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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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] |
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CATEGORY 1 REGULA ~ INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9606200158 DOC.DATE: 96/06/12 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 AFFILIATION FITZPATRICK,E.E American Electric Power Co., Inc.
RECIP.NAME RECIPIENT AFFILIATION
. Document Control Branch (Document Control Desk)
SUBJECT:
Provides third 10-yr interval in-service pump test plan 6 requests relief from ASME Section XI requirements.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE; OR Submittal: Inservice/Testing/Relief from ASME Code GL-89-04 NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL' ID CODE/NAME LTTR ENCL PD3-1 LA 1 PD3-1 PD 1 1 HICKMANgJ 1 1 INTERNAL: AEOD/SPD/RAB 1 1 ILE CENTE 01 1 1 NRR/DE/ECGB 1 1 /D~EMCB 1' NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 RES/DET/EMMEB 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
DOCUMENT CONTROL DESK, PLEASE HELP US TO REDUCE WASTE! CONTACT THE ROOM OWFN 5D-5(EXT. 415-2083) TO EI IMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU 'DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 14
American Electrl .r 1 Riverside Plaza Columbus, OH 4321 5 2373
/f P. 614 223 1000 AINMICQM KI.KCTHEC PQWKR June 12, 1996 AEP: NRC: 0969AM Docket Nos.: 50-315 50-316 U, S, Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and 2 RELIEF REQUESTS FOR THE THIRD TEN-YEAR PUMP IN-SERVICE TEST PLAN The purpose of this letter is to provide the NRC with a copy of the Donald C. Cook Nuclear Plant's third ten year interval in-service pump test plan, and t:o request relief from ASME Section XI requirements which have been determined to be impractical to meet.
Attachment 1 contains the relief requests and attachment 2 contains the third ten-year interval in-service pump test plan.
The current in-service pump test program will expire on June 30, 1996. The attached relief requests are being submitted in accordance with 10 CFR 50.55a(f)(5)(iv). This regulation requires that, when the revised in-service test program does not include an ASME Code requirement, the licensee demonstrate to the NRC the impracticality of those requirements within twelve months of the expiration of the current program. We, therefore, request approval of the relief requests by June 30, 1997.
Sincerely, E. E. Fitzpatrick Vice President llg Attachments 200038 CC: A. A. Blind C. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman PCX7I l J. R. Padgett I
9sosaooiss 9sosm 5't PDR ADQCK 05000$ f P PDR~I
U. S. Nuclear Regulatory Commission AEP:NRC: 0969AM Page 2 bcc: S. J. Brewer/D. H. Malin/M. S. Ackerman/R. G. Vasey D. F. Powell J. D. Benes J. A. Kobyra/S. H. Steinhart/S. P. Hodge J. B. Shinnock J. S. Wiebe J. B. Hickman, NRC - Washington, D. C. w/attachment P, G. Schoepf/F. R. Pisarsky PRONET w/attachment DC-N-6015.1
ATTACHMENT 1 TO AEP:NRC:0969AM IN-SERVICE PUMP TEST PLAN RELIEF REQUESTS
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S Attachment 1 to AEP:NRC: 09 Page 1 COOK NUCLEAR PLANT,PUMP IST PROGRAM RELIEF REQUEST NO. 1 TITLE: Containment S ra Pum Vibration Limits O General O Specific X
Unit Applicability: 1 2 X 1 and 2 PUMP NAME: Containment S ra PUMP NUMBER(S): PP-009 SYSTEM: Containment S ra CTS FLOW DIAGRAM: 5144 ASME CLASS: 2 PUHP FUNCTION: Provide cool water flow to s ra the containment atmos here in a LOCA or steamline break.
