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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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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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ACCEI ERATO)DOCUMENT DISTRIBUTION SYSTEM REGULAT~INFORMATION DISTRIBUTIO~STEM (RIDS)'ACCESSION NBR:9302220199 DOC.DATE: 93/02/12 NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
Indiana Michigan Power Co.(formerly Indiana 8 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R MURLEYPT.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Informs of plans to remove alarming capabilities of saturation margin monitors in approx 90 days,per previous submittals re NUREG-0578,NUREG-0737 a GL 82-28.Justification-for removal of alarming capability encl.DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR r ENCL (SIZE: C TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33)NOTES: D RECIPIENT ID CODE/NAME PD3-1 LA DEANPW INTERNAL: NR~RD~LP/LHFBl1~ILE 01 EXTERNAL PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD OC/LFMB RES/DSIR/EIB NSIC COPIES LTTR ENCL 1 1 1 0 1 1 1 1 D D S A D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM P1-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!D TOTAL', NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9
~II Indiana Michigan Power Company P.O.Box 16631 Coiumbus, OH 43216 AEP:NRC: 1183 Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 JUSTIFICATION FOR REMOVAL OF THE B&W SATURATION MARGIN MONITOR ALARM AND THE PLANT PROCESS COMPUTER SATURATION MARGIN MONITOR PROGRAM ALARM U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: T.E.Murley February 12, 1993
Dear Dr.Murley:
In previous submittals concerning NUREG-0578, NUREG-0737 and Generic Letter 82-28, we mentioned that our B&W Saturation Margin Monitor and the Plant Process Computer Saturation Margin Monitor Program would have alarms that would be annunciated once subcooling margin dropped below 33'F (the set point was revised to 29'F in 1984).In the past few years, these alarms have become a nuisance since normal power operation has some core locations with less than 29'F subcooling.
They are standing alarms and provide no useful information to the reactor operators.
There is no regulatory, technical specification, or UFSAR requirement for these alarms.These standing alarms could distract the operators and serve no purpose.Therefore, we intend to remove the alarming capability of the saturation margin monitors in Donald C.Cook Unit 1 and Unit 2 in approximately 90 days, unless we are informed otherwise by your staff.IBOI06 9302220i99 9302i2 PDR ADOCK 050003i5 I PDR jrt~)~E C Dr.T.E.Murley Page 2 AEP:NRC:1183 On February 2, 1993, a member of your staff, Mr.William M.Dean, and our Licensing Section Manager, Mr.Douglas H.Malin, discussed the possibility of removing the B&W Saturation Meter Alarm and the Plant Process Computer Saturation Margin Program Alarm.At that time, Mr.Dean requested that we submit to the staff our justification for removing the alarms.Attachment Number 1 to this letter provides the justification for removal of the alarms, as requested by Mr.Dean.Attachment Number 2 includes the applicable correspondence we had with the staff concerning NUREG-0578, NUREG-0737 and Generic Letter 82-28.Sincerely, E'g~f)E.E.Fitzpatrick Vice President dr Attachments CC: A.A.Blind-Bridgman J.R.Padgett G.Charnoff A.B.Davis-Region III NRC Resident Inspector-Bridgman NFEM Section Chief Dr.T.E.Murley Page 3 AEP:NRC: 1183 bc: S.J.Brewer D.H.Malin/K.J.Toth M.L.Horvath-Bridgman J.B.Shinnock W.G.Smith, Jr.W.M.Dean, NRC-Washington, D.C.AEP:NRC:1183 DC-N-6015.1 Attachment No.1 to AEP:NRC:1183 JUSTIFICATION FOR REMOVAL OF THE B&W SATURATION MARGIN MONITOR ALARM AND THE PLANT PROCESS COMPUTER SATURATION MARGIN MONITOR PROGRAM ALARM Attachment No.1 to AE.C:1183 Page 1 JUSTIFICATION FOR REMOVAL OF THE B&W SATURATION MARGIN MONITOR ALARM AND THE PLANT PROCESS COMPUTER SATURATION MARGIN MONITOR PROGRAM ALARM INTR D TI As a result of the TMI accident, NUREG-0587 was issued.The NUREG provided lessons learned and short-term recommendations.
