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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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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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Text
RIORITY PACCELERATED 1 RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9409020190 DOC.DATE: 94/08/24 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 P FITZPATRICK,E.E Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T. Document Control Branch (Document Control Desk) R
SUBJECT:
Informs of revision to 900221 ltr in response to RAI re post-fire safe shutdown methodology at util. Installing reflash capability in control rooms is cancelled.
DISTRIBUTION CODE: A006D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR/Licensing Submittal: Fire Protection App R GL-88-12 NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 1 1 HICKMAN,J 2 2 INTERNAL: NRR/DSSA/SPLB 1 1 NUDOCS-ABSTRACT 1 1 OC/LEDC 1 0 OGC/HDS2 1 0 R~FTL 01 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
0 C
U E
NOTE TO ALL"RIDS RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 8
'1 I
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:0692CU Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 REVISION OF PLANS TO INSTALL REFLASH CAPABILITY FOR THE CONTROL ROOM FIRE ANNUNCIATOR PANELS U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: W. T. Russell August 24, 1994
Dear Mr. Russell:
The purpose of this letter is to revise previous information submitted February 21, 1990, (AEP:NRC:0692BT), in response to a September 14, 1989, NRC Request for Additional Information (RAI),
regarding post-fire safe shutdown methodology at Donald C. Cook Nuclear Plant. On page 13, of Attachment 1, of AEP:NRC:0692BT, we committed to install "detection system reflash capability in the control rooms", and indicated that this "modification is being developed with a target completion by December 1991." The commitment was not required by the RAI but, at that time, was believed to be a desirable enhancement.
On December 2, 1991, we submitted AEP:NRC:0692BY, and noted therein that the fire alarm reflash project had to be rescheduled for completion by December 31, 1994, due to the complexity of the project. After extensive review, we have concluded that the cost of installing reflash capability will not have a commensurate safety. benefit, -and may not be technically desirable. This conclusion was based on operator interviews, fire alarm system walkdowns, review of the Fire Probabilistic Risk Assessment (PRA),
review of the Detailed Control Room Design Review (DCRDR),
engineering evaluations of the fire annunciator panels, and a review of fire detection corrective and preventive maintenance procedures. Attachment 1 to this letter provides detailed justification to support cancelling the reflash modification.
QOUA g 9409020190 'F40824 PDR ADOCK 05000315
.F., PDR
Mr. W. T. Russell AEP:NRC:0692CU In addition, this is a Cost Beneficial Licensing Action (CBLA).
The lifetime cost savings associated with this CBLA are approximately $ 2,421,000, as detailed in Attachment 2.
Sincerely, E. E. Fitzpatrick Vice President cad Attachments cc: A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett
ATTACHMENT 1 TO AEP:NRC:0692CU REVISION OF PLANS TO INSTALL REFLASH CAPABILITY FOR THE CONTROL ROOM FIRE ANNUNCIATOR PANELS to AEP:NRC:0692CU Page 1 During a November 1989 meeting with NRR and Region III staff at Cook Nuclear Plant, the maintenance and surveillance of our Technical Specification (T/S) 3/4.7.10, "Fire Related Assemblies,"
was discussed. A miscellaneous issue was discussed regardjng fire alarm system circuit supervision. During this discussi'on, NRC if staff inquired the alarm system had a "reflash" capability. In response to the NRC inquiry, we indicated that reflash capability would be installed.
On February 21, 1990, we submitted AEP:NRC:0692BT, in response to NRC Request for Additional Information regarding post-fire safe shutdown methodology. On page 13 of Attachment 1, we committed to install "detection system reflash capability in the control rooms" and indicated that this "modification is being developed with a target completion by December 1991." On December .2, 1991, we submitted AEP:NRC:0692BY and noted therein that the fire alarm reflash project would be rescheduled for completion by December 31, 1994, due to the complexity of the project.
