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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed ML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 ML20209D6951999-07-0707 July 1999 Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock ML20206P0921999-05-0707 May 1999 Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule ML20206H1011999-05-0404 May 1999 Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20206E7821999-04-29029 April 1999 Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program ML20206E3721999-04-29029 April 1999 Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required ML20206B7381999-04-26026 April 1999 Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined ML20196K7881999-03-29029 March 1999 Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept ML20205E3471999-03-29029 March 1999 Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to ML20204F4611999-03-19019 March 1999 Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML20203F8041999-02-11011 February 1999 Forwards Temporary Addendum to Security Plan Re Central Alarm Station,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21(c) ML20203C8971999-02-0808 February 1999 Informs That NRR Contracted with PNNL to Evaluate Storage of Spent Fuel at Number of Decomissioning Nuclear Power Facilities.Forwards Request for Info Re Spent Fuel Storage at Big Rock NPP ML20202H4891999-01-26026 January 1999 Informs That Exemption Request from Various 10CFR73 Physical Protection Requirements, ,was Improperly Based on Requirements of 10CFR50.12.Request Was Resubmitted by Ltr ML20199H2431999-01-15015 January 1999 Forwards Insp Rept 50-155/98-09 on 981201-990112 & Nov.One Weakness Identified Re Event Involving Ungrappling Fuel Bundle Without Being Fully Seated in Rack & Without Independent Verification That Ungrappling Bundle Was Proper ML20199E0781999-01-13013 January 1999 Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5 ML20199E1841999-01-13013 January 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication ML20199D9711999-01-13013 January 1999 Forwards Plant Defueled TS Administrative Replacement Pp.On 990104 Staff Informed NRC That Pp Numbering for Table of Contents Was Incorrect.Subj Pp Requested to Be Replaced with Encl ML20199E9051999-01-12012 January 1999 Submits Revised Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls ML20199E7671999-01-12012 January 1999 Informs That Licensee Has Elected to Comply with Listed 10CFR50.68(b) Requirements in Lieu of Maintaining Monitoring Sys Capable of Detecting Criticality as Described in 10CFR70.24 ML20199A4151999-01-0404 January 1999 Informs That Individuals Listed on Attachment 1 Will No Longer Maintain Operating License for Plant.Senior Licensed Operators & Licensed Operators No Longer Required at Facility ML20198K6551998-12-24024 December 1998 Forwards Amend 120 to License DPR-6 & Safety Evaluation. Amend Changes License DPR-6 & App A,Ts to Reflect Permanently Shutdown & Defueled Status of Plant ML20198J4001998-12-21021 December 1998 Requests That Words Decommissioning of in First Sentence of Paragraph a of Fol,License DPR-6 Be Removed from CPC 970919 Request ML20196H3171998-12-0303 December 1998 Forwards Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted.Inspection Covered Activities in Areas of Radiological Safety ML20196G7541998-11-25025 November 1998 Requests Withdrawal of Listed Sections of 970919 Amend Request,As Supplemented by Ltrs ,0721 & 1014, Respectively.Util Proposed to Retain Certain Sections of Current Tech Specs (CTS) to Support Withdrawal Request ML20195G9851998-11-17017 November 1998 Forwards Rev 0 to Vol 9 of Defueled Emergency Plan & Rev 0 to Vol 9A of Defueled Epips ML20195H5321998-11-13013 November 1998 Provides Confirmation That Revs Required by NRC to Defueled Emergency Plan Prior to Implementation Have Been Completed by Licensee.Items Incorporated Into Plan,Listed ML20195F2271998-11-12012 November 1998 Forwards Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls.Request Withheld,Per 10CFR73.21 ML20154M5381998-10-14014 October 1998 Forwards Supplement to Plant Defueled TS & Bases, Incorporating Licensee Response to NRC 980416 RAI & Clarifying Listed Items ML20154M2211998-10-14014 October 1998 Forwards Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted.Insp