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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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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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REGULATO INFORMATION DISTRIBUTION TEM (RIDE)
ACCESSION NBR:9609180259 DOC.DATE: 96/09/10 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana, M 05000315 50-3.'.ig Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316
.'UTHOR
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AUTH. NAME AFFILIATION FITZPATRICK,E.E American Electric Power Co., Inc.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to 960614 RAI re third ten year inservice insp interval program plan 6 associated requests for relief.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submi,ttal: 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 1 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL: AEOD/SPD/RAB 1 1 LE CglgZE 01 1 1 NRR/DE/ECGB 1 1 NRR DE EMCB 1 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 PDR 1 1
'RC NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415"2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 14,
Indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216
/NJNSlNA NICNlCAN PWM September 10, 1996 AEP:NRC:0969AW 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 THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM AND ASSOCIATED REQUESTS FOR RELIEF (TAC NOS. M94871 AND M94872)
REQUEST FOR ADDITIONAL INFORMATION This letter responds to your June 14, 1996, request for additional information regarding the third 10 year inservice inspection interval program plan and associated relief requests. The requested information is contained in Attachment 1 to this letter.
Attachment 2 contains a summary of weld examinations where the third 10 year interval exam schedule does not agree with the first 10 year interval.
Vice President jmb Attachments CC: A. A. Blind A. B. Beach NFEM Section Chief NRC Resident Inspector A%7 ~
J. R. Padgett 7QQQgg 9'609i80259 9609i0 PDR ADQCK 050003i5
, 8 PDR
ATTACHMENT 1 TO AEP:NRC:0969AM REQUEST FOR ADDITIONAL INFORMATION REGARDING THE DONALD C. COOK NUCLEAR PLANT, UNITS 1 and 2 THIRD 10 YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF (TAC NOS. M94871 AND M94872) to AEP:NRC:0969AM Page 1 The Cook Nuclear Plant units 1 and 2 third 10 year inservice inspection interval began on July 1, 1996. In accordance with 10CFR50.55(a), relief requests for examinations and inspections that cannot be conducted in accordance with the adopted edition of ASME Section XI must be demonstrated to the satisfaction of the NRC within 12 months after the start of the new inspection interval.
Code relief requests for Cook Nuclear Plant, units 1 and 2 for examinations of components that could not be performed in accordance with ASME Section XI were submitted to the NRC in January 1996, in submittal AEP:NRC:0969AJ. Also provided with the required third 10 year interval code relief requests was a copy of the long term plan for the .inservice inspection (ISI) program for each unit to facilitate the review of the code relief requests.
In a letter dated June 14, 1996, the NRC's reviewer (INEL) concluded that additional information was required based on the review of the ISI program. The purpose of this submittal is to provide the requested information.
The following lists each question as stated in the NRC correspondence dated June 14, 1996, (italicized) followed by our response.
Question A Section I.l references Code Cases N-491-1, N-498-1, N-509, N-521, and N-524. The code cases have not been approved for use by reference in Regulatory Guide Nl.147. Therefore, to use these code cases, requests for relief are required. For use as a guide when preparing request for relief, attached is Appendix A, "Inservice Inspection: Guidance for preparing requests for relief from certain code requirements pursuant to 10CFR50.55(g) (5) ."
Answer A 10CFR50.55 in footnote 6 references that the code cases listed in Regulatory Guide 1.147, Inservice Inspection Code Case Applicability, ASME Section XI can be used by reference in the long term plan without prior NRC approval. Because several code cases the Cook Nuclear Plant desires to use during the third 10 year interval are not listed in Regulatory Guide 1.147, code relief requests will be submitted to the NRC by October 31, 1996, and the long term plan will be revised accordingly.
Question B A number of welds cannot be examined due to inaccessibility or component configuration. Code relief is requested for the third interval. ~
Details of code relief requests are contained in Appendix E. Appendix E does not exist in the January 25, 1996, submittal. Provide the necessary requests for the relief for the welds that cannot 'e examined, thi s interval, due to inaccessibility or component configuration as required by 10CFR50.55a (g) (5) (i v) .
Attachment 1 to AEP:NRC:0969AW Page 2 Answer B Appendix E was a courtesy copy of the long term plan. The code relief requests were inadvertently left out of the copy provided to the NRC. The contents of this appendix, however, are identical to the code relief requests we provided to the NRC in our letter AEP:NRC'0969AJ.
