Similar Documents at Cook |
---|
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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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 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. 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 ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML20205P0591999-04-14014 April 1999 Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed ML17325B5141999-03-30030 March 1999 Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML17325B5191999-03-29029 March 1999 Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed ML20204F6401999-03-19019 March 1999 Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage ML17325B4751999-03-18018 March 1999 Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed ML17325B4721999-03-18018 March 1999 Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal ML17325B4641999-03-17017 March 1999 Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation 1999-09-30
[Table view] |
Text
~ccrc,za~x REGULAT oocvMKm O~Sr INFORMATION DISTRIBUTION mrs SvSrKM STEM (RIDS)
ACCESSION, NBR:9307190241 DOC.DATE: 93/07/09 NOTARIZED: YES DOCKET FACIL:50"316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana !; Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B. Document Control Branch (Document Control Desk)
SUBJECT:
Documents results of 930708 telcon re util request for exercise of enforcement discretion for TS 3.1.2.4 (charging pumps operating) 6 3.5.2 (ECCS subsys).Requests that 72 h action statements be extended for addi 60 h.
DISTRIBUTION CODE AOOZD COPIES RECEIVED:LTR g ENCL Q SIZE: l+
TITLE: OR Submittal: General Distribution 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 DEANgW 2 2 INTERNAL: NRR/DE/EELB 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW/OTSB 1 1 NRR/DSSA/SPLB 1 '1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OCJ~CB 1 0 OGC/HDS2 1 0 REG FIL 01 1 1 EXTERNAL: NRC PDR NSIC 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 13
t i v 0
.,J F )
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 Donald C. Cook Nuclear Plant Unit 2 AEP:NRC:1191 Docket No. 50-316 License No. DPR-74 REQUEST FOR EXERCISE OF ENFORCEMENT DISCRETION FOR TECHNICAL SPECIFICATIONS 3.1.2.4 (CHARGING PUMPS OPERATING) AND 3.5.2 (ECCS SUBSYSTEMS)
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: Mr. J. B. Martin July 9, 1993
Dear Mr. Martin:
The purpose of this letter is to document the results of a teleconference held at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on July 8, 1993, among American Electric Power Service Corp. (AEPSC), Indiana Michigan Power Company (I&M), and the NRC Regional and NRR staffs in which AEPSC/I&M requested Regional Exercise of Enforcement Discretion for Technical Specifications (T/S) 3.1.2.4 and 3.5.2 for Unit 2 of the Donald C. Cook Nuclear Plant. Currently, Unit 2 is at 70%
power with the West centrifugal charging pump (CCP) inoperable.
The unit is therefore in action statements for T/S 3.1.2.4 and 3.5.2 which allow 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the pump to operable status or commence a unit shutdown. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement time clock began at 2237 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.511785e-4 months <br /> on July 6 and expires at 2237 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.511785e-4 months <br /> on July 9. We are requesting that the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statements be extended an additional 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> to allow repairs to the inoperable pump to be performed without the need to shut the unit down.
The basis for this request is provided in the attachment and may be summarized as follows:
(1) A discussion of the requirements for which an exercise of enforcement discretion is requested.
(2) A discussion of the circumstances surrounding the situation, including the need for prompt action.
(3) A description of why the situation could not have been avoided.
9307'1 90241 930709 I PDR P
ADQCK 050003th PDR gg)(
Mr. J. B. Martin AEP'NRC:1191 (4) An evaluation of the safety significance and potential consequences of the proposed request.
(5) A discussion of compensatory actions.
(6) A discussion which justifies the duration of the request.
(7) The basis for concluding that the request does not involve a significant hazards consideration.
(8) The basis for concluding that the request, does not involve irreversible environmental consequences.
If the West CCP remains inoperable as of 1037 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.945785e-4 months <br /> on July 12, (the expiration of the Exercise of Enforcement Discretion) Unit 2 will be placed in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and then Mode 4 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, as required by T/S 3.1.2.4 and 3.5.2.
This request for Exercise of Enforcement Discretion has been reviewed by the Plant Nuclear Safety Review Committee. It be presented to the Nuclear Safety and Design Review Committee at will its next regularly scheduled meeting.
This letter is submitted pursuant to 10 CFR 50.54(f) and, as such, an oath statement is attached.
