Similar Documents at Cook |
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999 Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21 IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20217D9241999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML20196K5961999-06-30030 June 1999 Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021 ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal 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] Category:UTILITY TO NRC
MONTHYEARML17328A4481990-09-21021 September 1990 Requests Withdrawal of Mode 6 Proposed Tech Spec Change Since Issue Currently Being Addressed by New STSs ML17328A4331990-08-27027 August 1990 Informs of Preliminary Assessment of 900713 Electrical Contact Accident at Facility.Investigation Concludes That No Safety Rules Violated ML17328A4001990-08-24024 August 1990 Responds to 900725 Ltr Re Commitments Made in Response to Generic Ltr 88-14 on Instrument Air Supply Problems Affecting safety-related Equipment.Simulator Training to Be Provided as Stated ML17334B3781990-08-24024 August 1990 Forwards Info to Certify Plant Simulator Facility.Results of Evaluation of Dual Unit Simulation Facilities Demonstrate That Plant Simulator Performance Compares Favorably W/Units ML17328A4231990-08-21021 August 1990 Forwards Under Separate Cover,Semiannual Radioactive Effluent Release Rept for Jan-June 1990 ML17328A3901990-08-17017 August 1990 Responds to NRC 900720 Ltr Re Violations Noted in Onsite Audit of Spds.Corrective Actions:Apparent Disparity in Selection of Reactor Trip & Sys Capacity or Anticipatory Values Rectified ML17328A3891990-08-15015 August 1990 Forwards Performance Data Sheets for Plant fitness-for-duty Program for Period Jan-June 1990,per 10CFR26.Encl Includes Statistics on Various Categories of Testing,Substances Tested for & cut-off Levels Used ML17328A3571990-08-0202 August 1990 Responds to Open Items in Safety Evaluation of Util Response to Unresolved Issues on post-fire Safe Shutdown Methodology. Open Items 1 & 21 Will Be Closed by Implementing Plant Procedures Providing Equivalent Degree of Protection ML17328A3431990-07-23023 July 1990 Requests Withdrawal of 890830 Proposed Tech Spec Changes Re Sections 3.0 & 4.0.Util Will Resubmit Generic Ltr 87-09 Recommended Improvement Items on Case by Case Basis ML17328A3421990-07-23023 July 1990 Provides Results of Offsite Dose Calculation for Reactor Coolant Pump Locked Rotor Event for Facility Cycle 8.Util Identified Previously Issued SERs Addressing Short Term Containment Analysis & LOCA Containment Integrity ML20055G7551990-07-18018 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-315/90-10 & 50-316/90-10.Corrective Actions:Required Review Performed & Updated Procedure 12 Mhp 5021.019.001 Revised & Issued ML17328A3191990-07-12012 July 1990 Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Electrical Testing Techniques Improved & Surveillance Procedures for Feedwater Pumps Will Be Rewritten ML17328A3181990-07-0909 July 1990 Responds to Generic Ltr 90-03,Suppl 1, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' Licensee Will Contact safety-related Vendors on Annual Basis ML17328A3111990-07-0303 July 1990 Provides Certification of Funding Plan for Decommissioning of Plant,Per 10CFR50.33 & 50.75 ML17328A2961990-06-25025 June 1990 Forwards Response to Generic Ltr 90-04 Re Closeout of Generic Safety Issues.Util Supports Concern & Desire to Close long-standing Generic Safety Issues ML17328A2921990-06-22022 June 1990 Forwards WCAP-12483, Analysis of Capsule U from American Electric Power Co DC Cook Unit 1 Reactor Vessel Radiation Surveillance Program. ML20044A3521990-06-22022 June 1990 Submits Info Re Sensitivity Study Performed on Number of Fuel Axial Intervals,Per Topical Rept, American Electric Power Reactor Core Thermal-Hydraulic Analysis Using Cobra III-C/MIT-2 Computer Code. ML17328A2821990-06-15015 June 1990 Submits Ltr Re Proposed Control Room Habitability