RELIEF TYPE O X COMPLIANCE WITH CODE REQUIREMENTS ASME CODE TEST REQUIREMENT
REFERENCE:
IS IHPRACTICAL OMa-1988, Part 6, Table 3a Ranges for vibration'est parameters CODE REQUIREMENT DESCRIPTION: (for centrifugal pumps >600 rpm)
Acceptable range <2.5 vibration reference value (V)
Alert range >2.5 V to 6 V or >0.325 in/sec Required action range >6 V or >0.70 in/sec BASIS THAT COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL:
The design of the CTS pumps utilizes a four vane impeller in a double volute casing. This combination of an impeller with an even number of vanes operating in a casing with two volutes creates a high, reinf'orced vibration response at the vane passing frequency (7200 cpm). This condition is further compounded by the fact that the quarterly IST tests are performed at only 25K of the pump's design flow. This results in the discharge angle of the impeller flow not matching the stationary volute angle, producing high interaction forces between the impeller and the volutes. This high vane pass frequency amplitude is the major component......
of overall amplitude and is not indicative of overall pump condition. On this basis, compliance with the referenced acceptance criteria would be impractical due to the burden created by unnecessary repair and replacement of otherwise suitable pump components.
PROPOSED ALTERNATE TESTING:
Acceptable range <2.0 V Alert range >2.0 V to 4.0 V or 1.2 in/sec Required action range >4 V or 2.0 in/sec BASIS ALTERNATE TESTING YIELDS ACCEPTABLE LEVELS OF QUALITY AND SAFETY:
Although the overall vibration amplitude is increased over the alert and required action limits of ASME OMa-:1988. Part 6. Table 3a, the proposed alternate values are based upon our review of past operating data for these pumps. The values are a more representative basis for trending performance of the containment spray um s, and as such rovide an acce table level of uality and safety.
to AEP:NRC:0969 Page 2 COOK NUCLEAR PLANT PUMP IST PROGRAM RELIEF REQUEST NO. 2 TITLE: Boric Acid Transfer Pum Axial Vibr ation Measurement Unit Applicability: 1 2 X 1 and 2 PUMP NAME: Boric Acid Transfer Pum PUMP NUMBER(S): 1-PP-45-1 2'-PP-46-3 4 SYSTEM: CVCS-Makeu FLOW DIAGRAM: 12-5131 ASHE CLASS: 2 PUMP FUNCTION: Transfer boric acid solution from stora e tank to char in um suction header.
RELIEF TYPE ASME CODE TEST REQUIREMENT
REFERENCE:
OMa-1988, Part 6, Paragraph 4.6.4(a)
CODE REQUIREMENT DESCRIPTION:
On centrifugal pumps, measurements shall be taken in a plane approximately perpendicular to the rotating shaft in two orthogonal directions on each accessible pump bearing housing. Measurement also shall be taken in the axial direction on each accessible pump thrust bearing housing.
BASIS THAT COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL:
The pump thrust bearing housing is inaccessible. It is very close to the coupling, and safety considerations prevent placement of the probe. In addition, the housing is partially blocked by the impeller adjustment nuts.
PROPOSED ALTERNATE TESTING:
Take measurements in a plane approximately perpendicular to the shaft in two orthogonal directions on each accessible pump bearing housing.
BASIS ALTERNATE TESTING YIELDS ACCEPTABLE LEVELS OF QUALITY AND SAFETY:
Measurements taken in planes perpendicular to the shaft in two orthogonal directions have provided adequate data to evaluate pump performance and condition.
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~ t Attachment 1 to AEP:NRC:0969~ Page 3 COOK NUCLEAR PL'ANT PUMP IST PROGRAM RELIEF REQUEST NO. 3 TITLE: Su ersede OMa-1988 Corrective Action Part 6 Para ra h 6.1 X
Unit Applicability:
Gener al D Specific 1 2 X 1 and 2 PUMP NAME:Various PUMP NUMBER(S):PP-03 07 46 26 09 -31 T-106 -130 SYSTEM:All IST Pum in S stems in Table A FLOW DIAGRAM:See Table A ASHE CLASS:253 PUMP FUNCTION: As listed in Table A RELIEF TYPE O X COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL ASME CODE TEST REQUIREMENT
REFERENCE:
OMa-1988, Part 6, Subsection 6. 1 Acceptance Criteria CODE REQUIREMENT DESCRIPTION:
OMa-1988, Part 6, Subsection 6. 1, First Paragraphs Second Sentence Relative to Action Range. If deviations fall within the requi red action range of Table 3. the pump shall be declared inoperable unti 1 the cause of the deviation has been determined and the condition corrected.