Sincerely, EF~pm Vice President dr Attachment cc: A. A. Blind - Bridgman J. R. Padgett G ~ Charnoff NRC Resident Inspector - Bridgman NFEM Section Chief
COUNTY OF FRANKLIN E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing Request For Exercise of Enforcement Discretion for Technical Specifications 3.1.2e4 (Charging Pumps - Operating) and 3.5.2 (ECCS Subsystems) and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed end sworn to before me this ~d>
day of 19~>
TARY P BLIC RITA D. HILL TIOTARY PUBLIC. STATE Of CHIO II
ATTACHMENT TO AEP:NRC:1191 ENFORCEMENT DISCRETION FOR UNIT 2 WEST CENTRIFUGAL CHARGlNG PUMP
4 Ivy f
Attachment to AEP:NRC:1191 Page 1 (1) DISCUSSION OF REQUIREMENTS FOR WHICH THE EXERCISE OF ENFORCEMENT DISCRETION IS REQUESTED This letter requests an Exercise of Enforcement Discretion from the requirements of Technical Specification (T/S) 3.1.2.4 (Charging Pumps - Operating) and 3.5.2 (ECCS Subsystems). For T/S 3.1.2.4, relief is requested from the requirement to have two charging pumps operable in Modes 1 through 4. With only one charging pump operable, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed to restore two pumps to operable status or the unit must be placed in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (and borated to a shutdown margin equivalent to at least 1%
delta k over k at 200 deg. F). Both charging pumps must be restored to operable status within the next 7 days, or the unit must be placed in Mode 5 within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. For T/S 3.5.2, relief is requested from the requirement to have two independent ECCS subsystems operable in Modes 1 through 3. With one ECCS subsystem inoperable, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed to restore the inoperable subsystem to operable status or the unit must be in mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The basis for T/S 3.1.2.4 is to ensure that negative reactivity control is available. A minimum of two separate and redundant boron injection systems are provided to ensure functional capability in the event an assumed failure renders one of the systems inoperable.
The basis for T/S 3.5.2 is to ensure that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one train of ECCS. Although not specifically discussed in the basis, the charging and other ECCS pumps are also modeled in other UFSAR analyses such as steamline break.
Since the duration of the requested Exercise of Enforcement Discretion is brief (60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />), we believe the extension is preferable to imposing a thermal transient on the plant as would occur if the unit must be shut down. Additionally, we note that warm weather conditions have resulted in an increased demand for power within our region, making it undesirable from a system operation's perspective to unnecessarily remove the unit from service. As discussed below, the increased risk to core damage frequency, as determined by our individual plant examination, is small.
(2) DISCUSSION OF THE CIRCUMSTANCES SURROUNDING THE SITUATION On July 6, 1993, at approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, the unit was in operation at 70% power. The shift experienced difficulty in maintaining constant pressurizer level at the program value with
Attachment to AEP:NRC:1191 Page 2 the West CCP in service. Manipulation of various valves in the system was required in order to attain consistent pressurizer level control. At 2237 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.511785e-4 months <br />, the East CCP was placed in service and the West CCP placed in standby due to this condition. (The pump was not declared inoperable at that time because, based on observed pump discharge and suction pressure, the ASME Section XI and T/S pressure requirements were satisfied.)
On the morning of July 7, troubleshooting of the pump was performed. The West CCP was started at 1032 hours0.0119 days <br />0.287 hours <br />0.00171 weeks <br />3.92676e-4 months <br />, and shut down quickly due to high vibrations. Another start was made, this time with additional instrumentation. Although discharge pressure was greater than required by the T/S, vibration at the outboard pump bearing was abnormally high. The pump was shut down and declared inoperable. Although during the evening of July 6 the pump appeared to be operable, the decision was made retroactively to conservatively declare the pump inoperable as of 2237 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.511785e-4 months <br /> on July 6, 1993.
At the present time, replacement of the pump internal assembly is in progress. It is currently anticipated that the pump will be returned to operable status no later than 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on July 12.
Therefore, we are requesting 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of time (beyond the original 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by the T/S) that the pump may be inoperable before a shutdown must be initiated, as required by T/S 3.1.2.4 and 3.5.2.
(3) DESCRIPTION OF WHY THE SITUATION COULD NOT BE AVOIDED The pump undergoes ASME Section XI testing, as required by T/S 4 '.5, on a quarterly basis. The suxveillance was last run on May 6, 1993, and indicated no abnormalities. Since there were no indications of problems with the pump prior to those on the night of July 6, the situation could not have been avoided.
(4) EVALUATION OF THE SAFETY SIGNIFICANCE AND POTENTIAL CONSEQUENCES OF THE PROPOSED RELIEF.
The proposed relief only impacts the West CCP. The train associated with the redundant East CCP will remain operable during this period, or the unit will be shutdown in accordance with the requirements of T/S 3.0.3. The severe accident risk of core damage, as determined during the Cook Nuclear Plant Individual Plant Examination project, was calculated to be 6.26E-05 per year. The increase to this core damage frequency that the West CCP represents while unavailable on a one-time basis for 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> beyond the LCO time limit is 1.82E-06 per year. This is only a 2.9% increase to the baseline core damage
Attachment to AEP:NRC:1191 Page 3 frequency. This slight increase is not considered to have significant implications for public health and safety.