Question C Many exams listed in the schedule of examinations contained in the long term plan do not appear to follow code successive examination requirements. The code requires the sequence of examinations established during t'e first inspection interval shall be repeated during each successive inspection interval, to the extent practical. However, many items seems to be scheduled for examination in the third interval without regard to when they were examined in the previous intervals. Provide a detailed technical position explaining how Donald C. Cook Nuclear Plant, Units and 2, meets the Code successive examination requirements.
l Answer C ASME Section XI in paragraph IWB-2420, states that "sequence of component examinations established during the first interval shall be repeated during each successive inspection interval to the extent practical." Many changes were made to the sequence of component examinations; however, successive examination requirements were met to the extent practical. These changes were necessary to maximize examination coverage and reduce radiation exposure while meeting the requirements of successive examination to the extent practical. We believe that we meet the intent of the phrase "to the extent practical" where there are significant radiation exposure savings or improvement in examination coverages.
In inspection of piping, code changes between the first 10 year inspection interval and the third 10 year interval have required revisions to the allocations due to reclassification of systems (high pressure safety injection lines). In some cases, weld examinations which were performed during the first interval were not performed in the second interval due to differences in the edition of the code adopted during those intervals. To meet the ASME Section XI code requirements and Table IWX-2412, adjustments were necessary to balance the percentage of examination between periods. Attachment 2 lists these sorted by class and summary number in addition to the reason the change was made.
In the case of vessel examinations, the proposed use of code cases that defer examinations to the end of the interval (RPV nozzle to shell welds and nozzle inside radius examinations) and reductions in examination of some welds account for a majority of the differences.
to AEP:NRC:0969AW Page 3 Question D The schedule of examinations, included in the long-term plan, contains no class -3 pressure tests. Appendix D Pages D-34 and D-35 (Units 1 and 2 respectively) states: "Class 3 pressure-retaining components will have pressure test scheduled by IMP, as maintenance requirements and plant technical specifications dictate." Do the technical specifications dictate a 10-year system hydrostatic test or periodic syst'm pressure testP If not, how will ensure that Section XI pressure test requirements are met7 the licensee Answer D The 10 year ISI system hydrostatic tests for class 3 components are conducted in accordance with technical specification 4.0.5, which requires conformance to ASME Section XI. The required system pressure tests for class 3 components are performed in accordance with ASME Section XI and Code Case N-498-1 as indicated in the third 10 year interval long term plan for units 1 and 2. We have been granted approval from the NRC in another request to use this code case at Cook Nuclear Plant as an alternative to hydrostatic testing. A code relief request to use Code Case N-498-1 for the third 10 year interval will be provided by October 31, 1996, as discussed in Answer A.
Question E It appears that'he scheduling of Unit 2, Examination Category B-D does not meet the code percentage requirements of IVA-2412. Vas this an oversight? If not, provide a request for relief justifying this deviation from code requirements.
Answer E The schedule for the ASME Section XI, Table IWB-2500, B-D welds for both units is consistent with code case N-521. We intend to use guidance provided in this code case for the units 1 and 2 reactor pressure vessel nozzle to shell welds and inside radius geometries.
Request for approval to use this code case will be submitted as a relief request by October 31, 1996, as described in Answer A. The B-D welds for the unit 2 pressurizer are all scheduled in the first inspection period, which is not in compliance with Table IWB-2412.
We will adjust the schedule of these welds for the third 10 year interval to agree with the schedule of the second 10, year interval and the long term plan will be revised accordingly.
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4 Attachment 1 to AEP:NRC:0969AW Page 4 Question F Included with the submittal of the Donald C. Cook Nuclear PLant, l
Units and 2, Third Ten Year Inservice Inspection Plan was several requests for Units l and 2. The requested date for these reliefs is associ ated wi th the second interval. However some of these reli efs state they are for the third intervaL. Furthermore, reli efs are menti oned in the thi rd interval program but not included in t'e plan. Based on the conflicting information presented, it is unclear as to which interval the reliefs apply.
Provide clarification as to what interval each of the reliefs is requested.
Answer F All relief requests submitted in this package are for the third 10 year interval.
Question G Provide a listing of the code cases being used at the Donald C.
Cook Nuclear Plant, Units l and 2, that are included in Regulatory Guide L. L47, Inservi ce Inspection Code Case Acceptability ASME Section XI Division l.
Answer G Code Case N-481 has been approved for use in Regulatory Guide 1.147 and will be used in the third 10 year interval. As stated in Answer A, relief requests will be submitted by October 31, 1996, for code cases that have not been accepted in Regulatory Guide 1.147 that we intend to use during third 10 year inspection interval.
