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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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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
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CATEGORY 2 REGULA RY INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9711170206 DOC.DATE: 97/08/01 NOTARIZED: YES 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 Project-686 Westinghouse Owners Group Generic Lic Renewal Pr PROJ0686 AUTH. NAME AUTHOR AFFILIATION FXTZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana E Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards response to two items noted in GL 97-01, "Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations," dtd 970401.
Avail)J DISTRIBUTION CODE: DF01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Direct Flow Distribution: .50 Docket (PDR NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL INTERNA . ILE CENTER 0 1 1 NUDOCS-ABSTRACT 1 1 Y
EXTERNAL: NOAC NRC PDR 1 1 D
0 E
N 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 TOTAL NUMBER OF COPIES REQUIRED: LTTR 4 ENCL 4
-Indiana Michigan Power Company 500 Circle Drive Ouchanan, Ml 49>07 1395 INDIAitM NICHIGAN PQWM August 1, 1997 AEPrNRC01218C 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 GENERIC LETTER 97-01, "DEGRADATION OF CONTROL ROD DRIVE MECHANISM NOZZLE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS" 120 DAY RESPONSE This letter and its attachments respond to the two items noted in generic letter (GL) 97-01, "Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations," dated April 1, 1997.
Attachment 1 contains the responses to the items as applicable to Cook Nuclear Plant. Attachment 2 contains WCAP-14901, "Background and Methodology for Evaluation of Reactor Vessel Closure Head Penetration Integrity for the Westinghouse Owners Group," dated July 1997.
As noted in our initial response, we are a member of the Westinghouse Owners Group, and are participating in the Nuclear Energy Institute-sponsored industry group to develop an integrated industry program for future inspections. The integrated industry program plan will be submitted to the NRC by the end of 1997. We are conducting a records search to determine past resin ingress into the reactor coolant system. Due to the volume of records, we are requesting an extension to October 30, 1997, to respond to this issue.
Sincerely, E.E.Fitzpatrick SWORN TO AND SUBSCRIBED BEFORE ME Vice President I
vlb Notary Public Attachments My Commission Expires /-2/- Add I A. A. Blind A. B. Beach MDEQ - DW Ec RPD NRC Resident inspector IINDAL BoflCKE J. R. Padgett Notary Public, Berrien County, Ml r 4 My Commimioo rrrpiror 2moory 21, 2001 PQ 97i i i70266,97080i ADOCK'050003iS PDR P -"
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ATTACHMENT 1 TO AEP:NRC:1218C DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 GENERIC LETTER 97-01 "DEGRADATION OF CONTROL ROD DRIVE MECHANISM NOZZLE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS" 120 DAY RESPONSE to AEP:NRC:1218C Page 1 Introduction The NRC generic letter (GL) 97-01, "Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations,"
was issued to request licensees to describe their programs for ensuring the timely inspection of pressurized water reactor (PWR) control rod drive mechanism (CRDM) and other vessel closure head penetrations. This response provides the information requested by the GL as applicable to Cook Nuclear Plant.
We continue to work with the Westinghouse Owners Group (WOG), the Electric Power Research Institute (EPRI), and the Nuclear Energy Institute (NEI) to understand the issues associated with the degradation of CRDM head penetration tubes. Several tasks have been initiated in the areas of operational experience, technical issues, cause factors, relative importance, and solutions. One of these tasks was the development of a safety evaluation by Westinghouse Electric Corporation that characterized crack initiation, propagation, and consequences. This safety evaluation is contained in Westinghouse report WCAP-13565 and is applicable to Cook Nuclear Plant. The NRC reviewed the Westinghouse safety evaluation and issued a safety evaluation report (SER) on November 19, 1993, that concluded primary water stress corrosion cracking (PWSCC) of reactor pressure vessel (RPV) head penetrations is not an immediate safety issue. The Westinghouse safety evaluation and the NRC SER establish the basis for continued operation of the plant.
The following responses are offered to the information requested in GL 97-01.
1.1 A description of inspections of all CRDM nozzle and other VHPs performed to the date of this generic letter, including the results of these inspections.
Res onse - Unit 1 The requirements of GL 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants," have been incorporated in plant procedure 12-PMP 5030.001.001, "Boric Acid Corrosion of Ferritic Steel Components and Materials,"
and visual inspections have been performed regularly during the refueling outages. This procedure establishes the guidelines for the identification, examination, and evaluation of boric acid induced corrosion of ferritic steel components within the reactor coolant system (RCS) pressure boundary and other plant systems that see borated water service. If identified, an evaluation of the material wastage would be performed and a recommended course of action developed. Corrective maintenance would be performed, as required, thus preventing RCS pressure boundary degradation.
Examinations conducted as part of GL 88-05 have not revealed any RPV head penetration leakage.
The in-service inspection (ISI) visual inspection requirements to identify RCS leakage are set forth in procedure 12-QHP 5070 NDE.001, "RCS System Leakage Test."