Tech Spec Changes & Supporting Analyses,Per 900521 Discussion.Revised Calculations of Control Room Thyroid Doses Will Be Submitted within 60 Days of Receipt of Proposed Generic Ltr ML17328A2741990-06-12012 June 1990 Submits Followup,Per 900205 & 0308 Ltrs & Provides Update Re Inoperable Fire Barrier.Fire Seal Repaired & Restored to Operability on 900419 ML17328A2551990-06-0505 June 1990 Forwards Addl Info Re Util 900126 Revised Response to NRC Bulletin 88-002,per NRC 900509 Request ML17328A7361990-06-0101 June 1990 Forwards Addl Info Re 890825 & 1212 Applications for Amends to Licenses DPR-58 & DPR-74,per Request.Amends Make Changes to Administrative Controls ML17328A7331990-05-29029 May 1990 Forwards Nonproprietary WCAP-12577 & Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument... Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Per 900419 Commitment ML17328A7321990-05-24024 May 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 Series B or D or Model 1154 Transmitters Installed at Facility.Transmitters Purchased as commercial-grade Units ML17328A6991990-05-0909 May 1990 Provides Suppl to 900103 Response,Certifying That Fitness for Duty Program Implemented at Plant.Change Also Clarifies When More Stringent cut-off Levels Adopted at Plant Program Apply ML17328A7001990-05-0909 May 1990 Responds to NRC 900406 Ltr Re Inadequacies of Spds,Per Audit on 900221-22.Corrective Actions:Software Mod Will Prevent User from Accessing Displays Other than Iconic Displays from SPDS Dedicated Terminal ML17328A7071990-05-0707 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept Mar 1990 for Donald C Cook Nuclear Plant Unit 1 ML17328A7031990-05-0707 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for DC Cook Nuclear Plant Unit 2 ML17328A6951990-04-30030 April 1990 Certifies That Training Programs for Initial Licensing & Requalification Training of Operators & Senior Operators at Plant Accredited by Inpo,Per Generic Ltr 87-07 ML17328A6861990-04-30030 April 1990 Forwards Annual Environ Operating Rept,Jan-Dec 1989, & DC Cook Nuclear Plant Units 1 & 2 Operational Radiological Environ Monitoring Program 1989 Rept Jan-Dec 1989. ML17328A6801990-04-23023 April 1990 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Study Planned to Evaluate Alternative Actions to Be Taken for Protecting RHR Pumps ML17328A6771990-04-23023 April 1990 Forwards DC Cook Nuclear Plant 1990 Annual Emergency Preparedness Exercise. Exercise Scope & Objectives & Detailed Scenario Documentation Encl ML17334B3641990-04-11011 April 1990 Responds to NRC 900301 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Reliability Centered Maint Program Initiated ML17328A6601990-04-11011 April 1990 Forwards Updated QA Program Description for Cook Nuclear Plant, Incorporating Editorial,Organizational & Position Title Changes ML17328A6551990-04-0909 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-316/90-08.Corrective Actions:Procedure for Steam Generator Stop Valve Operability Test Revised to Require That MSIV Be Declared Inoperable After Failing Stroke Test ML17334B3601990-04-0606 April 1990 Forwards Revised Figures for Loss of Load Event Previously Submitted in Attachment 4,App B of Vantage 5 Reload Transition Safety Rept Supplied by Westinghouse in Jan 1990. Update Is Editorial in Nature ML17334B3621990-04-0606 April 1990 Forwards 1989 Annual Rept & Projected Cash Flow ML17328A6341990-03-30030 March 1990 Forwards Application for Renewal of Plant NPDES Permit,For Info,Per Section 3.2 of App B to Plant Tech Specs.W/O Encl ML17328A6331990-03-30030 March 1990 Responds to NUMARC 900104 Request for Addl Info Re Station Blackout Submittals.Target Reliability for Emergency Diesel Generator of 0.0975 Established for 4 H ac-independent Coping Category Will Be Maintained ML17328A6321990-03-30030 March 1990 Forwards Response to Generic Ltr 90-01, NRC Regulatory Impact Survey. Util Ack Recommendation by NUMARC ML17328A6221990-03-27027 March 