BASIS THAT COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL:
Compliance with the required acceptance criteria will impose a significant burden if test data cannot be analyzed to determine if a pump is still capable of performing its safety function. Past experience evaluating pump test data clearly indicates a burden will be created by unnecessary extension of Technical Specification LCO durations. unnecessary reportabi lity submittals, unnecessary repairs and replacements of otherwise suitable equipment, and unnecessary component wear due to accelerated testing frequencies.
PROPOSED ALTERNATE TESTING:
ON-1995, Subsection ISTB 6.2.2. Action Range. If the measured test parameter values fall within the requi red action range of Table ISTB 5.2. 1-1 or Table ISTB .
5.2.1-2. as applicable, the pump shall be declared inoperable until either the cause of the deviation has been determined and the condition is corrected, or an analysis of the pump is performed and new reference values are established in accordance with paragraph ISTB 4.6.
to AEP:NRC:0969 Page 4 BASIS ALTERNATE TESTING YIELDS ACCEPTABLE LEVELS OF QUALITY AND SAFETY't is requested that the corrective action requirements, per ASME OMa-1988, Part 6, Subsection 6.1, be superseded for all pumps included in the ZST program. The proposed alternative is to follow subsection ZSTB 6.2.2 of ASME OM-1995, "Action Range." When applying the requirements of ISTB,6.2.2, Tables 5.2.1-1 and ISTB 5.2.1-2, the Group A test hydraulic acceptance criteria will be used since all pumps are treated as Group A pumps by ASME OMa-1988.
The current pump IST program trends the test results and replaces the pumps as they approach the IST lower limits. The trending allows for evaluations of system conditions if the test point deviates from the trend path. At that time, the pump is retested or the system conditions are reviewed to determine the cause of the deviation. This type of evaluation is consistent with the current code and is consistent with the 1995 code. On this basis, we are requesting that the corrective actions be established per ASME OM-'1995 requirements since the OMa-1988 code does not allow evaluation of test conditions.
to AEP:NRC:0969AM DONALD C. COOK NUCLEAR PLANT - UNI'I' Page 5 PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM
SUMMARY
TEST PARAMETERSr Discharge Differential Flow Vibration Pump Speed Pressure Pressure Rate Amplitude Test Pump Service Number (N) (P) (~P) (Q) (V) Frequency (Drawing No.)
Auxiliary Feedwater
- PP-3W No No Yes Yes Yes Quarterly (I-5106A) PP-3E No No Yes Yes Yes Quarterly PP-4 Yes No Yes Ycs Ycs Quarterly Essential Service Water PP-7W No No Yes Yes Yes Quarterly (1-5113) PP-7E No No Yes Yes Yes Quarterly Centrifugal Charging PP-50W No No Yes Yes Yes Quarterly (1-5129) PP-50E No No Yes Yes Yes Quarterly Boric Acid Transfer PP-46-1 No No Yes Yes Quarterly (12-5131) PP-46-2 No No Yes Yes Yes'es'es Quarterly Component Cooling Water PP-10W No No Yes Yes Quarterly (I-5135A) PP-10E No No Yes Yes Yes Quarterly Safety Injection PP-26N No No Yes Yes Yes Quarterly
'1-5142)
PP-26S No No Yes Yes Yes Quarterly Residual I-leat Removal PP-35W No No Yes Yes Yes Quarterly
'1-5143)
PP-35E No No Yes Yes Yes Quarterly to AEP:NRCr0969AH Page 6 DONALD C. COOK NUCLEAR PLANT - UN1T 1 PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM
SUMMARY
TEST PARAMETERS'ump Discharge Differential Flow Vibration Service Pump Speed Pressure Pressure Rate Amplitude Test (Drawing No.) Number (N) (P) (IP) (Q) (V) Frequency Containment Spray PP-9W No No Yes Yes Quarterly
'1-5144)
PP-9E No No Yes Yes Yes'es'es Quarterly Diesel Fuel Oil QT-106-AB1 No Yes No Yes Quarterly Transfer QT-106-AB2 No Yes No Yes Yes Quarterly
'1-5151A 8c C) QT-106-CD 1 No Yes No Yes Yes Quarterly QT-106-CD2 No Yes No Yes Yes Quarterly Spent Fuel Pit Cooling 12-PP-3 1N No No Yes Yes Yes Quarterly (12-5136)~
Jacket Water QT-130-AB1 No No Yes Yes Yes Quarterly (1-5151B Ec D) QT-130-AB2 No No Yes Yes Yes Quarterly QT-130-CD1 No No Yes Yes Yes Quarterly QT-130-CD2 No No Yes Yes Yes Quarterly These pumps are tested on test, bypass, or minimum flow loops per ASME OMA-1988 Part 6, g 3.2.