One of the recommendations was to install instrumentation to monitor inadequate core cooling.One instrument that was determined capable of.providing relevant information was a saturation margin monitor.Prior to January 31, 1980, a saturation margin computer program was installed on the PRODAC-250 plant process computer (PPC).A few months later, a dedicated digital saturation margin monitor, manufactured by Babcock and Wilcox (B&W), was installed.
Both of the saturation margin monitors provided alarming capabilities to alert the operator if subcooling of the reactor coolant system dropped below a given set point.In the past, the saturation margin monitors'larms had given us only a few problems.For example, in 1984 the set point was recalculated and reduced to 29'F.This kept the alarms cleared for many years.With the current concerns of reactor vessel embrittlement, our current core designs have incorporated low leakage loading patterns (LLLP).An expected result of the LLLP was that some fuel assemblies in the center of the core would have hotter core exit temperatures.
Our current Unit 2 Cycle 9 core design has a few core exit temperatures yielding approximately 24'F margin of subcooling.
Thus, the current set point of 29'F is exceeded and the alarms are annunciated (standing alarm).To relieve the operators of the standing alarms, the following options have been considered:
reduce the set point again, abandon the LLLP to achieve a more"flat" power distribution, monitor only"cold" incore thermocouples, or remove the saturation margin monitors'larming capability.
The most reasonable of these options is to remove the alarming capability.
We believe that since the alarms currently provide the operator with no useful information, they should be removed altogether.
This is justifiable since no credit is taken for the alarm in any of the plant's emergency operating procedures, nor is it mentioned in the Technical Specifications or UFSAR.
~~
Attachment No.1 to AE.C:1183 Page 2 BA K R-RE AT RY As a result of NUREG-0578, item 2.1.3.b,"Instrumentation for Inadequate Core Cooling (Saturation Meter)", several actions took place at Donald C.Cook Nuclear Plant to comply with the recommendations:
1.Curves of saturation temperature versus reactor coolant pressure were provided to the operators.
2.A computer program was written for the Plant Process Computer (PPC)to monitor saturation margin.3.A dedicated saturation margin monitor was installed.
These actions were documented in the following submittals:
AEP:NRC:00334B, March 10, 1980, AEP:NRC:00334, January 18, 1980 (which supplemented the following submittals), AEP:NRC:00253C, December 26, 1979, AEP:NRC:00253B, December 19, 1979, AEP:NRC:00253A, November 26, 1979, and AEP:NRC:00253, October 24, 1979.On March 20, 1980, the staff issued a safety evaluation report (SER), referencing the above submittals, stating that actions 2 and 3 satisfied the short term lessons learned requirements for NUREG-0578, item 2.1.3.b.In response to Generic Letter 82-28, which refers to NUREG-0737 in regard to saturation margin monitors, we submitted two letters AEP:NRC:0761, dated March 11, 1983, and AEP:NRC:0761A, dated June 22, 1983.On December 19, 1983, the staff issued an SER, with an initial review of our responses.
In the SER, our saturation margin monitors were described as functionally acceptable.(The reason the SER was not final was that more information was required by the staff to complete the SER;however, the saturation margin monitors capabilities were not in question).
The submittals refered to in the 1979/1980 time frame made reference to the PPC saturation margin monitor alarming features.The June 22, 1983 submittal made reference to the B&W and PPC saturation margin monitor alarming features.As stated, information on the alarms features was provided to the staff;however, these alarms were not regulatory requirements.
For the staff s convenience, the referenced submittals have been included in Attachment Number 2.Please note that in the March 20, 1980 SER, a few other submittals were referenced, but they had nothing to do with the saturation margin monitor.Therefore, they were not included in Attachment Number 2.
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I Attachment No.1 to AE.C:1183 Page 3 BA K R PER ATI THE A ATI MAR M NITOR In 1984, the problem of standing alarms existed on the saturation margin monitors.The problem was eventually resolved by recalculating the set point to 29'F.(The set point calculation is based on the maximum error the saturation margin monitor could see during accident conditions.)
