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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 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 ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted 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 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) 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 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 ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily 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 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) 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 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999 Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable 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 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 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 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 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 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 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 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999 Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable 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 Plant'S 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 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 ML20059B6221990-08-22022 August 1990 Forwards Missing Pages 25 & 26 Omitted from Facility Decommissioning Funding Rept,Consisting of Attachment a to Exhibit E 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 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 ML20055E0211990-06-29029 June 1990 Requests NRC Approval of Encl Simulation Facility Application for Plant,Per 10CFR55.45(b) 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 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 ML20246J1721989-08-30030 August 1989 Forwards Semiannual Radioactive Effluent Release & Waste Disposal Rept,Jan-June 1989 & Rev 4 to Offsite Dose Calcuation Manual 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 ML20244A5411989-04-0707 April 1989 Submits Supplemental Response to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers (Mcb). Justification for Continued Operation Will Not Be Prepared Since Traceability of in-stock & Installed Mcbs Established ML20247P3431989-03-31031 March 1989 Forwards Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Confirms That Requested Actions 1,2,3,4,6 & 7 Completed & Testing & Reporting Re Action 5,will Be Completed within 30 Days After Startup ML20246P3891989-03-22022 March 1989 Forwards Emergency Plan Exercise Scenario for 890523 Exercise.Comments on Scenario Should Be Submitted No Later than 890424 to Allow Mod of Package & Controller Preparation.W/O Encl ML20235S8991989-02-28028 February 1989 Forwards Semiannual Radioactive Effluent Release & Waste Disposal Rept for Jul-Dec 1988 & Revised Semiannual Radioactive Effluent Release Rept for Jan-June 1988 W/Actual Data Replacing Estimated Values for Apr-June 1988 ML20235R7701989-02-27027 February 1989 Forwards Integrated Plan,Semiannual Update 10.Issues Added to Plan Include,Rewiring CRD Accumulator Pressure Switch & Leak Detector Schemes & Evaluate Instrument Air Sys Per Generic Ltr 88-14 ML20235R7761989-02-27027 February 1989 Responds to NRC Re Violations Noted in Insp Rept 50-155/88-26.Concurs That Potential Weakness Did Exist W/ Respect to Identifying Critical Performance Parameters for Improvement of Equipment Replacement Program ML20235T5211989-02-24024 February 1989 Advises That Payment of Civil Penalty Imposed by 880922 Order Will Be Submitted on 890301,per NRC 890131 Denial of Util 881201 Request for Mitigation of Subj Penalty ML20235R9151989-02-22022 February 1989 Forwards Description of Emergency Exercise Scope & Objectives Scheduled for 890523 ML20235Q0931989-02-20020 February 1989 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. During 1989 Refueling Outage,Instrument Air Sys Will Be Removed from Svc for Maint & Air Dryer Replacement ML20235N8411989-01-17017 January 1989 Forwards Endorsements 119 & 120 to Nelia Policy NF-117. Endorsement 119 Reflects 1989 Advanced Premium & Endorsement 120 Amends Condition 4 of Policy ML20235N8211989-01-17017 January 1989 Forwards Endorsement 4 to Nelia Certificate NW-53 & Maelu Certificate MW-137 ML20196A1631988-12-0101 December 1988 Requests Commission Reconsider Amount of Proposed Fine for Imposed Civil Penalty for Violation Re Environ Qualification of Electrical Equipment Deficiencies.Proposed Fine Unreasonable for Plant Size & Age 1990-09-07
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~ Consumers
@MERlH nlKNNEAN'E MEDGRESE Power General Offees: 1945 West Pernali Road, Jackson, MI 49201 e (517) 7881217 nw.rieu w soen .
Senior Vke President kergy Supply January 20, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
SALP 7 REPORT COMMENTS Consumers Power Company appreciates NRC effort in assessing the performance of Big Rock Point during the SALP 7 period. Of special note was Mr. Paperiello and the SALP Board holding the presentation in Charlevoix,' Michigan, which permitted an increased attendance of Consumers Power Company personnel responsi-ble for the operation of Big Rock Point. The direct communication was a valuable part of the overall SALP process, and it will assist us in planning future strategies and' activities to achieve excellence in performance.
Following the presentation and review of the SALP 7 Report, Consumers Power Company provides the following comments.
