Similar Documents at Cook |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999 Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21 IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20217D9241999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML20196K5961999-06-30030 June 1999 Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021 ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML20207A9201999-05-21021 May 1999 Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML20205P0591999-04-14014 April 1999 Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed ML17325B5141999-03-30030 March 1999 Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML17325B5191999-03-29029 March 1999 Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed ML20204F6401999-03-19019 March 1999 Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage ML17325B4751999-03-18018 March 1999 Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed ML17325B4721999-03-18018 March 1999 Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal ML17325B4641999-03-17017 March 1999 Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation 1999-09-30
[Table view] |
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CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION .'TBR:9803030313 DOC.DATE: 98/02/23 NOTARIZED: YES FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M DOCKET 05000315 I
50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co.
'RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC 980113 ltr re violations noted in'insp repts 50-315/97-18 & 50-316/97-18.Corrective actions:review of current practices was conducted to ensure that proper controls were in place to prevent recurrence.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response E NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG,J 1 1 INTERNAL: AEOD/SPD/RAB 1 1 AEOD 1 1 DEDRO 1 1 CENTER 1 1 NRR/DRCH/HHFB 1 1 CB 1 1 NRR/DRPM/PERB 1 1 NUDOCS -ABSTRACT 1 1 OE DIR 1 1 OGC/HDS2 1 1 RGN3 FILE 01 1 1 XTERNAL: LITCO BRYCE,J H 1 1 NOAC 1 1 D NRC PDR 1 1 NUDOCS FULLTEXT 1 1 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 17 ENCL 17
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Indiana Michigan Power Company 500 Circle 0:ive Buchanan. Ml 49107 1395 INDIANA NICHIGAN POWER February 23, 1998 AEP: NRC: 1260 J 10 CFR 2.201 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-P1-17 Washington, D.C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and 2 REPLY TO NOTICE OF VIOLATION NRC INSPECTION REPORT NO. 50-315/97018(DRP);
NO. 50-316/97018 (DRP)
This letter is in response to a letter from Geoffrey E. Grant, dated January 13, 1998, that transmitted a notice of violation.
The notice of violation contained one violation of NRC requirements identified during an inspection conducted by Messrs. B. Bartlett, B. Fuller, J. Maynen and E. Schweibinz on September 26, 1997, through November 7, 1997. The violation is associated with plant procedures that did not meet the requirements of 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings."
Our reply to the violation is provided in the attachment to this letter.
The letter from Mr. Grant, dated January 13, 1998, was not received in our offices until January 21, 1998. This was discussed with Mr. Bruce Burgess of Region III on February 4, 1998. He agreed to extend the due date from February 12, 1998, to February 23, 1998.
Sincerely, E. E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME T gg DAY OF 1998 JAI;CE M. BICl(EBS Nolary pr.hc, Bemen Coaly. MI My Commissiaa Expiree Feb. 18, 2C01 Notary ubls.c My Commission Expires
/vlb i/
Attachments x-(
'F803030313 980223 'J'IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII PDR ADOCK 05000315 8 PDR
0 U.S. Nuclear Regulatory Commission AEP: NRC: 12608 Page 2 J. R. Sampson A. B. Beach MDEQ - DW & RPD NRC Resident Inspector Z. A. Abramson
ATTACHMENT TO AEP:NRC: 1260J REPLY TO NOTZCE OF VZOLATZON NRC ZNSPECTZON REPORT NO. 50-315/97018(DRP);
NO. 50-316/97018(DRP)
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Attachment to AEP:NRC:1260J Page 1 During an NRC inspection conducted from September 26, 1997, to November 7, 1997, one violation of NRC requirements'as identified.
In accordance with the "General Statement of Policy and Procedure:
for NRC Enforcement Actions", NUREG-1600, the violation is stated below, followed by our response. We also include a general response to the issue of providing quality procedures.
NRC Violation
."10 CRR 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," requires, in part, that activities affecting quality be prescribed by procedures of a type appropriate to the circumstances and be accomplished in accordance with these procedures.
Contrary to the above, On October 17, 1997, the inspectors identified that procedure 02-OHP 4021.082.003, Revision 3, "Feeding 600 Volt Buses Through Bus Tie Breakers," was not appropriate to the circumstances circumstances, in that.
an excessive it allowed, under load to be placed on the certain emergency diesel generators.
B. On October 17, 1997, the inspectors identified that procedure 02-OHP 4021.082.013', Revision 2, "Isolating, Transferring and Restoring a 250 VDC Load," was not appropriate to the circumstances in that it failed to contain adequate guidance to ensure that battery cross-ties would not be overloaded.