This procedure demonstrates by visual VT-2 examination the integrity of the RCS by performing a system leakage test at system operating pressure and temperature conditions in mode 3, prior to returning the unit to service. The to AEP:NRC:1218C Page 2 procedure satisfies the testing and documentation requirements set forth in ASME section XI, articles IWA-5000, IWB-2500, IWB-5000, code cases N-498-1, N-416-1, and N-533.
This system leakage test is performed prior to start-up following each refueling outage, and following the opening and closing of a component in the system. RCS leakage tests have not identified any RPV head penetration leakage.
A liquid penetrant inspection of the RPV head CRDM penetrations'i-metallic welds are performed during each ten year ISI interval in accordance with the requirements of ASME section XI, table IWB-2500-1, examination category B-O, item no. B14.10. Liquid penetrant inspection of the RPV head penetrations'i-metallic welds during the first and second ten year ISIinterval has not identified any bi-metallic weld degradation.
During the unit 1 1994 refueling outage, using a remote camera, 33 outer RPV head penetrations were visually inspected to identify RCS leakage. No evidence of RCS leakage was identified.
Res onse - Unit 2 As a result of a voluntary commitment to inspect RPV head CRDM penetrations, 71 of the 78 unit 2 RPV head penetrations were inspected during the 1994 unit 2 refueling outage.
Spare penetrations at locations 22, 23, 25, 26, 27, 28, and 29 were not inspected due to accessibility problems resulting from installed part length drive shafts. Of the 71 penetrations inspected, 70 penetrations exhibited no indications and 1 penetration exhibited 3 indications. The indications were detected in an outer row penetration 75.
In addition, during the unit 2 1996 refueling outage, the 5 outer RPV head CRDM penetrations, including penetration 75, were reinspected. Reinspection of penetration 75 identified no significant flaw growth and no additional indications were identified in the other outer penetrations. Penetration 75 was repaired following the reinspection. Using the Westinghouse probabilistic model for susceptibility and plant specific data, a probabilistic assessment was performed for the 78 RPV head penetrations. The results identified the 5 outer penetrations as most susceptible and the 7 spare penetrations not inspected during the 1996 unit 2 refueling outage as low susceptibility. The results of these inspections were submitted to the NRC via letter AEP:NRC:1218, dated October 26, 1994, and letter AEP:NRC:1218A, dated March 12, 1996.
The requirements of GL 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants," have been incorporated in plant procedure 12-PMP 5030.001.001, "Boric Acid Corrosion of Ferritic Steel Components and Materials,"
and visual inspections have been performed regularly during the refueling outages. This procedure establishes the guidelines for the identification, examination, and evaluation of boric acid induced corrosion of ferritic steel components within the RCS pressure boundary and other plant systems that see borated water service. If identified, an evaluation of the material wastage would be performed and a to AEP:NRC:1218C Page 3 recommended course of action developed. Corrective maintenance would be performed as required, thus ensuring RCS pressure boundary integrity. Examinations conducted as part of GL 88-05 have not revealed any RPV head penetration leakage.
The ISI visual inspection requirements to identify RCS leakage are set forth in procedure 12-QHP 5070 NDE.001, "RCS System Leakage Test." This procedure demonstrates, by visual VT-2 examination, the integrity of the RCS by performing a system leakage test at system operating pressure and temperature conditions in mode 3 prior to returning the unit to service. The procedure satisfies the testing and documentation requirements set forth in ASME section XI, articles IWA-5000, ZWB-2500, IWB-SOOO, code cases N-498-1, N-416-1, and N-533. This system leakage test is performed prior to start-up following each refueling outage, and following the opening and closing of a component in the system. RCS leakage tests have not identified any RPV head penetrations leakage.
A liquid penetrant inspection of the RPV head welds are performed during each ten year ISI penetrations'i-metallic interval in accordance with the requirements of ASME section XZ, table 1WB-2500-1, examination category B-O, item no.
B14.10. Liquid penetrant inspection of the RPV head penetrations'i-metallic welds during the first and second ten year ZSI interval has not identified any bi-metallic weld degradation.
1.2 Zf a plan has been developed to periodically inspect the CRDM nozzle and other VHPs:
a ~ Provide the schedule for the first, and subsequent, inspections of the CRDM nozzle and other VHPs, including the technical basis for the schedule.
- b. Provide the scope for the CRDM nozzles and other VHP inspections, including the total number of penetrations (and how many will be inspected), which penetrations have thermal sleeves, which are spares, and which are instrument or other penetrations.
~Res onse We are participating in the WOG/NEZ RPV head penetration industry integrated inspection program, as discussed in our response to item 1.4.
1.3 If a plan has not CRDM nozzle been developed to periodically inspect the and other VHPs, provide the analysis that supports why no augmented inspection is necessary.
~Res onse We are participating in the WOG/NEZ RPV head penetration industry integrated inspection program, as discussed in our response to item 1.4.