A. Plant Operations No Comments.
B. Radiological Controls Unresponsiveness to NRC initiatives and concerns for fuel inspections was never our intent. Only after carefully examining previous cycles' fuel failures, current indicators, and personnel doses was the decision made not to inspect fuel. We were confident that the fuel causing the failures was being discharged and not used in Cycle 22. In the spirit of ALARA, the possibility was great for receiving more dose from fuel inspections than the fuel failures we had been experiencing. Results of ultrasonic inspections and next cycle performance substantiated our original evaluation that all leaker bundles were disr.harged. Paragraph six (6) of this section incorrectly refers to "... gaseous releases... continued to be about a factor of 6 higher than normal." After the Cycle 22 Refueling Outage (March, 1987) gaseous release rate was restored to normal and currently no leaking fuel is evident.
It is true that a water chemistry control program based on BWR Owners Group Guidelines was not formalized, however, virtually every chemistry parameter is within these guidelines and we feel confident that plant management would take the appropriate measures if these parameters were above the d0 OC0188-0016-NLO2 8801270047 880120 PDR ADOCK 05000155 h \
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Nuclasr Regulatory Commission 2 Big Rock Point' Plant SALP 7 Report Comments January 20, 1988 "action levels" of the guidelines even though they were not proceduralized.
The applicable guidelines will be incorporated into plant procedures over the next procedure review cycle.
We note NRC concerns and have implemented improvements in the ALARA and Radiation Work Permit programs and frisking equipment / practices since the assessment, and will continue efforts to further reduce dose and contamin-ation incidents.
C. Maintenance Consumers Power Company utilized extensive resources in establishing a "good faith" effort in complying with the EEQ and Appendix R regulations.
However, both the EEQ and Appendix R efforts evolved over a very long-time period allowing program managers, both. Consumers Power Company and NRC, to change during program development and compliance review. Decisions or compliance interpretations agreed upon at one stage have been changed or modified by individuals involved at later time periods. Consumers Power Company originally was involved in EEQ since 1975, with a LOCA task force, followed with the RDS Modifications, and with the Systematic Evaluation Program in the late seventies. Implementation Inspections did not commence until 1986. We believe this contributed to the EEQ issues dealing with l M0-7068 and Polyethylene and Butyl rubber cables. Consumers Power Company still believes that M0-7068 and the cables were capable of performing their safety function, however, we agreed to replace the components rather than continuing to debate the issues.
Big Rock Point continues to have an effective maintenance performance history as evidenced by historical plant availability and number of forced outages. Reactor trips from power have been minimal and the plant material condition has been noted as very good by the NRC, INF0, and Insurance Inspectors. During this SALP period Big Rock Point initiated and recently completed a Maintenance Self-Assessment utilizing INPO guidelines.
Throughout the next SALP period we will be implementing changes in our Maintenance Programs to improve the high priority areas identified in the self-assessment. These will further strengthen our maintenance performance.
In addition, several major pump and motor overhauls are planned for the upcoming refueling outage. The main feedwater pumps, turbine / generator, and a service water pump have been completed in the recent past. Over the next few years, two to three major pump overhauls per year are planned.
Big Rock Point will continue to monitor equipment performance and industry maintenance practices toward enhancing existing Maintenance programs.
D. Surveillance One inaccuracy existed in paragraph 3 of this section with regard to not performing a surveillance test (Service Test) on the station battery. A Technical Specification Change Request submittal dated December 22, 1986, which is still under NRR review, modified the Service Test design time interval to resolve errors as described in LER 86-004. Consumers Power OC0188-0016-NLO2 I
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-SALP 7 Report Comments January 20, 1988 Company agreed to implement this proposal into testing scheduled for the j 1987 Refueling Outage. .The modified surveillance test was completed satisfactorily during the outage.
'E. Fire ~ Protection The NRC concern on lack of plant staff Appendix R understanding is related to the duration of the review and implementation. As discussed above in Section C, the effort extended over a long time period (approximately 1978-1986). Because of the long time interval the need existed _ for several technical-level meetings with staff and consultant personnel to review extensive submittals to understand the safe shutdown paths for Big Rock Point in complying with the Appendix R requirements. Although further NRR review was needed and one additional exemption was required, overall the post-fire safe shutdown methods met the requirements for Appendix R. Since the inspection, documentation has been improved and fire plans strengthened to enhance the capability of Big Rock Point to mitigate the effects of a plant fire.
F. Emergency Preparedness No comments.
G. Security In response to NRC concerns regarding equipment aging, the 1987 CCTV Upgrade Project was completed by year-end. Existing equipment was repaired, cleaned or replaced. Two additional CCTV cameras and new lights were installed and some existing lights were repositioned. A new metal detector and X-ray machine were purchased for installation in the Lobby of the Security Building.