1990 Responds to 900226 Ltr Transmitting Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000. Corrective Actions:Flow Retention Circuitry Setpoints Set to Compensate for Missized Process Flow Orifice ML17328A6191990-03-27027 March 1990 Forwards Payment in Amount of $75,000 for Civil Penalty Imposed Through Notice of Violation Issued in Insp Rept 50-316/89-02 on 891016-20,24-26 & 1204.Response to Violation & Corrective Actions Provided in Separate Submittal ML17328A6161990-03-20020 March 1990 Responds to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs (USI A-47).Both Units Have Steam Overfill Protection Sys That Would Automatically Prevent Water Carryover Into Steam Lines If Control Sys Failed ML17328A6121990-03-13013 March 1990 Forwards Monthly Performance Monitoring Rept,Jan 1990. ML17325B3901990-03-0606 March 1990 Forwards Annual Rept to NRC Per 10CFR50.54(W)(2) Re Nuclear Property Insurance ML17325B3921990-03-0606 March 1990 Modifies Application for Amend to License DPR-74 Re Cycle 8, Per 900228 Telcon ML17325B3781990-02-28028 February 1990 Forwards Response to NRC Info Notice 89-056 Re Questionable Certification of Matl Supplied to Dod by Nuclear Suppliers. Matl Capable of Performing Design Function & Acceptable for Continued Use ML17328A5971990-02-27027 February 1990 Withdraws 890203 Application for Amend to License DPR-74, Modifying Tech Spec Table 3.2-1 Re DNB Parameters to Express RCS Flow Rate on Volumetric Rather than Mass Basis ML17334B3511990-02-22022 February 1990 Submits Annual Rept of Changes to or Errors in Acceptable LOCA Evaluation Models or Application of Models for Plants. Wflash Analyses Will Be Superceded by Notrump Analyses for Unit 2,Cycle 8 Reload ML17328A5881990-02-21021 February 1990 Responds to NRC 890914 Request for Addl Info Re Safe Shutdown Methodology.App R Fire Barriers Being Maintained & Surveilled Under 3/4.7.10 for Units 1 & 2 ML17328A5861990-02-16016 February 1990 Provides Revised Comments in Response to NRR Comments During 891213 Telcon Re Allowable Stresses for Piping & Piping Supports 1990-09-21
[Table view] |
Text
INDIANA II MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y 10004
~
YES PIXg CgPg November 12, 1982 AEP:NRC:0660E Donald C.Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 ORDER IMPOSING CIVIL MONETARY PENALTIES Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. DeYoung:
We have received your letter of October 14, 1982, with its enclosed Order Imposing Civil Monetary Penalties.
We appreciate the consideration you have given to our Response of March 1, 1982, and your consequent determination to withdraw the proposed civil penalties for Items I.A through I.F set out in your Notice of Proposed Imposition of Civil Penalties, dated December 30, 1981.
For the reasons set out in our March 1, 1982, Response, we take issue with the fines proposed for Items I.G, I.H, I.I, II.A and II.B. Nevertheless, rather than proceed with any extended debate over past, events, we are enclosing herewith a check in the amount of
$ 52,000.00 covering your imposed fines for the events.
While we are not requesting a hearing with respect to your imposed fine concerning Item I.I, we respectfully request you to reconsider your determination in this single matter.
While there may well have been an honest misunderstanding of the distinction we made in our January 31, 1977 letter between "administrative measures" and "administrative procedures", it remains our view that the submittal was not false.
821 1 190273 821 1 12 PDR ADOCK 05000315 8 PDR S
1 b
I" il r
0 g
Mr. Richard C. De g :NRC:0660E
~ ~
The January 31, 1977 Response in question stated (a) In re 1 to Section B.2 of BTP 9.5-1:
"Administrative measures have been established to control the storage of combustible materials and to prohibit their storage in the vicinity of safety related systems. These measures basically conform to the guidance provided in Regulatory Guide 1.39." (emphasis supplied.)