(5) DISCUSSION OF COMPENSATORY ACTIONS During the period that the requested Exercise of Enforcement Discretion is in effect, we will not conduct any non-emergency or non T/S-required work activities involving either train of emergency core cooling, including associated emergency electrical distribution. Additionally, we will conduct T/S surveillance 4.5.2.b (ECCS valve lineup verification) and T/S surveillance 4.1.2.2.b (Reactivity Control Systems valve lineup verification) prior to implementation of the Exercise of Enforcement Discretion. These measures will give increased confidence in the operability of the'charging and ECCS systems.
Also, we will not conduct any non-emergency or non T/S-required work activities involving certain equipment that could help to mitigate the consequences of a LOCA or steamline break accident.
The specific equipment involved is the Unit 2 auxiliary feedwater pumps, the cross-tie connecting the chemical and volume control systems of Units 1 and 2, the Unit 2 main steam isolation valves,-
and the Unit 1 CCPs.
(6) DISCUSSION WHICH JUSTIFIES THE DURATION OF THE RELIEF The duration of the requested enforcement discretion is 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.
We believe that during this period we will be able to effect the necessary repairs and perform necessary post-maintenance testing to return the pump to operable status. As discussed under item 4, above, the waiver is not considered to have significant implications for public health and safety.
Should operability of the West CCP be restored prior to expiration of the Exercise of Enforcement Discretion, the Exercise of Enforcement Discretion will be concluded.
(7) THE BASIS FOR CONCLUDING THAT THE REQUEST DOES NOT INVOLVE A SIGNIFICANT HAZARDS CONSIDERATIONS We have evaluated the proposed Exercise of Enforcement Discretion against the criteria of 10 CFR 50.92 regarding significant hazards considerations. Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration does not:
if the change
~ ~
Attachment to AEP:NRC:1191 Page 4 Involve a significant increase in the probability or consequences of an accident previously evaluated,
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated, or Involve a significant reduction in a margin of safety.
Criteria 1 and 2:
The requested waiver of compliance only impacts the amount of time that the West CCP may be inoperable. It does not introduce any new modes of plant operation or physical changes to the plant. This extension will not alter or change initiating aspects of previously evaluated accidents, since this extension will not initiate or create a precursor to a previously evaluated accident. With regard to the consequences of accidents previously evaluated, this extension will have no significant impact because of the redundancy of the East CCP. Therefore, the waiver does not significantly increase the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any previously evaluated.
Criterion 3:
The proposed Exercise of Enforcement Discretion allows continued operation of the unit with a CCP inoperable for a time period in excess of the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> permitted by the T/S. This is a one-time change, requested to allow repair of an inoperable CCP. To allow for the possibility of a failure in one train of a function, the accident analyses only credit one train of charging pumps. The proposed relief only impacts the train involving the West CCP. The train associated with the redundant east pump will remain operable during this period, or the unit will be shut down in accordance with the requirements of T/S 3.0.3. The severe accident risk of core damage, as determined during the Cook Nuclear Plant Individual Plant Examination project, was calculated to be 6.26E-05 per year. The increase to this core damage frequency that the West CCP represents while unavailable on a one-time basis for 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> beyond the LCO time limit is 1.82E-06. This is only a 2.9% increase to the baseline core damage frequency. This slight increase is not considered to have significant implications for public health and safety, or to constitute a significant reduction in a margin of safety.
Attachment to AEP:NRC:1191 Page 5 (8) BASIS FOR CONCLUDING THAT THE REQUEST DOES NOT INVOLVE IRREVERSIBLE ENVIRONMENTAL CONSEQUENCES This proposed Exercise of Enforcement Discretion does not involve a change in the installation or use of the facilities or components located within the restricted areas as defined in 10 CFR 20. Ve have determined that this proposed Exercise of Enforcement Discretion does not involve a significant increase in the amount, or a significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this proposed Exercise of Enforcement Discretion meets the eligibility criteria for categorical, exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with granting of this proposed Exercise of Enforcement Discretion.
Attachment to AEP:NRC:1191 Page 6 BASIS FOR 60 HOURS REQUESTED FOR EXERCISE OF ENFORCEMENT DISCRETION The schedule below was used as the basis for determination of the need for 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of additional allowable outage time to restore the West CCP to operable status.
ACTIVITY ENDPOINT Install Pump Head 7/8 2100 4 hrs.
Center Shaft, 7/9 0700 Prepare Bearing Housings 10 hrs.
Install Seals 7/9 1200 5 hrs.
Reinstall Bearings 7/9 2200 10 hrs.
Finish Assembly, 7/11 1000 Alignment, Sign off clearance 36 hrs.
Pick up clearance, 7/11 1600 Fill & Vent 6 hrs.
Operations Run Surveillance Test, 7/12 0400 Coordinate flow changes for pump curve with Plant Engineering 12 hrs.
Evaluate flow data 7/12 1000 6 hrs.
(Pump operable at this time)