Consisted of Examination of Activities in Areas of Facility Mgt & Control,Decommissioning Support (Including Physical Security),Sf Safety & Radiological Safety ML20154A7511998-10-0101 October 1998 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments, Since Oct 1997.Summary of Changes to Facility, Brief Description of Each Change & Summary of SE 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20206E7821999-04-29029 April 1999 Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program ML20196K7881999-03-29029 March 1999 Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML20203F8041999-02-11011 February 1999 Forwards Temporary Addendum to Security Plan Re Central Alarm Station,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21(c) ML20202H4891999-01-26026 January 1999 Informs That Exemption Request from Various 10CFR73 Physical Protection Requirements, ,was Improperly Based on Requirements of 10CFR50.12.Request Was Resubmitted by Ltr ML20199E7671999-01-12012 January 1999 Informs That Licensee Has Elected to Comply with Listed 10CFR50.68(b) Requirements in Lieu of Maintaining Monitoring Sys Capable of Detecting Criticality as Described in 10CFR70.24 ML20199E9051999-01-12012 January 1999 Submits Revised Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls ML20199A4151999-01-0404 January 1999 Informs That Individuals Listed on Attachment 1 Will No Longer Maintain Operating License for Plant.Senior Licensed Operators & Licensed Operators No Longer Required at Facility ML20198J4001998-12-21021 December 1998 Requests That Words Decommissioning of in First Sentence of Paragraph a of Fol,License DPR-6 Be Removed from CPC 970919 Request ML20196G7541998-11-25025 November 1998 Requests Withdrawal of Listed Sections of 970919 Amend Request,As Supplemented by Ltrs ,0721 & 1014, Respectively.Util Proposed to Retain Certain Sections of Current Tech Specs (CTS) to Support Withdrawal Request ML20195G9851998-11-17017 November 1998 Forwards Rev 0 to Vol 9 of Defueled Emergency Plan & Rev 0 to Vol 9A of Defueled Epips ML20195H5321998-11-13013 November 1998 Provides Confirmation That Revs Required by NRC to Defueled Emergency Plan Prior to Implementation Have Been Completed by Licensee.Items Incorporated Into Plan,Listed ML20195F2271998-11-12012 November 1998 Forwards Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls.Request Withheld,Per 10CFR73.21 ML20154M5381998-10-14014 October 1998 Forwards Supplement to Plant Defueled TS & Bases, Incorporating Licensee Response to NRC 980416 RAI & Clarifying Listed Items ML20154A7511998-10-0101 October 1998 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments, Since Oct 1997.Summary of Changes to Facility, Brief Description of Each Change & Summary of SE ML20153F6061998-09-17017 September 1998 Commits to Revise Defueled Emergency Plan Currently Under Review by Staff,Per Discussion with NRC on 980917.Section 10.2, Assessment Methods Will Be Revised as Listed ML20151Y2621998-09-11011 September 1998 Provides Description of Three Listed Requirements Re Plant Defueled Emergency Plan Implementation Commitments,In Response to 980911 Telcon with NRC ML20238E8081998-08-28028 August 1998 Forwards Revised Big Rock Point Defueled Emergency Plan. Rev to Plan Resulted from NRC Questions Raised During 980813 Meeting ML20237B4351998-08-11011 August 1998 Provides twenty-ninth Update of Big Rock Point Integrated Plan.Plan Has Had No Changes Since Last Update Dtd 980213. Proposed Defueled Facility OL & Tss,Currently Under Review by Nrc,No Longer Require Submission of Plan 05000155/LER-1998-001, Forwards LER 98-001-00 Re Discovery During Facility Decommissioning of Severed Liquid Poison Tank Discharge Pipe.Rept Being Submitted IAW 10CFR50.72(b)(2)(iii) & 10CFR50.73(a)(2)(i)(B)1998-08-0606 August 1998 Forwards LER 98-001-00 Re Discovery During Facility Decommissioning of Severed Liquid Poison Tank Discharge Pipe.Rept Being Submitted IAW 10CFR50.72(b)(2)(iii) & 10CFR50.73(a)(2)(i)(B) ML20236Y4171998-08-0606 August 1998 Forwards semi-annual Fitness for Duty Program Performance Rept for Period Jan-June 1998 ML20236V7741998-07-30030 July 1998 Forwards Revs to Defueled Emergency Plan & Related Exemption Request,As Result of 980625 Meeting W/Nrc Re Plant Restoration Project Defueled