(b) In re 1 to Section B.3(c) of BTP 9.5-1:
"Administrative rocedures, will be established to control the use of combustible materials within any safety related areas. These materials must be used immediately when brought into a safety related area and their use will be limited and controlled." (emphasis supplied.)
Our letter of January 31, 1977, also said the,"procedures" would be effective as of July 31, 1977; it commitment was met on July 28, 1977.
is uncontroverted that this We are attaching with this letter (a) the requirement in Section B.2 of Appendix A to Branch Technical Position APSCB 9.5-1, which required the implementation of "administrative measures" to accommodate the "Housekeeping Requirement" of Regulatory Guide 1.39 referenced there (Section B.2), and (b) our "Housekeeping/Plant Cleanliness" instructions, which were in effect as of January 31, 1977.
We are also attaching (c) the requirement in Section B.3.(c) of Appendix A to BTP 9.5-1 and (d) a copy of our formal procedures, "Control of Combustible Materials," which ware in effect as of July 28, 1977, as we committed on January 31, 1977. We believed that
Attachment:
(b) fulfilled the intent of the Housekeeping "measure" required in Attachment (a) . Similarly Attachment (d) complied with the requirement of Attachment (c).
We are confident that your review of these enclosures, along with your reconsideration of our Response of March 1, 1982, will convince you that, at most, your inspectors may disagree with the adequacy of our "administrative measures," but that there is no basis at all for characterizing the January 31, 1977, submittal as false, and certainly it was not a material false statement.
It is to preserve this important distinction that we request reconsideration of this matter. If you personally continue to conclude that, indeed, this was a false statement, we will place this matter behind us.
11 E
k
) I 4 ~ 'I I) "(4 4 i'i) f ah )
v ~,. , at 4 'F '4' , Ifl=.a ) ~
4 I 4 F"
4 ll ') 4"hll
'4 4 )1')'
F 4'-, 4 h
4 ff aE 4
4 I II '
4 p IJ a I )hh
~I
- 4) "'h ",4)
Fhh V,lf 1 4 4 4 FE IF F
'h ,'a g ff
) 4 ~ I 1 ~
4 Fl 4
1 '1 4 Jhow EF) 1' Ih 4
- (a iv) '
)
4" 4( l)F 4 QI IF
'Il)h) )Ff 1 g lfgh ~
a ah* * ~
- 4) '4 ) H ff~ 4
'i)Eb 4 I' Th 'll 4 'Fh ll V E,<)
~
I 4 Il4, II
) 1 ~
a) 4 I'
',h f I'4 E
Mr. Richard C. DeYoung P:NRC:0660E
~ ~
This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours,
, S. unter
/os Vice President cc'John E. Dolan - Columbus H. P. Alexich R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.
NRC Resident Inspector at Cook Plant Bridgman
't )I I
I I <II A h
4 t
Attachment to AEP:NRC:0660E
F '
~ Mt 4 4
Attachments A and C APPLICATION DOCKETED BUT CONSTRUCTION PLANTS UNDER CONSTRUCTION AhD PER.'IIT NOT RECEIVED AS OF 7/I/76 OPERATING PLANTS 7.
The fire protection program for an Schedule for implementation of ent:ire reactox unit: should be fully modifications, if any, will be operational prior to initial fuel established on a case-by-case loading in that reactor unit. basis.
- 8. 8. Hulti le-Reactor Sites On multiple-reactor sites where there are operating reactors and construction of remaining units is being completed, the fire protection program should provide continuing evaluation and include additional fire barriers, fire protection capability, and administrative controls necessary to protect: the operating units from construction fixe hazards. The superintendent of. t: he operating plant should have the lead responsibility for site fixe protection.
- 9. Simultaneous Fires 9. Simultaneous Fires Simultaneous fires in more than one SAIfE reactor need not be postulated, where
<. sopaxation requirements are met. A fire involving more than one reactor unit need not be postulated except ior facilities shared between units.