C. On October 22, 1997, the inspectors identified that Emergency Operating Procedure E-O, 01[02] -OHP 4023.E-O, Revision 14 [12], "Reactor Trip or Safety Injection," was not appropriate to the circumstances in that 12 examples were identified where the set point for a reactor trip or safety injection as stated in E-0 was not as stated in the plant set point document.
This is a Severity Level ZV violation (Supplement X)."
Res onse to Violation Item A
- 1. Admission or Denial of the Alle ed Violation We admit to the violation as cited in the NRC notice of violation.
Reason for Violation The reason for this item of the violation is insufficient, documentation of the basis for the values used. Had the basis for the values selected been documented and controlled in a more readily retrievable fashion, it would have, been easier to determine whether adequate protection of the 600 VAC bus was being provided by the procedure. During the investigation into this condition, a memo requesting the addition of overcurrent limits in the procedure was identified. However, insufficient information was available to show how the limits used were selected.
Attachment to AEP:NRC:1260J Page 2 Corrective Action Taken and Results Achieved An engineering calculation, PS-600VD-012, was performed on October 30, 1997; and it was determined that the maximum continuous loading, whether or not the bus is cross-tied, is 225 amps for the essential (ESS) buses and 140 amps for balance of plant buses. Another engineering calculation, PS-EDGL-006, demonstrated that procedures were not adequate to assure the emergency diesel generator (EDG) continuous rating would not be exceeded had operators initiated cross-tie operation of the 600V ESS buses subsequent to a blackout (BO), a BO with safety injection (SZ), or a BO 'with containment spray. Based on this, engineering direction was provided to control the EDG loading prior to cross-tying 600V ESS buses, and to not exceed the EDG continuous load ratings while cross-tied.'he above information was provided to
'operations through technical direction memo (TDM) ENTDM 97-0126, "600V Bus Cross-Tie Procedure OHP 4021.082.003 Current Limitations."
For unit 1, 01-OHP 4021.082.003, revision 6, "Feeding 600 Volt Buses Through Bus Tie Breaker", was made effective on November 17, 1997, to correct the identified issue and incorporate information contained in ENTDM 97-0126. For unit 2, 02-OHP 4021.082.003, revision 4, "Feeding 600 Volt Buses Through Bus Tie Breaker", was made effective on November 2, 1997, to correct the identified issue and incorporate information contained in ENTDM 97-0126.
10 CFR 50.59 screenings performed on both procedures determined that no unreviewed safety question existed.
Corrective Actions to Avoid Further Violations AEPNG procedure 227200-STG-2400-02, "Technical Direction",
provides requirements for providing technical direction to ensure that information is accurate, based on sound engineering principles, and properly communicated and documented. This procedure was not in effect when the operating procedure at issue was incorrectly revised. The AEPNG procedure establishes appropriate reviews, approvals, and documentation to support correct transfer of technical information.
The current revision of OPM.002, revision 4, "Operations Department Procedure Review Manual", requires a system engineer review of procedure revisions. This was not in place at the time of the event. The system engineer review provides additional assurance of plant and system compatibility, and that the procedure is technically correct.
TDM ENTDM 97-0126, "600V Bus Cross-Tie Procedure OHP 4021.082.003 Current Limitations", has been placed in the procedures reference section to maintain a record of the requirement with the procedure.
Date When Full Com liance Will Be Achieved Full compliance for this item was achieved on November 17, 1997, following revision to both units'rocedures.
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Attachment to AEP:NRC:1260J Page 3 Res onse to Violation Item B Admission or Denial of the Alle ed Violation We admit to the violation as cited in the NRC notice of violation.
- 2. Reason for Violation A review'of historical information relative to the procedure did not reveal why guidance had not been incorporated into the procedure to prevent overloading a battery during a cross-tie condition. We believe that guidance was not provided because the procedure for cross-tying batteries is applicable only during modes 5 and 6. In modes 5 or 6, certain components that are fed from the DC busses are assumed not to operate. Review has shown that these assumptions are reasonable and 'onsistent with plant operating history. The components assumed not to operate are associated with main turbine and main feedwater support systems not normally used in modes 5 and 6.
Corrective Action Taken and Results Achieved A technical direction memo (TDM) was issued on October 13, 1997, relative to the unit 2 AB/CD cross-tie operation. The TDM contained the guidance for the 2AB and 2CD battery to be cross-tied in modes 5 and 6. A similar TDM, ENTDM 97-0133, "Battery 1AB/CD Cross-tie", was issued for the 1AB and 1CD battery.
For unit 1, 01-OHP 4021.082.013, revision 6, "Isolating, Transferring and Restoring a 250 VDC Battery Load", was made effective on December 12, 1997, to provide guidance from ENTDM 97-0133 to ensure that battery cross-tying during modes 5 and 6 would not result in an overload condition. For unit 2, 02-OHP 4021.082.013, revision 2, change sheet "Isolating, Transferring and Restoring a 250 VDC Battery Load", was made effective on October 23, 1997, to .provide guidance from the October 13, 1997, TDM to ensure that battery cross-tying during modes 5 and 6 would not result in an overload condition.