1.4 In light of the degradation of CRDM nozzle and other VHPs described above, provide the analysis that supports the
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Attachment 1 to AEP: NRC: 1218C Page 4 selected course of action as listed in either 1.2 or 1.3 above. In particular, provide a description of all relevant data and/or tests used to develop crack initiation and crack growth models, the methods and data used to validate these models, the plant specific inputs to these models, and how these models substantiate the susceptibility evaluation.
Also, if an integrated inspection program is being relied on, provide a detailed description of this program.
~Res onse We are a participant in the WOG/NEI RPV head penetration integrated inspection program as identified in WCAP 14901, attachment 2. The Westinghouse Owners Group (WOG), Babcock and Wilcox Owners Group (BWOG), Combustion Engineering Owners Group (CEOG), and EPRI agreed to combine their efforts as part of the NEI alloy 600 CRDM head penetration cracking task force. This industry integrated program includes volumetric inspections of head penetrations that have been performed, (see attachment 2, section 1.3), and additional volumetric inspections that will be performed. Present plans call for two CE-designed plants and two B&W-designed plants to be inspected over the next three years. Additionally, Westinghouse-designed plants are likely to be added to the list over the next few months.
The crack growth rate model, crack initiation model development, and crack initiation testing are discussed in WCAP 14901, sections 2 and 3, respectively. The technical description of the probabilistic model is discussed in WCA-14901, section 4.
We believe the number of plants that have been or will be inspected is sufficient to demonstrate the adequacy of the WOG/NEI industry integrated inspection program. The need and schedule for initial and subsequent inspections will be based on an evaluation of the inspection results from the integrated inspection program.
NEI is integrating, for all PWR RPV head penetrations (nozzles), the estimated time to initiate and propagate a PWSCC flaw 75% through wall. This integrated information with an evaluation of its significance will be provided to the NRC by the end of 1997.
- 2. Provide a description of any resin bead intrusions, as described in IN 96-11, that have exceeded the current EPRI PWR Primary Water Chemistry Guidelines recommendations for primary water sulfate levels, including the following information:
2 ' Were the intrusions cation, anion, or mixed bed7
~Res onse We are currently reviewing the plant records using the intrusion volume criteria agreed upon by the industry. This data search is structured to identify all resin intrusion events into the primary coolant system with a magnitude greater than 1 ft'7.48 gallons). The threshold of 1 ft~ was chosen as a conservative lower bound because it represents to AEP:NRC:1218C Page 5 less than 15%. of the estimated volume of resin released in the reactor coolant system during the events at Jose Cabrera.
The value of 1 ft'as selected as a screening limit by the NEI alloy 600 RPV head penetration cracking task force.
Due to the volume of records, we are requesting an extension to complete the review of the plant records and to determine any resin ingress occurrences that exceeded the industry criteria as noted above. We will submit the results of our review to the NRC by October 30, 1997.
2.2 What were the durations of these intrusions2
~Res onse Due to the volume of records, we are requesting an extension to complete the review of the plant records and to determine whether any resin ingress occurred that exceeded the industry criteria as noted above. We will submit the results of our review to the NRC by October 30, 1997.
2 ~3 Does the plant's RCS water chemistry Technical Specifications follow the EPRI guidelines2
~Res ense Cook Nuclear Plant's RCS water chemistry specifications follow the RCS control parameters in EPRI primary water chemistry guidelines, revision 2, issued in November 1990.
2 ~4 Identify any RCS chemistry excursions that exceed the plant administrative limits for the following species: sulfates, chlorides or fluorides, oxygen, boron, and lithium.
~Res onse We believe that it is unnecessary to review plant records for boron, chlorides, and oxygen because these species are not viewed as valid indicators of cation resin ingress and degradation within the primary coolant system of a PWR. Due to the volume of records, we are requesting an extension to complete the review of the plant records with respect to sulfates, flourides and lithium. We will submit the results of our review to the NRC by October 30, 1997.
2 ~5 Identify any conductivity excursions which may be indicative of resin intrusions. Provide a technical assessment of each excursion and any follow-up actions.
R~es onse Due to the volume of records, we are requesting an extension to complete the review of the plant records. We will submit the results of our review to the NRC by October 30, 1997.
to AEP:NRC:1218C Page 6 2.6 Provide an assessment of the potential for any of these intrusions to result in a significant increase in the probability for IGA of VHPs and any associated plan for inspections.
~Res ense Due to the volume of records, we are requesting an extension to complete the review of the plant records. We will submit the results of our review to the NRC by October 30, 1997.
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ATTACHMENT 2 TO AEP:NRC:1218C WCAP-14901, "BACKGROUND AND METHODOLOGY FOR EVALUATION OF REACTOR VESSEL CLOSURE HEAD PENETRATION INTEGRITY FOR THE WESTINGHOUSE OWNERS GROUP DATED JULY 1997
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