ATTACHMENT 2 TO AEP:NRC:0969AW
SUMMARY
OF WELD EXAMINATIONS
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'4 Attachment 2 to AEP:NRC:0969AW Page 1 A
Suumary of wold oxmninations <<hozo schoduling of third interval oxams does not agroo with tho first interval Wold I.D Remarks Unit 1 Class 1 022200 1-RC-1-14N Perform 1st interval, rescheduled 3rd 024400 1"RC-2-12F Alignod w/ associated longitudinal weld schedule Class 2 300010 STH-11-05 Aligned w/ STH-11-04 exam 300210 STH-12-HSN-IRS Aligned w/ STH-12HSN nozzle exam 300480 RHE-I"13 Shifted from 2nd period to 3rd to balance distribution.
300490 RHE-1-16 Shifted from 2nd period to 3rd to balance distribution.
300500 RHE-1-13 Shifted from 2nd period to 3rd to balance distribution 300510 RHE-1-13 Shifted from 1st period to 3zd to balance distribution.
300680 1-CVCT-1 Shifted from 1st period to 3rd to balance distribution 300690 1-CVCT-2 Shifted from 2nd period to 3rd to balance distribution 301600 1-SI-3-09S Perform 1st interval, rescheduled 3rd 302600 1-SI-21-09S Perform 1st interval, zoschoduled 3rd 304290 1-SI-70" 11F Perform 1st interval, rescheduled 3rd 307320 1-RH-8-18F Perform 1st interval, rescheduled 3rd 310930 1 "FW-10-17S Shifted from 2nd period to 3rd to balance distribution 311170 1-FW-11-13S Perform 1st interval, rescheduled 3rd 311560 1-FW-13-09S Perform 1st intorval, rescheduled 3rd 312060 1-FW-17-07S Shifted fzom 2nd period to 3rd to balanco distribution 313000 1-FW-31-01S Perform 1st interval. rescheduled 3rd 314210 1 "HS-10-07S Perform 1st interval, reschedulod 3rd 314410 1-HS-11-13S Perform 1st interval, rescheduled 3rd 315240 1-HS-190-02S Perform 1st interval, rescheduled 3rd Unit 2 Class 1 045100 2-RC-31-11 Perform 1st intorval, rescheduled 3rd
4 Attachment 2 to AEP:NRC:0969AW Page 2 048400 2-RC-32-08 Perform 1st interval, rescheduled 3rd 050800 2-RC-33-02 Perfozm 1st interval, rescheduled 3rd 054700 2-RC-34-03 Shifted from 1st period to 3rd to balance distribution 055100 2-RC-34-04 Shifted from 1st period to 3rd to balance distribution 055200 2-RC-34"05 Shifted from 1st period to 3rd to balance d i stzibut ion 055400 2-RC-'34-06 Shifted from 1st period to 3rd to balance distribution 055500 2-RC-34-07 Shifted fromintervaled 1st period to 3rd to balance distribution 058200 2-RC-34-29 Perform 1st rescheduled 3rd 065700 2-RC-514-02 Perform 1st interval, rescheduled 3rd 072100 2"RC-515-25 Perform 1st interval, rescheduled 3rd Class 2 300260 STH-23-08 Perform 1st interval, rescheduled 3rd 300700 E-RHRHEX-IN Shifted from 2nd period to 3rd to balanco distribution 300840 2-BIT-A Shifted from 2nd period to 3rd to balance distribution 300850 2-BIT-B Shifted fromintervaled 2nd period to 3rd to balance distribution 310020 2-SI-7-028 Perform 1st interval, rescheduled 3rd 310370 2"SI-7-36S Perform 1st rescheduled 3rd 310720 2-SI-8-30S Perform 1st interval, rescheduled 3rd 310800 2-SI-8-37S Perform 1st interval, rescheduled 3rd 310950 2-SI-9-09S Perform 1st interval, rescheduled 3rd 312490 2-SI-77-05S Perform 1st interval, rescheduled 3rd 318710 2-FW-72-12S-PL1 Perform 1st interval, rescheduled 3rd and 2 319530 2-FW-76-05F Perform 1st interval., rescheduled 3rd 320130 2-FW-80-03S Perform 1st interval, rescheduled 3rd 320510 2-FW-89-04S Perform 1st interval, rescheduled 3rd 321690 2-HS-94-15S Perform 1st interval, rescheduled 3rd 322370 2-HS-193-01F Perform 1st interval, rescheduled 3rd I