B. Administrative Procedures, Controls and B. Administrative Procedures Pire Bri ade Controls and Fire Bri ade Administrative procedures consistent SAI fE with the need for maint:aining the per'-
formance of t: he fire protection system and personnel in nuclear power plants should be provided.
Guidance is contained in tfie following publica tions:
NFPA 4 Organization for Fire Services
AI'PLICATION DOCKETED BUT CONSTRUCTION PLANTS UNDER CONSTRUCTION AND PERiIIT NOT RECEIVED AS OF 7/1/76 OPERATING PIANTS Nl'I'A 4A - Organization for Fire Department NFPA 6. Industrial Fire Loss Prevention NFPA 7 - Management of Fire Emergenci.es NFPA 8 >fanagement Responsibility for Effects of Fire on Operations NFPA 27 Private Fire Brigades
- 2. Effective administrative measures 2. SAME should be implemented to prohibit hulk storage of combustible materials inside oi adjacent to safety related buildings or systems during operation or maintenance periods. Regulatory Guide 1.39, "Housekeeping Require-ment" for Water-Cooled Nuclear Power
'lants", provides guidance on house-keeping, including the disposal of combustible materials.
- 3. Normal and abnormal conditions or other 3. SAME.
anticipated operations such as modi-fications (e.g., breaking fire st'ops, impairment of "fire detection and suppression systems) and refueling activities should be reviewed by appropriate levels of management and appropriate special actions and procedures such as fixe watches or temporary fire barriers implemented to assure adequate fire protection and reactor. safety. Xn particular:
(a) Work involving ignition sources such as welding and flame cutting should be done under closely controlled conditions. Procedures governing such work should be re-viewed and approved by persons
G ADI'LICATION DOCKETED1'OVETKUCTIOH~ PLANTS ER COIXSTRUCTXON AND PERlfXT NOT RFCEXVED AS OF 7/1/76 OPEFNTXNG PLANTS trained and experienced in fire protection. Persons performing and directly assisting in such work should be trained and equipped to prevent and combat fires. Xf this is not possible, a person qualified in fire pro-tection should directly monitor the work and function as a fixe watch.
(b) Leak testing, and similar pro-cedures such as air flow deter- .
mination, should use one of the commercially available aeresol techniques. Open flames or combustion generated smoke should not. be permitted.
(c) Use of combustible material, e.g.,
.lfEPA and charcoal filters, dry ion exchange resins or other
,combustible supplies, in safety related areas should'be con-trolled. Use of wood inside buildings containing safety related systems or equipment
~
should be per'mitted only, when suitable non-combustible sub-stitutes are not available. Xf wood must be used, only fire retardant treated wood (scaffolding lay down blocks) should be per-mitted. Such mat:erials should be allowed into safety related areas only when they are to be used immediately. Their possible and probable use should be con-sidered in the fire hazard analysis
'to determine the adequacy of the installed fire protection systems.
- 4. Nu'clear power plants are frequently 4. Sax located in remote a'reas, at some distance from public fire departments.
Also, first response'fire departments are often volunteer. Public fire department response should be con-
~
4~
DO~'iALD C. COOK i~)UCLEAR PLANi PLANr h~ANAGER iNs:ri<UCiiON COVER SH""":r "ht tachment 8 Instruction No. I'i'll 2090 Revision No. 1 ff r; E )lousek epii;g/Plant Cleanl iness
': O."E OF REVISION Rev. 1 Changed format to coini)ly }!ith PilI-2010 Rev. 5.
Deleted reference Lo conti'act cleaners.
~
Added responsibility for inspection of Contaillm nt and balance of plant.
/j'p~q il
~'J
)
'-..J rll n )" r
'l jIPI '"
/
f>>l>>'!
r, >1~,l
>> ( iA ~ ~ >>g
>>>> ~
n.')",!ij"hff ..',
r-SI G NATU RES CP,I 6 I NAL REV. 1 REV. 2 REV. 3 PREPARED BY /)/ g/~g 0(/g+>> /
AEPSC QUALITY ASSt I R ANC f REV I EVP
/ I,>>':"~.