Emergency Plan & Related Exemption Request from 10CFR50 Requirements ML20236W3341998-07-27027 July 1998 Submits Draft Rev 19b of Quality Program Description for Operational Nuclear Power Plants (CPC-2A).Changes in Draft Rev 19b Respond to NRC Questions Re Program Scope as Applied to Big Rock Point & Restore TSs Re on Site Review Committee ML20236T6651998-07-21021 July 1998 Provides Remaining Responses to NRC 980416 RAI Re Big Rock Plants Proposed Defueled Tech Specs.Proposed Defueled Tech Specs & Bases,Encl ML20236R2771998-07-14014 July 1998 Submits Response to Violations Noted in Insp Rept 50-155/98-03.Corrective Actions:Staff Reviewed Decommissioning Surveillance Testing on safety-related Sys, Structures & Components ML20236J3461998-06-30030 June 1998 Forwards Rev 135 to Vol 9 of Site Emergency Plan & Rev 184 to Vol 9A to Site Emergency Plan Implementing Procedures ML20236H0701998-06-30030 June 1998 Responds to Violations Noted in Insp Rept 50-155/98-04. Corrective Actions:Rcw Sys Function Plant Performance Criteria Was Revised to One MPFF for Sys Function in Expert Panel Meeting 98-02,980506 ML20248L8131998-06-0505 June 1998 Requests Withdrawal of Application for Amend to License DPR-6 Dtd 980325.Facility Security Mods Described in Amend Will Not Be Performed as Originally Scheduled ML20248L5461998-06-0505 June 1998 Forwards Draft Proposed TS & Bases Rev,Incorporating Changes Responsive to 980416 RAI ML20247G1481998-05-12012 May 1998 Forwards Rev 14 to Plant Suitability,Training & Qualification Plan,Per Provisions of 10CFR50.54(p).Changes Are Editorial to Reflect Change from Consumers Power Co to Consumers Energy Co.Encl Withheld ML20216A9351998-04-30030 April 1998 Forwards Big Rock Point Radioactive Effluent Release Rept & Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program ML20217N2011998-04-29029 April 1998 Forwards Brpnp Zircaloy Oxidation Analysis, Which Presents Site Specific Analysis That Derives Time When Zircaloy Oxidation Analysis Phenomenon Is No Longer Applicable to Plant Fuel Pool ML20217G4941998-04-23023 April 1998 Informs That Previous Commitments Will Not Be Retained Due to Permanent Cessation of Big Rock Point Plant Operation. Commitments Associated W/Nrc Insp Repts,Encl ML20217E9101998-04-21021 April 1998 Forwards 1997 Consumers Energy Co Annual Rept, Including Certified Financial Statements ML20217P2401998-03-31031 March 1998 Forwards site-specific Dimensions & Construction Info Re Big Rock Point Wet Spent Fuel Storage Sys as Requested in 989223 RAI on Exemption from Offsite Emergency Planning Requirements ML20217H4521998-03-26026 March 1998 Forwards Rev 2 to Post Shutdown Decommissioning Activities Rept (Psdar). Rev Incorporating Revised,Detailed Schedule & Revised Cost Estimate,Will Be Submitted to Util ML20217F5061998-03-25025 March 1998 Forwards Application for Amend to License DPR-6,per 10CFR50.90.Security Plan Revised to Reduce Scope of Plan to Correspond to Condition of Facility,Since Reactor Has Been Permanently Defueled.Encl Withheld,Per 10CFR73.21 ML20217G7771998-03-24024 March 1998 Submits Annual Rept of Insurance & Financial Security Maintained at Util Operating Npps,Per 10CFR50.54(w)(3) 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0161990-09-18018 September 1990 Forwards Corrected Monthly Operating Rept for Aug 1990 for Big Rock Point Plant,Consisting of Corrections to Grey Book ML20059K2381990-09-0707 September 1990 Forwards Info in Response to Request for fitness-for-duty Policy & Procedures,Per NRC ML20059F5031990-09-0505 September 1990 Forwards Description of Scope & Objectives for 1990 Emergency Exercise Scheduled for 901204.Region III Will Participate ML20059E0001990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990 ML20059B6371990-08-22022 August 1990 Forwards Correction to 900628 Response to Generic Ltr 90-04 Re Status of Generic Safety Issues (Gsis).Response Contained Some Errors in That Some Palisades Plant Related Info Inadvertently Substituted Into GSI Table for Big Rock Point ML20059B6321990-08-22022 August 1990 Forwards Revised Engineering Analysis of Generic Ltr 88-01 on Plant Temp Pressure Limits in Support of Licensee 900110 Tech Spec Change Request,Per NRC Request ML20059B6221990-08-22022 August 1990 Forwards Missing Pages 25 & 26 Omitted from Facility