In accordance with our commitment to install reflash on the control room fire panels, a plant modification (12-PM-1015) was opened. This plant modification was subsequently closed when it was realized that the scope of work was significantly more resource intensive than initially envisioned and would require a corporate (AEPSC) design change. Subsequent reviews and evaluations have now determined that reflash cannot be installed for the fire panels for less than a minimum cost of approximately
$ 2,421,000 (1993 dollars, for both units excluding the simulator).
The fire annunciator panels in the Cook Nuclear Plant control rooms have a simple operating sequence consistent with the rest of the control room annunciator panels. When the input to an annunciator drop changes from normal to abnormal, the drop will begin to flash and sound an audible alarm. The operator acknowledges the alarm by pushing the associated drop (which is also a push button switch) which silences the audible alarm and results in a standing (solid) visual alarm. When the condition clears, the light will flash again, along with an audible signal, until the drop is'epressed.
The Cook Nuclear Plant control room annunciator system was designed to provide plant monitoring functions and to address human factors concerns. This was achieved, in part, by the utilization of shared alarm point inputs (multi-input drops).
This enables each drop to accept multiple process signals to provide necessary information without distracting operators with to AEP:NRC:0692CU Page 2 redundant or "low-level" information. In general, multiple alarm point inputs are logically grouped by system function and/or physical location (e.g., fire protection alarms for all four reactor coolant pumps are grouped together onto one annunciator drop). When the first abnormal condition occurs, the alarm point can return to normal only after all associated input conditions have returned to normal. Subsequent abnormal conditions would not "reflash" that alarm point while a previous abnormal condition still exists.
Cook Nuclear Plant utilizes multi-input: drops in accordance with NUREG-0700 and the AEP system control room design philosophy.
Multi-input: alarms without reflash are used if the quantity, sequence or combination of alarm inputs does not change the priority of the alarm, the identity of the alarm condition is available at a local panel or on a hard copy printout (or status it light), and does not significantly affect the nature of or the time required to implement the initial corrective action in response to the alarm condition.
Unit control room fire annunciator panels consist of 150 drops.
Drop ¹41, labeled FIRE, is a red drop (first priority alarm) and was designed to clearly indicate actuation of fire protection systems. This drop is only energized in conjunction with another drop which identifies the actuating equipment or to signal that the other control room has received their drop ¹41 alarm. Other fire panel drops are either red (first priority alarm) indicating system actuation, amber (second priority) for abnormal conditions, or white (third priority) which also indicate syst: em trouble.
The annunciator response procedures indicate the areas and/or equipment associated with each drop. For multi-input drops which monitor a large number of zones, the procedures require that, if the annunciator or fire detection zone light remains illuminated, then the operator must monitor the status lights at the top of the fire protection panel once per hour (administratively, once per 30 minutes) for other alarms. The status lights tell the operator which fire protection zone has the abnormal condition. The requirement to monitor- the fire panel is reiterated in the "Standing Fire Detection Alarm" data sheet which is used to document and track standing alarms on a 30 minute frequency.
In addition, standing alarms associated with Technical Specification required detectors located outside of containment require hourly fire watch patrols to inspect the affected zone(s).
Detectors located inside containment have different parameter to AEP:NRC:0692CU Page 3 monitoring requirements such as monitoring containment air temperatures. Also, certain drops, such as drop ¹94 "REACTOR COOLANT PUMP FIRE OR ABN," simultaneously annunciate abnormal conditions on their'ssociated system panel. For example, a fire condition illuminating drop ¹94 will have an associated alarm on the reactor coolant pump (RCP) panel (located in the control room) indicating the specific affected RCP.
The control room operators are trained not to tolerate standing alarms and faulted detector circuits are promptly repaired and well maintained under a comprehensive surveillance and maintenance schedule in accordance with Technical Specifications. Standing abnormal alarms are tracked on a daily basis by management and action is taken to keep the number of standing alarms to a minimum.