4, Corrective Actions to Avoid Further Violations A review of current practices was conducted to ensure proper controls are in place to prevent recurrence. Per guidance provided in OPM.002, revision 4, "Operations Department Procedure Review Manual", a system engineer review is required to provide assurance of plant and system compatibility for the procedure and determine if the procedure is technically correct as written.
For unit 1, ENTDM 97-0133, "Battery 1AB/CD Cross-Tie", dated December 4, 1997, was placed in the procedure reference section to maintain a record of the requirement along with the procedure. For unit 2, the October 13, 1997, TDM, "Battery 2AB/CD Cross-Tie Operation", was placed in the procedure's reference section to maintain record of the requirement with the procedure.
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Attachment to AEP:NRC:1260J Page 4 Date When Full Com liance Will Be Achieved Full compliance for this item was achieved on December 12, 1997, following revision to both units'rocedures.
Res onse to Violation Item C Admission or Denial of the Alle ed Violation We admit to the violation as cited in the: NRC notice of violation.
Reason for Violation The reason for this violation was a lack of guidance provided for the review and evaluation of the affected setpoint changes. PMP 6065. ISP.001, "Plant Instrument Setpoint Control Program", requires completed change packages be sent to applicable plant departments for procedure impact review.
When operations received a setpoint change, the change was evaluated for significance, and if considered a significant change, the appropriate procedures would be changed. If the change was considered insignificant, procedure changes would not be made. Insufficient guidance was provided to make this determination. Based on this, we believe that when op'erations was notified of the setpoint changes, the changes were considered insignificant and no procedure changes were made.
- 3. Corrective Action Taken and Results Achieved The plant setpoint document (PSPD) was reviewed against the emergency operating procedures (EOPs) setpoints, and the applicable EOPs were revised to reflect the setpoints in the PSPD.
For unit 1, 01-OHP 4023.E-O, revision 14, change sheet 3, "Reactor Trip or Safety Injection", was made effective on October 30, 1997, to obtain'consistency between the procedure and the PSPD. For unit 2, 02-OHP'023.E-O, revision 12, change sheet 3, "Reactor Trip or Safety Injection", was made effective on October 30, 1997, to obtain consistency between the procedure and the PSPD.
Corrective Actions to Avoid Further Violations The operations department procedure revision manual, OPM.001, attachment 1, was revised to clarify the use of setpoints listed in the operations department procedures. The operations procedure manual now provides specific actions for the review of setpoint changes.
Date When Full Com liance Will Be Achieved Full compliance for this item was obtained on October 30, 1997, following revision to both units' procedures.
0 Attachment to AEP:NRC:1260J Page 5 General Res onse to Violation The following describes additional actions taken to provide additional assurance of conformance and to avoid further violations on a broad basis.
Additional Action P Additional action relative to other system/train cross-tying was performed in response to a single failure concern identified during the 1997 architect engineering design inspection. We performed a review of other safety systems with cross-tie capabilities, either between trains or between units, to provide reasonable assurance that single failure criteria have been appropriately considered and that procedures allowing the use of the cross-ties have been properly evaluated. Systems reviewed were:
Electrical Distribution Systems
~ 250 VDC
~ 480 VAC
~ 600 VAC Auxiliary Feedwater System Essential Service Water System Chemical and Volume Control System The review confirmed that the systems were operable when cross-tied in accordance with existing procedures.
- 2. Additional Actions to Avoid Further Violations Additional actions being taken to avoid further violations of a similar nature include the following:
Operations Department Procedure Upgrade Program Design Basis Reconstitution Project These actions have been described in previous docketed correspondence. A summary of each is provided below.
0 erations De artment Procedure U rade Pro ram The principal objective of the operations department procedure upgrade project is to provide high quality, usable procedures to improve Cook Nuclear Plant unit availability and regulatory performance.
During the NRC operational support team inspection (OSTI),
the operations department committed to a program to upgrade the normal operating procedures and annunciator response procedures. Prior to the OSTZ, weaknesses had been identified related to procedure quality and usability by the 1996 systematic assessment of license performance, and the 1996 ZNPO evaluation and assessment.
Desi n Basis Reconstitution Pro ect The purpose of the design basis reconstitution project includes the following:
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Attachment to AEP:NRC: 1260J Page 6 to assure an adequate understanding of, and control over, the plant's design and licensing basis requirements; and to provide assurance that these requirements are being implemented correctly, both in plant design and in the procedures that govern the plant's operation and maintenance.
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