/.r/= /I"/,,
C "4"L/-~~ i'- -<
'VLArf'I'UCIEAR --.. =/) f/(/ <> -=/'i fi!"
SAf. ETY COHtvllTTFE ',';3 U ~'<<-~:h~~.<., ~H~>,.Jg, AEI'SC NUCLEAR SAFE'I Y DESIGN ftEVII'W COIv1MI1 TEE rLANT;;ANAGER APPROVAI (yjjjlj DA'I'Ir I r OF ISSL3E Io /t'jl
/
i/ 7 i=i-"
u't3 rOjrhl VO. Phil PO i 02 ACV.
n>>>> ~ l
> r/>> j'$i +>>>>!gq>y .
>>$ q>>fy>>>>'p>>}~q~gr>> '~1>>ws>>4 }/>>8 tf 8/>> s>>>>Q~~> ~A ~
LIST OF EFFECTl'VE PRGES Pa e Number Revision Hum6er and Date Re'v. 1 Rev. 1 Rev. 1 Page 1 Rev. 1
~ ~
p ~,
(i 0 .
INDIANA 5 t'lICHIGAN PO!fEf1 COf1PANY DONALD C. COOYi NUCLEAR PLAIlT
SUBJECT:
Housekeeping/Plant Cleanliness FROl'1 Plant t1anager TO: Department Heads OBJECTIVE To establish the policy and administrative controls for housekeeping and plant cleanliness.
BACYGROUND ANSI N45.2.3-1973 requires that housekeeping policies be established for all phase" of p<<".~t a" t".v ti s. Indiana 8 hicl;igan Power Company Safety t1anual Section G.9 established basic housekeeping policies for all of its organizations.
DETAILS The plant shall be maintained clean at all times. Cleanliness is a prerequisite to efficient and safe ope. ation.
The following are general levels of cleanliness which will be maintained:
Containment/Auxiliary Building a) Refueling Cavities: Follow cleanup procedures (for (Any lined cavity used for lined portions only) outlined in storage of fuel or borated water) PO-020-200 Rev. 1. "Nuclear Systems General Flushing and Cleaning" procedures prior to flooding cavity for refueling.
b) Painted concrete surfaces: Remove excess dust, dirt, grime and debris until the surface is visibly clean and dry.
c) Unpainted concrete surfaces: Same as painted surface.
d) Electrical cable trays: t1aintain free of excess wire, debris paper, wood chips.
e), Plant equipment (exterior of Outside surfaces should be free- of equipment, supports; cranes, etc.) dirt, grime, grease and dry, consistent with the normal operating condition of the equipment.
I Page 1 Rev. 1
'I'I I -EUPV General cleaning throughout the plant will be performed by Utility men.
Qc&
First line supervisors are responsible for insuring that the conditions existing in an area are satisfactory for conducting work prior to starting. (Reference - Safety thnual).
If an area or piece of equipment needs to be enclosed to assure the surrounding atmosphere is not detrimental to the equipment or the equipment detrimental to the surrounding area, such actions shall be accomplished prior to starting work.
The responsibility for cleaning the immediate surrounding area after work rests with the individuals performing the work..
> Inspections of completed work by first line supervisors shall also include inspection of the surrounding area for cleanliness, for removal of tools and equipment used to perform the work, for removal of fire hazards and proper disposal of scrap material and oily rags.
RESPONSIBILITY A
Department Heads are responsible for developing controls within their respecti ve departments to implement the requirements of this instruction.
The Operations Supervisor is responsible for conducting cleanliness inspections of the containment as required by the Appendix A Technical Specifications Section 4.5,2.b..
The g'uality Assurance Supervisor is responsible for conducting monthly Housekeeping/Cleanliness inspections of the entire plant with th~ exception of the Contuir,'ment..