Decommissioning Funding Rept,Consisting of Attachment a to Exhibit E ML20058L9891990-08-0606 August 1990 Provides Util Comments Re SALP 9 Board Rept.Declining Trend in Radiological Controls Noted in Cover Ltr Needs to Be Reevaluated ML20056A3491990-08-0303 August 1990 Updates Response to NRC Bulletin 90-002, Loss of Thermal Margin Due to Channel Bow 05000155/LER-1990-002, Requests Extension of Due Date for Radiation on-the-job Training to 901101,per 900518 LER-90-002 Describing Violation Involving Unqualified Technician Assigned to Shift Compliment.Delay Due to Forced Outage1990-08-0101 August 1990 Requests Extension of Due Date for Radiation on-the-job Training to 901101,per 900518 LER-90-002 Describing Violation Involving Unqualified Technician Assigned to Shift Compliment.Delay Due to Forced Outage ML20055J3841990-07-26026 July 1990 Forwards Certification of Financial Assurances for Decommissioning ML20044A9841990-07-13013 July 1990 Updates 881207 Response to Open Items Noted in Insp Rept 50-155/88-06.Corrective Actions:App R Schemes Completed on 890113.Requirements of App R,Section III.G.3 Satisfied for Fire Areas 12 & 13 & Associated Boundaries ML20055E0211990-06-29029 June 1990 Requests NRC Approval of Encl Simulation Facility Application for Plant,Per 10CFR55.45(b) ML20042E6471990-04-20020 April 1990 Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Analyses Evaluating Effect of Channel Box Upon Min Critical Power Ratio at Plant Being Performed ML20012E2201990-03-27027 March 1990 Forwards Rev 9 to Suitability,Training & Qualification Plan.Rev Withheld 05000155/LER-1989-006, Advises That Schedule for Upgrading Fire Barrier Penetration Surveillance Program,Per LER 89-006,extended from 900301 to 9006301990-03-0101 March 1990 Advises That Schedule for Upgrading Fire Barrier Penetration Surveillance Program,Per LER 89-006,extended from 900301 to 900630 ML20033E0681990-02-27027 February 1990 Provides Semiannual Update 12 to Plant Integrated Plan, Including Index of All Issues & Open Items.Issues Added Also Listed ML20033F1191990-02-14014 February 1990 Responds to Generic Ltr 89-11, BWR Reactor Water Level Redundancy, Providing Resolution to Generic Issue 101 & NUREG/CR-5112.Breaks in Vessel Level Instrumentation Have No Effect on Feedwater Operation ML20011E6901990-02-13013 February 1990 Provides Util Interpretation of Plant Tech Spec Section 6.2.2 Re Control Rod Withdrawal Interlock Operability.To Permit Drive Movement,Temporary Jumper Placed in Control Rod Withdrawal Permissive Circuit to Inhibit Rod Block ML20006E4341990-02-13013 February 1990 Responds to 891221 Request for Addl Info Re Generic Ltr 89-04.Procedure Written to Test Water Supply Check Valve & Limiting Stroke Time Values for Subj Valves Changed in Accordance W/Position 5 in Generic Ltr ML20006F1301990-02-12012 February 1990 Lists Suggested Topics for Licensee Info Conference,Per 900117 Request ML20006D1201990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Responsibility for post-accident,long-term Cooling Primarily Relegated to post- Incident Sys & Interfacing Support Sys ML20042D2581989-12-29029 December 1989 Forwards Request for Approval of Procedures to Relocate Sediment from Plant Discharge Canal to Confined Disposal Area Onsite,Per 10CFR20.302(a) ML20011D2881989-12-19019 December 1989 Provides Certification That Fitness for Duty Program Meets 10CFR26 & Will Be Implemented by 900103 ML18054B0951989-11-0606 November 1989 Forwards Executed Amends 10 & 18 to Indemnity Agreements B-40 & B-22,respectively ML18054B0431989-10-19019 October 1989 Forwards Revs 9 & 10 to CPC-2A, QA Program Description for Operational Nuclear Power Plants. Lists of Affected Pages in Revs 9 & 10 & Change Matrices Encl ML20248B4091989-09-29029 September 1989 Confirms Util Commitment to Conform W/Generic Ltr 89-04 Positions Re Guidance on Developing Acceptable Inservice Testing Program ML20247B1871989-09-0505 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-155/89-14.Corrective Actions:Appropriate Surveys & Labeling W/Contamination Levels,Contents & Date Completed & Procedures Re Guidelines for Contaminated Matls Revised ML20246N1211989-08-31031 August 1989 Forwards Integrated Plan Semiannual Update 11,consisting of Index of All Issues Identified by Category,Rank,Description & Status & List of All Open Issues Containing Detailed Scope Statements,Status & Applicable Scheduled Completion Dates ML20246J1721989-08-30030 August 1989 Forwards Semiannual Radioactive Effluent Release & Waste Disposal Rept,Jan-June 1989 & Rev 4 to Offsite Dose Calcuation Manual ML20246N6901989-08-30030 August 1989 Forwards Response to Generic Ltrs 89-12 & 89-03.Operator Licensing & Requalification Exam Schedules for Plants Encl ML20246L9111989-08-30030 August 1989 Responds to NRC Re Violations Noted in Insp Rept 50-155/89-13.Corrective Actions:Plant Procedures Being Rewritten to Address Human Factors Concerns & Complete Insp & Clean Up of Reactor Bldg Area Conducted ML20248A4431989-07-27027 July 1989 Advises That Integrated Leak Rate Test Will Commence on 890724-28,in Response to Open Items Noted in Insp Rept 50-155/85-20.Test Will Be Performed Per Method Described in Bechtel Rept BN-TOP-1 ML20247N8281989-07-25025 July 1989 Responds to NRC Concern Re Ability of Employees & Contractors to Raise Safety Issues to Licensee Mgt & NRC W/O Restrictions.Licensee Understands & Endorses Importance of Maintaining Communication Pathway Unrestricted ML20247A6161989-07-18018 July 1989 Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Review of NUMARC Guidelines Contained in App a of NUREG-1344,performed.Plant Intends to Implement Erosion/Corrosion Monitoring Program ML20245K6791989-06-30030 June 1989 Forwards Corrected Tech Spec Paragraph 3.7(f) Re Containment Sphere Leakage Testing,Per 890627 Telcon.Original 890525 Tech Spec Change Request Contained Inadvertent Textual Error ML20245K0631989-06-29029 June 1989 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Evaluation & Addl Listed Considerations Dictate That Future Component Insp Should Be Performed & Evidence of Pump Degradation Be Continued ML20245E9671989-06-23023 June 1989 Responds to 890418 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping ML20245A9771989-06-15015 June 1989 Forwards Scenario for 1989 Emergency Plan Exercise,Per Util 890322 Commitment ML20244A6311989-06-0606 June 1989 Submits Update to Util 880725 Response to Violations Noted in Insp Rept 50-155/88-12.Corrective Actions:Util Staffed Procedure Writers Group to Upgrade Maint Procedures & Procedure MGP-14 Revised ML20247D5631989-05-19019 May 1989 Responds to Re Util 881021 Rev 8 to QA Topical Rept CPC-2A.List of Recommended Changes Concerning Training Qualification & Certification Encl ML20247C3671989-05-17017 May 1989 Discusses Status of Corrective Actions Re Violations Noted in Insp Repts 50-155/87-22 & 50-155/88-11.Instructions Provided to Shift Supervisors Re Trending Requirements of Valve Timing After Maint ML20246G8961989-05-12012 May 1989 Forwards Temporary Addendum to Security Plan Re Replacement of Plant Heater Boiler.Encl Withheld (Ref 10CFR73.21(c)) ML20246C6851989-05-0101 May 1989 Forwards Annual Radiological Environ Operating Rept Jan-Dec 1988 ML20245J2871989-04-27027 April 1989 Comments on SALP 8 Board Rept for Sept 1987 - Dec 1988. Correction of Reactor Depressurization Sys Valve Problems, Neutron Monitoring Sys Upgrades & Resolution of Steam Drum Relief Valve Concerns Completed in 1988 ML20245B3601989-04-18018 April 1989 Forwards Details of Document Search Including Closure Dates in Response to 890414 Request for Status of TMI Action Plan Items ML20244D8891989-04-17017 April 1989 Submits Info Re Station Blackout Rule 10CFR50.63,including Justification for Selection of Proposed Blackout Duration, Description of Procedures Implemented for Events & Discussion of Plant Unique Design Re Survival Capability ML20245A3701989-04-14014 April 1989 Forwards Endorsement 121 to Nelia Policy NF-117 ML20244D5561989-04-13013 April 1989 Forwards Corrected 1988 Personnel Exposure Range Summary Rept,Correcting Typo ML20244D6111989-04-12012 April 1989 Responds to Request for Addl Info Re Tech Spec Change Requests Dtd 870723,880908 & 0922.Specs Cover Inservice Insp & Testing,Fire Spray &/Or Sprinkler Sys & Plant Staff Qualifications 1990-09-07
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@M Consumers POW 8f x.nn.m w s.ny Durctor Nwirar Ekenung SMM M' Generet Offees: 1945 West Pamall Road, Jackson, MI 49201 (517) 788-1636 April 14, 1986
- Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLAh -
FIRE PROTECTION - ADDITIONAL INFORMATION REGARDING ITEMS OF NON-COMPLIANCE /0 PEN ITEMS IDENTIFIED DURING 1985/1986 INSPECTION An inspection of fire protection measures and compliance with the applicable sections of 10CFR50.48 and 10CFR50, Appendix R was conducted by the NRC at the Big Rock Point Plant from December 9, 1985 through December 13, 1985. This inspection was continued during the week of March 5, 1986. Certain items of non-compliance with the applicable regulations and a number of open items were identified by the NRC inspectors during this inspection. A meeting with the NRC inspectors and representatives of the NRC-NRR was then held in Washington, DC on March 31, 1986 to discuss these items. During this meeting, Consumers Power Company agreed to submit a letter within 14 days which responds to the following NRC requests:
1.
Identify all areas in the Plant which are not in compliance with applicable sections of 10CFR50.48 and 10CFR50, Appendix R, or areas which are not in compliance with regulations because an exemption has not been requested.
2.
Describe the compensatory actions taken for the items identified in response to "1" above.
3.
Provide a date for submittal of a comprehensive fire protection summary document to the NRC.
(This summary document should include an updated Fire Hazards Summary, Safe Shutdown Summary, all pertinent correspondence between the NRC and Consumers Power Company concerning compliance to 10CFR50.48 and 10CFR50, Appendix R, as well as Appendix A to Branch Technical Position (BTP) 9.5-1.)
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Director, Nuclear Reactor Regulation 2
Big Rock Point Plant Fire Protection-Items on Non-Compliance April 14, 1986 This letter provides the responses to these requests, and summarizes Consumers Power Company's plan for resolving the items identified in the responses to "1".
This letter includes, for completeness, the information in our letter dated March 14, 1986 which described the compensatory actions taken for the lack of emergency lighting in the Plant yard and the indeterminate temperature rise due to an oil fire in the Recirculation Pump Room.
The following four items of non-compliance / lack of exemption request have been identified.
A.
10CFR50, Appendix R, section III.J and 10CFR50, Appendix B -
Untimely Corrective Action - Corrective action to resolve deficiencies with emergency lights within the power block was not taken in a timely manner.
B.
Routine fire protection measures - Lack of Control of Combustibles - Combustible material was stored in the vicinity of the electrical conduits carrying electrical cable for the Alternate Shutdown Building.
C.
10CFR50, Appendix R, section III.J - Lack of Emergency Lighting in Yard - Plant yard lighting that illuminates access and egress to areas / buildings in which safe shutdown equipment is located is not powered by an emergency power source.
D.
10CFR50, Appendix R, section III.G.2 - Lack of Exemption Request for Screenhouse - A radiant energy shield was installed in the Screenhouse, in lieu of fixed suppression, to protect the service water pumps in the event of a fire which disabled the diesel fire pump located in the same building.
While this compensatory measure was approved by the NRC in its review of our response to BTP9.5-1, Appendix A, an exemption to the requirements of 10CFR50, Appendix R, section III.G.2.b which applies to fixed suppression in areas of redundant equipment was not requested.
The following open items have also been identified.
E.
Unresolved exemption request concerning the separation of safe shutdown circuits in the Control Room.
F.
Unresolved exemption request concerning the need for oil collection capability in the Recirculation Pump Room.
Each item is discussed below.
A.I.
Untimely Corrective Action During the inspection, two of four emergency lights tested failed to operate for eight hours. Although a duration problem was identified by Consumers Power Company in August, 1984, corrective OC0486-0072-NLO4 J
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Director, Nuclear Reactor Regulation 3
Big Rock Point Plant Fire Protection-Items on Non-Compliance April 14, 1986 action was incomplete at the time of the inspection in December, 1985.
This is considered to be an isolated incident.
