21 investigation. In accordance with the Part 21 regulations and our Part 21 procedure, these conclusions, as well as any other information available to us, including the fact and extent of the NRC's prior knowledge of the issue, would have then been taken into account in any decision to commence a formal Part 21 investigation. As was noted to the inspection team, the engineer responsible for conducting our preliminary evaluation of the Gelles report was only a short time away from completing his assessment so that the appropriate determinations on this issue under Part 21 could be made.
Westinghouse is always willing to meet with the NRC to further discuss any facet of this issue. Should you wish to discuss this further, please contact Mr. H. A. Sepp, Manager, Regulatory and Licensing Engineering at (412) 374-5282 at your convenience.
Very truly yours, N. J. Liparulo, Manager Equipment Design and Regulatory Engineering Enclosures Mr. Melvin S. Holmberg Reactor Inspection NRC Region III 801 Warrenville Road Lisle, Il 60532
l +4 ~ CATEGORY 1~
~4 REGULATORY INFORMATION DISTRIBUTIOWSYSTEM (RIDS)
ACCESSION NBR:9807130177 DOC.DATE: 98/06/26 NOTARIZED: NO DOCKET FACIL: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 LIPARULO,N.J. Westinghouse Electric Company, Div of CBS Corp.
RECIP.NAME RECIPIENT AFFILIATION PETTIS,R.L.
SUBJECT:
Responds to request for addi status re issues raised during insp on 980615-17 pertaining to ice condenser basket screws.
Preliminary schedule for completion of potential issue investigation is listed.
DISTRIBUTION CODE: IE19T COPIES RECEIVED:LTR J ENCL 0 SIZE:
TITLE: Part 21 Rept (50 DKT) E NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3- STANG, J INTERN : FI E CENTER 01 NRR/DRPM/PECB R DRPM P PDR WARD, M.
RES/DET/EIB RGN1 RGN2 RGN3 RGN4 EXTERNAL: INPO RECORD CTR NOAC SILVER,E NRC PDR NUDOCS FULL TXT D U
E N
YHIS DOCUMENT HAS BEEN SCANNED
-NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL k5'
I p II 6'ti f*, g" '
f',a
Westinghouse Electric Company, Box 355 a division of CBS Corporation Pittsburgh Pennsylvania 152304355 NSD-NRC-98-5728 June 26, 1998 Mr. Robert L. Pettis Senior Reactor Engineer Once of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC
Subject:
Supplemental Information Regarding tbe NRC Inspection of Westinghouse, June 15-17, 1998
Dear Mr. Pettis:
The following information is in response to your request for additional status regarding the issues raised during your inspection pertaining to icc condenser basket cracked screws.
I. Ice Condenser Basket Sheet Metal Screws Westinghouse is investigating this situation as a Potential Issue (PI) within our 10 CFR Part 21 program as delineated in Westinghouse procedure ESBU-21. This investigation will include a review of both the TVA Central Laboratory Services report produced in June 1995 and the Gclles Laboratories report produced for American Electric Power in May 1998 and provided to Westinghouse in June 1998. Westinghouse has further committed to inform our utility customers whose plants incorporate ice condensers of the interactions between Westinghouse and the NRC on this issue.
A preliminary schedule for completion of the Potential Issue (PI) Investigation is as follows:
Com letion Tar et
- 1. Perform metallurgical evaluation of D. C. Cook Sheet Metal 7/1/98 Screws (200 supplied by utility)
- Preliminaryresults: 100screwsevaluated. Only two screws contained cracks: one was indication of a quench crack and one had cracks at the apex of the thread. Approximately tcn (10) screws with screw heads broken off indicated failure duc to overtorquing. No service induced failures were apparent.
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,, Mr.'Robert L. Pettis 2. Review screw design including coatings. 7/15/98 I
- 3. Investigation and confirmation of the failure mechanism and 7/15/98 root cause.
- 4. Review of available reports and draft W technical position. 7/22/98 Includes:
- Evaluation of Gelles Report supplied by D. C. Cook.
- Review 1995 Westinghouse Evaluation of TVA Central Lab Services Report 95-1021 (Preliminary and Final).
- Interface with Duke Power Company and TVA regarding previous metallurgical work.
- 5. Investigate consequences of having cracked screws. 7/22/98
- CAR 98-1157 "Design Documentation to assure correct screws specified".
i) Review Vendor Purchase Order Documentation.
ii) Revise Ice Basket Dwg./Spec to include screw required mechanical properties.
iii) Issue report.
- CAR 98-1170 "W Report MSE-REE-1371 i) Address TVA Central Lab Services Report 95-1021 ii) Address consequences of ejected ice baskets hitting air handling units.
iii) Address potential presence of additional cracked sheet metal screws.
- 6. Conduct Test Program to establish load cariying capacity of 8/14/98 Screws (ifdetermined to be necessary). (7/31 Preliminary)
Additional Information on the Evaluation of the TVA Central Laboratory Services Report, June 1995 Westinghouse is continuing to assess the circumstances and decisions made in 1995 regarding the TVA report and the potential impact on ice condenser equipment. However, we do note that the issue of ice basket screw cracking was given a broad dissemination at the time of its discovery in 1995 and at various times thercaAer. For example, thc issue of ice basket sheet metal screw failures was discussed at length at the "International Ice Condenser UtilityGroup Symposium" held from June 26-28, 1995. This symposium, hosted by American Electric Power at their Cook Nuclear Plant facility in Bridgman, Michigan was attended by all three domestic ice condcnscr utilitics. We also note that the NRC may have reviewed sheet metal screws issues during the course of its oversight activities prior to issuing the Watts Bar OL in 1995 and again as a part of an inspection at TVA in 1997 (NRC Inspection Report 97-04).
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- 3. C. Cook Gelles Report, June 1998 Finally, we would like to reiterate our position that, at the time of the NRC's recent inspection, the issue of ice basket screws cracked at D. C. Cook was being assessed by our cognizant engineering organization to reach the necessary engineering conclusions that are a prerequisite to determining whether to institute a Part 21 investigation. In accordance with the Part 21 regulations and our Part 21 procedure, these conclusions, as well as any other information available to us, including the fact and extent of the NRC's prior knowledge of the issue, would have then been taken into account in any decision to commence a formal Part 21 investigation. As was noted to the inspection team, the engineer responsible for conducting our preliminary evaluation of the Gelles report was only a short time away from completing his assessmcnt so that the appropriate determinations on this issue under Part 21 could be made.
Westinghouse is always willingto meet with the NRC to further discuss any facet of this issue. Should you wish to discuss this further, please contact Mr. H. A. Sepp, Manager, Regulatory and Licensing Engineering at (412) 374-5282 at your convenience.
Very truly yours, N. J. Liparulo, Manager Equipmcnt Design and Regulatory Engineering Enclosures CC: Mr. Melvin S. Holmberg Reactor Inspection NRC Region III 801 Warrenville Road Lisle, Il 60532
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