MANAGEtdENT REVIEN Department Heads and first line supervisors are responsible for monitoring activities under their control to assure cleanlines's.
is being maintained.
The In-Plant General Safety Corrmittee shall conduct cleanliness inspection of the plant as part of one of the a'uarterly safety observations they conduct.
I INTERFACES All plant personnel are interfaced by this instruction, Cleanliness is the responsibility of all personnel as a part of their job.
Page 2 Rev. 1
P)11-2090 DISTRIBUTION In accordance with the standard distribution list of PllI-2010.
Chairman of In-Plant General Safety Committee.
REPORTING The results of the In-Plant General Safety Committee and Quality Assurance Supervisor inspections shall be sent to the Plant thanager and all Department Heads.
SCffEDUl. E Housekeeping and Cleanliness are continuing activities.
Page 3 Rev. 1
\
INDI@ NAOl MICHIIGAH PQVlEOCQJ"IPAMY DONALD C. COOK NUCLEAR PLANT PLAINT MANAGER INSTRUCTION COVER SHEET Attachment D Instruction No. PMI 2p7]
Revision No.
TITLE CONTROL OF COMBUSTIBLE MATERIALS SCOPE OF REVISION flammable.e Rev. I: Revised requirements for storage of and combustib).e liquids.
Hinor additions and editorial corrections made. Revised format.
Revisions indicated by marginal markings.
DCR APR Xo 1979 SIGN ATU RES ORIGINAL REV. I REV. 2 REV. 3 PREPARED BY AEPSC QUALITY ASS U RAN C E REV I EVl PLANT NUCLEAR SAFETY COMMITTEE n AEPSC NUCLEAR SAFETY DESIGN REVIEW COMMITTEE PLANT MANAGER 8c
~lA APPROVAL DATE OF ISSUE q zW-77 No. PM( tA / hi;, nCV.
~ w 0 ~
PHX-2271 LXST OF EFFECTEVE PAGES Pa e Number Revision Number and Date 1 Rev. 1, 3/20/79 2 Rev. 1, 3/20/79 3 Rev. 1, 3/20/79 4 Rev. 1, 3/20/79
.Page 1 of 1 Rev. 1, 3/20/79
~ ~
NDIANA & ifICHIGAN I PO'sx'ER COI iP DONALD CD~ COOK NUCLEAR PLANT TITLE Contxol of Conbnstible Hatexials OBJECTIVE To establish the administ'rative controls for the control of flammable and combustible materials used at the Donald C. Cook Nuclear Plant.
e BACKGROKiD Appendix A to Branch Technical Position APCSB 9.5-1 "Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976", requires in part that the use of combustible supplies in safety related areas be controlled.
DETAILS This instruction is applicable to any flammable or combustible materials, liquids, or gases used in the Plant. Some restrictions apply only to safety related areas of the Pl.ant. For the purpose of this Instruction, safety related areas are the Containment and safety related equipment rooms (i.e., CTS, SI, RHR pump rooms) of the Auxiliary Building, and the 4KV switchgear rooms, cable vaults, cable tunnels, battery rooms and Emergency Diesel Generator rooms.
The controls established for materials, liquids and gases are described following:
Haterials Combustible materials such as ion exchange resins, wood, paper and cardboard, HEPA and charcoal filters, dry shall be controlled as follows:
- 1. HEPA and charcoal filters and dry ion exchange resins are normally replacement items that are stored when not in use. When replacing these items in safety related areas, only the amount that vill be used during the work shift should be brought into the area. Used filters and resins shall be removed from the safety related area when the work is completed and take'n to a suitable location (i.e., drumming room) for storage or disposal. Under no circumstances vill these items be left in the safety related area.
Page 1 Rev. 1, 3/20/79
- 2. Rag shall be removed from afety .ated areas at the completion of the work and taken to a suitab]e l,ocation for disposal.. Care shou],d be taken to prevent the accumulation of used rags in the safety related ax'ea while work is in px'ogress.