2.
Compensatory Actions A sufficient number of portable battery powered lanterns have been made readily available to the Plant operators, and will remain available until the corrective action described below is completed.
Plan for Resolution A modification will be made to the emergency lighting units that were installed as required by 10CFR50, Appendix R, section III.J.
to increase the capacity of these units. This modification involves adding an additional battery of the same ampere-hour capacity in parallel to the existing battery, thereby effectively increasing the time rating on each unit to greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
This modification will be completed by September 1, 1986.
B.1.
Lack of Control of Combustibles During the December, 1985 inspection, resin-filled barrels temporarily located in the Turbine Building in the vicinity of the electrical conduits associated with the Alternate Shutdown Building were identified by the inspectors. Contrary to Consumers Power Company's determination, the NRC inspectors confirmed that this material is flammable and therefore constitutes a potential fire hazard. This is considered an isolated incident.
2.
Compensatory Actions The barrels were relocated to an appropriate storage area upon identification of the concern by the NRC inspectors.
Plan for Resolution To prevent the recurrence of improperly stored combustibles that would contribute to the fire loadings in any fire area, the Plant staff has been reminded to be more aware of transient fire loads and has been directed to remove or clean up such materials as soon as ongoing work activities are completed. The Plant Property Protection Department will conduct routine naspections of the Plant to assure compliance. The Plant is ns. in compliance with requirements, and no further actione are deemed necessary.
OC0496-0072-NLO4 a
c y-Director, Nuclear Reactor Regulation 4
Big Rock Point Plant Fire Protection-Items on Non-Compliance April 14, 1986 C.I.
Lack of Emergency Lighting in Yard Access and egress to/from buildings / locations outside the power block are necessary in order to operate equipment needed for safe shutdown (eg, Screenhouse, Alternate Shutdown Building, Stand-by Diesel Generator).
Lighting in the Plant yard area along routes to these buildings / locations is not powered by an emergency power source, or is nonexistent.
The decision not to provide emergency lighting in the yard area was based on Consumers Power Company's determination that such lighting was unnecessary for Plant operators to access / egress the safe shutdown equipment outside the power block.
2.
Compensatory Actions As committed to in our letter dated March 14, 1986, a sufficient number of portable battery powered lanterns have been made readily available to the Plant operators.
Plans for Resolution An exemption from the applicable requirements of 10CRF50, Appendix R, section III.J will be requested. This request for exemption will be based on an appropriate justification and will be submitted to the NRC by May 1, 1986.
D.1.
Lack of Exemption Request for Screenhouse As a result of the NRC's review of our " Fire Protection Program Evaluation," dated March 29, 1977, the NRC stated its position in a ' letter dated November 20, 1978 that either a sheet metal shield or a sprinkler system installed in the area of the diesel fire pump would protect the redundant fire and service water pumps from a fire at the diesel fire pump.
By letter dated December 8, 1978, Consumers Power Company committed to the installation of a sheet metal (radiant energy) shield in the area of the diesel fire pump, and its installation was verified during the 1985/1986 inspection.
NRC Generic Letter 81-12 (" Fire Protection Rule,"
dated February 20, 1981), however, clarixied the requirement to reexamine fire protection measures for ccmpliance with 10CFR5J.48 and 10CFR50, Appendix R even if these measures were approved by Safety Evaluation Reports previously issued by the NRC. Although Consumers Power Company had acknowledged receipt of Generic Letter 81-12, an exemption from the requirements of 10CFR50, Appendix R, section III.G.2.b regarding fixed suppression in the screenhouse was not requested. This omission is considered an oversight.
OC0486-0072-NLO4
r Director, Nuclear Reactor Regulation 5
Big Rock Point Plant Fire Protection-Items on Non-Compliance April 14, 1986 2.
Compensatory Action Plant operations personnel tour this area every two hours, and security personnel now tour this area every four hours.
(Note that the four-hour tour by security personnel will now be required until this issue is resolved.) Both operations and security personnel are qualified as members of the Plant fire brigade. The Screenhouse also contains four rate-of-rise heat detectors that alarm in the Control Room. The manual suppression equipment that is maintained and available in the Screenhouse includes a hose reel, a 150 lb. wheeled dry chemical ANSUL cart extinguisher. :wo 30 lb. portable dry chemical extinguishers, and a 20 lb. port ble carbon dioxide extinguisher. Consumers Power Company considers that these fire protection measures provide adequate assurance that detection of and response to a fire in the Screenhouse will be accomplished rapidly, and most probably before any danage occurs.