Plant procedures and Technical Specifications require that fire watches be established for inoperable equipment and systems that could affect the safety of the plant. The utilization of local fire indicating/control panels by fire watch personnel provides added assurance that those areas which are monitored by multi-input drops in the control room are being adequately surveyed to preclude potential masking of abnormal fire protection conditions.
The Detailed Control Room Design Review (DCRDR) examined all multi-input drops and the annunciator response procedures to determine if reflash and/or printout capability would be needed or advantageous. The conclusion of the DCRDR was that no reflash of multi-input alarms was required and that the benefits of reflash would not be cost justified. Irrespective of this conclusion, an effort was made during the DCRDR to address the need to add alarms to the Plant Process Computer (PPC) in lieu of splitting multi-input alarms or installing reflash circuits and, it was concluded that adding alarms to the PPC would not, in general, be of value based on operations procedures and the overall control room annunciator design.
In conclusion, the integrated use of the control room fire panel along with the associated status . lights, the local fire annunciator panels, the annunciator response procedures, and other control room annunciator panels, provides the necessary information to identity different alarm signals associated with multi-input drops. In addition, the comprehensive surveillance to AEP:NRC:0692CU Page 4 and maintenance of detector circuits and the low probability of automatic detection system failure, further supports the conclusion that reflash capability will not have a significant plant safety benefit.
I Based upon these reviews, the installation of ref lash capability for the control room fire annunciator panels clearly will not provide a significant reduction in plant risk. In addition, installation of reflash capability is not required for compliance with 10 CFR Part 50 Appendix R, for licensing commitments pursuant to NFPA compliance, or for compliance with the guidance provided in Appendix A to BTP APCSB 9.5-1 and our response to the BTP dated January 31, 1977.
To support'he above evaluations, we have also reviewed the results of the Individual Plant Examination of External Events (IPEEE) Fire Analysis completed in April 1992. Based on the results of this evaluation, it is concluded that reflash capability will not impact the results of the fire Probabilistic Risk Assessment (PRA). Installation of reflash capability will not reduce the fire induced contribution to core damage frequency for Cook Nuclear Plant.
Finally, in accordance with 10CFR50.59 and the guidance provided in NSAC-125, an unreviewed safety question determination was performed. It was concluded, therein, that cancellation of the reflash modification will not constitute an unreviewed safety question per 10CFR50.59(a)(2), nor does it constitute a significant hazard to the health and safety of the public.
ATTACHMENT 2 TO AEP'NRC'0692CU COST BENEFICIAL LICENSING ACTION (CBLA)
REVISION OF PLANS TO INSTALL REFLASH CAPABILITY FOR THE CONTROL ROOM FIRE ANNUNCIATOR PANELS
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I Attachment 2 to AEP:NRC:0692CU Page 1 Regulatory Requirement:
A commitment was made in AEP:NRC:0692BT and AEP:NRC:0692BY, to install reflash capability for the control room fire annunciator panels. I Effect of Requirement:
Installation of reflash capability for the control room fire annunciator panels will make these panels inconsistent with the other control room panels, and may result in a human factors concern. Additionally, reflash capability will not result in a significant reduction of plant fire risk.
Rationale for Regulatory Change:
The availability of fire protection defense-in-depth measures ensures plant fire safety. These defense measures include the widespread use of fire detection and fixed suppression systems throughout the plant, the availability of manual fire suppression equipment, e.g., portable extinguishers and hose stations, the existence of a trained plant fire brigade, and the generally low fire loadings present throughout the plant.
Based on the justification provided in Attachment 1 and defense-in-depth strategies, installation of reflash will not provide a reduction in plant fire risk commensurate with the cost.
Approximate Cost of Requirement:
The minimum cost to install reflash capability for the control room fire panels is $ 2,421,000 (1993 dollars). This cost does not include any software changes, seismic supports for cable/conduit routing, modifications to the simulator, or replacement of window drop boxes.
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