Rags used in non-safety related areas of the Plant shou].d not be al,lowed to accumulate where they might become a fire hazard.. Rags shoul.d be disposed of or properly stored.
- 3. Wood may be used for scaffolding in safety re]ated areas only when suitable noncombustible substitutes are not availabl.e. If wood must be used, only fire retardant treated wood (scaffolding; laydown blocks) will be permitted. Wood, when used, must be removed immediate3y after completion of its use from safety rel.ated areas.
It is permissible to use wood l.adders in safety re]ated axeas providing they are removed fo].3.owing completion of work+
Mood used in non-safety related areas of the Plant for scaffolding, laydown, temporary structures or other uses should be fire retardant treated.
1
- 4. Shipping crates or containers shou].d be removed from equipment or materia3. prior to'hose items being taken into a safety related area. If removal is not feasibl.e, it is permissibl.e to take these containers into a safety related area provided the containers are removed from the area as soon as uncrating is completed.
- 5. Paper, cardboard and other trash shal.l, not be l,eft to accumul.ate in safety re3ated areas.
Paper, cardboard and othex'rash shou],d not be left to accumu3.ate in non-safety rel,ated areas of the P].ant except in containers intended for the disposal. of such debris.
used s Flammable and combustible ].iquids" such as acetone, alcoho].,
fuel oil, gasoline or tuluol shal.l be control].ed as fol].ows:
Flammable or combustible liquids shal.], onl.y be transported and stored in safety containers equipped with f],arne
- -- - arres tors. This requirement does not app3 y to such
].iquids as heavy weight oils which wi].l not pout. through the screen of a flame arx'estor.
Page 2 Rev. 1, 3/2Q/79
P>jI-2271 Flammable or combustible liquids in non-safety related areas shall be stored in a desi.gnated area'or safety cabinet and, when opened for use, transfered from shipping containers to safety containers with flame arrestors. Small quantities of liquids for use in shops, labs, etc., need not be stored in safety containers.
- 2. Flammable or combusti.ble liquids used in safety related area shall not be used or placed near heat or open flame. This restriction should also be observed in non-safety related areas.
- 3. Mien using flammable or combustible liquids in safety related areas a fire extinguisher shall be in the immediate area. This practice should be observed in non-safety related areas as well.
,Com ressed Gases Compressed gases in portable tanks such as oxygen, and flammable compressed gases such as acetylene, or aerosol cans containing flammables shall be controlled as follows:
- 1. The use of oxyacetylene torch equipment shall be in accordance with PHI-2275, Fire Prevention Control of Ignition Sources.'.
Leaking cylinders, valves, fittings or aerosol cans shall not be used.
- 3. Adequate ventilation must be available.
4, Upon completion of work, compressed gas containers or aerosol cans shall be removed from safety related areas.
- 5. Compressed gas cylinders, i.n use or in storage, sha].l be adequately secured in an upright position to prevent them from being accidentally tipped over.
RESPONSIBILITY Department Heads are rgsponsible for assuring that the policy and administrative controls established by this Instruction are implemented within their respective Departments.
Department Heads are responsible for. assuring that new employees within their Department receive indoctrination in these requirements.
This indoctrination shall be documented.
Page 3 Rev. 1, 3/20/79
PMX-2271 The Plant Manager or the Assistant Plant Manager is responsible for resolving problems which arise during the implementation of this instruction.
It is the responsibility of all Plant personnel to adhere to the requirements of this Instruction.
MANAGEMENT REVIEW Department Heads axe responsible for reviewing the effectiveness of the implementation of the requirements of this Instruction within their respective Departments.
INTERFACES All Departments are required to adhere'o this Xnstruction.
DHX's to implement this Instruction are not required.
DISTRIBUTION Per PMX-2010, and SOE Office.
REPORTXNG There are no 'reports required by this Instruction. However, violations of this Instruction shall be reported via a Condition Report in accordance with PMX-7030.
SCHEDULE This Instruction is effective on date of issue.
Page 4 Rev. 1, 3/20/79
0}}