Plan for Resolution An exemption from the requirements of 10CFR50, Appendix R, L
section III.G.2 will be requested.
This request for exemption will be based on an appropriate justification and will be i
submitted'to the NRC by May 1, 1986.
E.1.
Unresolved exemption request concerning the separation of safe shutdown circuits in the Control Room As a result of the 1985/1986 inspection, our understandings of the status of the exemption submitted by Consumers Power Company by letter dated September 28, 1982, is that this request is unresolved, ie, neither approved nor disapproved. This exemption concerns the separation of the emergency condenser inlet valve circuits, core spray valve circuits, and the reactor depressurization system circuits in the Control Room.
Since this
. exemption request is unresolved, Consumers Power Company agrees i
that compensatory actions must be identified.
2.
Compensatory Actions A Control Room " fire watch" will be implemented by personnel other than the Control Room operators performing a tour of the Control Room approximately every 20 minutes. This action will remain in effect until this item is resolved. Although we commit to implementing this " fire watch", we also point out that the Control Room is continuously manned by Plant operations personnel trained and equipped to fight fires in the Control Room.
Automatic Products of Combustion detectors are installed and alarm in the Control Room. Two portable carbon dioxide extinguishers and three self-contained breathing units are maintained and available in the Control Room.
In addition, two OC0486-0072-NLO4 t --
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Director, Nuclear Reactor Regulation 6
Big Rock Point Plant Fire Protection-Items on Non-Compliance April 14, 1986 2-3 gallon water extinguishers and a standpipe with 50 feet of 1-) inch hose and 50 feet of extra hose are located just outside the Control Room door.
Plan for Resolution Additional clarifying information is currently being assembled to support the exemption requested on September 28, 1982. This information will be submitted by June 1, 1986.
F.1.
Unresolved exonption request concerning the need for oil collection capability in the Recirculation Pump Room.
By letter dated February 9, 1982, Consumers Power Company requested an exemption from the requirements of 10CFR50, Appendix R, section III.0 for the Recirculation Pump Room. This request included a calculation of the temperature rise in this Room due to an oil fire as supporting justification for the exemption. This calculation was found to be in error by the NRC-Region III, and was discussed with the NRC inspectors during the March, 1986 inspection.
(Note: Our March 14, 1986 letter erroneously stated that calculation error was identified by Consumers Power Company due to a misunderstanding.) Accordingly, the expected maximum temperature in the Recirculation Pump Room due to an oil fire is now uncertain, thereby changing the status of this exemption to unresolved.
2.
Compensatory Action As described in our letter dated March 14, 1986, an Operations Memo has been issued to all Plant operators emphasizing the importance of activating the Recirculation Pump Room sprinklers upon receipt of an alarm from any of the detectors in this Room (in conformance with Big Rock Point Plant Alarm Procedures ALP 1.6).
This actuation involves opening the sprinkler head supply valve via a hand switch located in the Control Room. The sprinkler heads are the fusible link type and are designed to open at 250*F.
Plan for Resolution The calculation of the temperature rise in the Retirculacion Pump Room due to an oil fire has been re-performed, and is currently being checked by an independent technical reviewer. Based on the final result of this recalculation, appropriate corrective action, if any, will be identified and submitted to the NRC by June 1, 1986.
If the recalculation results in a Room temperature rise that supports the original exemption request, the corrected calculation will be submitted to the NRC for review and approval by May 1, 1986.
OC0486-0072-NLO4
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Director, Nuclear Reactor Regulation 7
Big Rock Point Plant Fire Protection-Items on Non-Compliance April 14, 1986 3.
Comprehensive Fire Protection Summary Document for the Big Rock Point Plant.
A comprehensive fire protection summary document will be submitted to the NRC before startup from the upcoming refueling outage (startup is currently planned for Dece:aber,1986). This summary will include an updated Fire Hazards Analysis and tabulation of the bases and assumptions which support the Analysis, all pertinent documentation and/or an index of fire protection documents (eg, correspondence between Consumers Power Company and the NRC, procedures, surveillances, training programs), the Safe Shutdown Summary, and revised plant system descriptions which describe fire protection equipment.
Kenneth W Berry Director, Nuclear Licensing CC-Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point OC0486-0072-NLO4