Refer to Comment l.
Refer to Comment 2.
Refer to Code Relief Request l.
Refer to Code Relief Request 2.
Refer to Code Relief Request 3.
Only North Spent Fuel Pit Pump shown here due to the alignment of its cooling train to Unit 1 Component Cooling Water.
V'ONALD to AEP:NRCr0969AM Page 7 C. COOK NUCLEAR PLANT - UNIT 2
~ ~
PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM
SUMMARY
TEST PARAMETERS'ifferential Discharge Flow Vibration Pump Speed Pressure Pressure Rate Amplitude Test Pump Service Number (N) (P) (AP) (Q) (V) Frequency (Drawing No.)
Auxiliary Feedwater PP-3W No No Yes Yes Yes Quarterly ~
'2-5106A)
PP-3E No No Yes Yes Yes Quarterly PP-4 Yes No Yes Yes Yes Quarterly Essential Service Water PP-7W No No Yes Yes Yes Quarterly (2-5113) PP-7E No No Yes Yes Yes Quarterly Centrifugal Charging PP-50W No No Yes Yes Yes Quarterly (2-5129) PP-50E No No Yes Yes Yes Quarterly Boric Acid Transfer PP-46-3 No No Yes Yes Quarterly (12-5131) PP-46-4 No No Yes Yes Yes'es'es Quarterly Component Cooling Water PP-10W No No Yes Yes Quarterly (2-5135A) PP-10E No No Ycs Yes Yes Quarterly Safety Injection '2 PP-26N No No Yes Yes Yes Quarterly
-5142) PP-26S No No Yes Yes Yes Quarterly Residual Heat Removal PP-35W No No Yes Yes Yes Quarterly
'2-5143)
PP-35E No No Yes Yes Yes Quarterly to AEP:NRCt0969AM Page 8 DONALD C. COOK NUCLEAR PLANT - UNIT 2 PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM
SUMMARY
TEST PARAMETERS Discharge Differential Flow Vibration Pump Service Pump Speed Pressure Pressure Rate Amplitude Test (Drawing No.) Number (N) (P) (h,P) (Q) (V) Frequency Containment Spray PP-9W No No Yes Yes Yes~ Quarterly
'2-5144)
PP-9E No No Yes Yes Yes4 Quarterly Diesel Fuel Oil QT-106-AB1 No Yes No Yes Yes Quarterly Transfer QT-106-AB2 No Yes No Yes Yes Quarterly
'2-5151A
& C) QT-106-CD1 No Yes No Yes Yes Quarterly QT-106-CD2 No Yes No Yes Yes Quarterly Spent Fuel Pit Cooling 12-PP-31S No No Yes Yes Yes Quarterly
( 2-5136)c 1
Jacket Water QT-130-AB1 No No Yes Yes Yes Quarterly (2-51518 & D) QT-130-AB2 No No Yes Yes Yes Quarterly QT-130-CD1 No No Yes Yes Yes Quarterly QT-130-CD2 No No Yes Yes Yes Quarterly These pumps are tested on test, bypass, or minimum flow loops per ASME OMA-1988 Part 6, $ 3.2.
Refer to Comment 1.
Refer to Comment 2.
Refer to Code Relief Request 1.
Refer to Code Relief Request 2.
f Refer to Code Relief Request 3.
g Only South Spent Fuel Pit Pump shown here due to the alignment of its cooling train to Unit 2 Component Cooling Water.