This provided adequate margin until 1990, when Unit 2 Cycle 8 was started up.At that time, we had switched to a new fuel vendor who provided us with a LLLP.As result of the LLLP, more of the reactor power was in the center of the core.As expected, this caused some fuel assemblies to have higher relative powers.Thus, creating some hotter core exit temperatures yielding subcooling margins of less the 29'F, and causing the saturation margin monitors'tanding alarms.As mentioned in the introduction, the foHowing options to eliminate the standing alarm were considered:
2.3.4.reduce the set point again, abandon the LLLP to achieve a more"flat" power distribution, monitor only"cold" incore thermocouples, and remove the saturation margin monitors alarming capability.
The first three options were rejected for the following reasons: Reducing the set point could only be justified by our experience-based knowledge that the incore thermocouples are accurate to approximately
+5'F (based on measured power distribution and calculating the expected exit temperatures).
However, the saturation margin monitor is for post accident monitoring and we have no basis to remove the error tolerances built into the set point for accident conditions.
2.3.The benefits of the LLLP for reducing vessel embrittlement outweighs the benefits of having the alarms available, for which credit is not taken and are not required.Monitoring only"cold" incore thermocouples would only defeat the purpose of'he saturation margin monitor.During an accident, the first core locations that would most likely lose their saturation margin, or boil, would be the ones with fuel assemblies with the highest decay heat.These assemblies would typically be those with the highest core exit temperatures.
Therefore, monitoring"cold" assemblies would not be prudent.Thus, the only reasonable solution to clear the standing alarms is to remove the alarming capabilities of the saturation margin monitors.
~\C 1 0 Attachment No.1 to AE.C:1183 Page 4 REVIEW A N TAKE TIFI ATI NUREG-0578, NUREG 0737 and Generic Letter 82-18 were reviewed to determine if any requirements existed committing us to install alarms on our saturation margin monitors.NUREG-0578 and Generic Letter 82-18 make no statements regarding saturation margin monitor alarms.The only reference of alarms was found in NUREG-0737.
In Section II.F.2, INSTRUMENTATION FOR DETECTION OF INADEQUATE CORE COOLING, Clarification 10, the following is stated: "The types and location of displays and alarms should be determined by performing a human-factors analysis taking into consideration: (a)the use of this information by an operat'or during both normal and abnormal plant conditions, (b)'ntegration into emergency procedures, (c)integration into operator training, and (d)other alarms during emergency and need for prioritization of alarms." Clarification 10 reveals that NUIT-0737 allowed the licensee to consider what would provide the best information of inadequate core cooling to the operator.At the time we installed the saturation margin monitors, the alarms were a viable method for initially warning the operators of potential inadequate core cooling.Considering the changes in core designs over the years (LLLP), the alarms associated with the saturation margin monitors are no longer effective and do not assist the operator in assessing inadequate core cooling.The reason is that we have a standing alarm during normal operation.
Thus from a human-factors standpoint, the operators are better positioned to identify inadequate core cooling by relying on saturation margin monitor readouts ('F margin)than seeing an alarm that is typically annunciating.
In fact, in the plant's emergency operating procedures, no credit is taken for the alarms and the operators are instructed to check the amount of subcooling margin available from the B&W saturation margin monitor or safety parameter display system (on the technical support center computer display in the control room).The UFSAR and Technical Specifications were reviewed for any reference to the alarms on the saturation margin monitors.The saturation margin monitors are referenced, but the alarms are not mentioned.
NCLUSION Even though the alarms were discussed in our submittals concerning inadequate core cooling instrumentation, there was no regulatory requirement to install alarms on saturation margin monitors.Since the alarms are on record from our previous submittals, we are providing this submittal showing adequate justification to remove both of the saturation margin monitors'larming capabilities.
This will be done in approximately 90 days.The alarms are a nuisance and provide no useful information to the reactor operator.The health and safety of the public will not be affected by removing the saturation margin monitors'larming capabilities.