In response to NRC concerns regarding an increase in personncl errors, several methods of monitoring personnel performance have been initiated in an effort to identify exceptional as well as weak performance. These methods allow trending errors and pinpointing the causes. Each First Lieutenant on shift is now committed to evaluating his shift personnel on a weekly basis and documenting the results on a "Personnel Evaluation Form."
They are committed to one planned and one unplanned evaluation each week.
Drills are conducted twice per month on each shift using adopted scenarios for contingencies. Individuals with recurring performance problems are retrained when needed and counseled or disciplined when applicable.
A new method of reviewing Logs has been established to track documentation errors. This will ensure that proper logging is being accomplished.
A full review of all site security manuals and routine job information sheets is being implemented to improve performance in the Security area.
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r Nuclesr.Rsguistory Commission' 4 Big: Rock Point Plant SALP.7 Report Comments January 20. 1988 CH. Outages No comments.
I. Quality Programs and Administrative Controls Affecting Quality No comments.
J. Training and Qualification Effectiveness Training and Qualification Effectiveness was evaluated as a. category 2 - a rating judged equivalent in performance to the previous assessment period which at that time had received a category I rating. While we do not take issue with the lowering of a previously assessed category, a review of the training results completed during this SALP period leads us to conclude training warrants a category 1 assessment.
In response to the statement "While employees received some general worker training and on-the-job instruction, management made little progress in upgrading the mechanical / electrical staff's skill levels, a condition noted in the previous assessment period" on page 10 under maintenance summary; we believe that maintenance training has been aggressively pursued. We have doubled the training time per repairworker from SALP 6 to SALP 7. During the SALP 7 period, we provided.443 student days of Mechanical / Electrical skills training and 108 student days of Safety training. This is a signif-icant investment of time dedicated for upgrading the skills of a maintenance staff of 14 repairmen. All of this instruction time was dedicated to strengthening the skills of our maintenance staff. This represents an investment of 13% of the repairmen's time for training.
We do not concur with the statement "Skill training that was scheduled during the assessment period was frequently cancelled because of plant activities..." on page 23 under the training summary. Our records indicate that there were no cancellations. There was some rescheduling of courses, but all courses originally scheduled were eventually completed. The percentage of courses required to be rescheduled was relatively low at 7.6%
for the entire SALP 7 period, and was due to unforeseen plant outages.
Also, on page 22 of the training summary, further clarification is in order in response to the statement "Skill training and worker protection training was too general, not nuclear plant specific, and did little to enhance the effectiveness of the maintenance staff". Skills training is not always required to be nuclear plant specific, however during the period, 121 student days of Big Rock Point specific training was provided to the maintenance staff. It should also be noted that all of the tasks required of the Maintenance repairmen were addressed via classroom training, on-the-job training, and shop practices during the SALP 7 period. During the SALP 7 period, a major effort was made to modify training materials to assure that all tasks were addressed as identified on the Big Rock Point Plant Specific Task List. It is recognized that additional systems training is necessary for improved worker understanding and performance. At the end OC0188-0016-NLO2
. Nuclear Rigulatory Commission 5 Big Rock Point Plant
-SALP 7 Report Comments January 20, 1988 of the SALP period the second round of systems training was started for the least senior repairworkers at the plant.
Finally, on page 22, the statement "The Procedural requirements for both required and on-the-job training were not met and the Maintenance Depart-ment Training Program has not been evaluated and accredited by INP0" is somewhat misleading. INPO evaluation and accreditation was not planned to occur during this SALP. period. The INPO evaluation was conducted in October 1987 and after the fourteen man team completed their evaluation they proposed zero recommendations in maintenance training. INPO considered the program to be very good and stated our program demonstrated a strong commitment by the plant. Essentially all of the procedural requirements for classroom and OJI were complete and in place prior to the end of the SALP 7 period. Formal INPO Board approval is tentatively scheduled to occur in the first quarter 1988.
We also reiterate the fact that initial or replacement license candidate and requalification license candidate classes both achieved a 100% pass rate during the SALP period. This is the sixth license class to achieve a 100% pass rate. It is a record we are very proud of and speaks for itself as to the caliber of Big Rock Point training.
We believe the above results demonstrate that management commitment to training is evident to assure that our training provides the skills and knowledge necessary to continue to operate Big Rock Point as a safe and eliable plant. We also believe that the training results completed during the SALP 7 period supports a Category 1 assessment.
K. Licensing Activities Consumers Power Company Management and staff will continue to support and utilize the Integrated Living Schedule (ILS) in accordance with License requirements to evaluate and prioritize workload. We also plan on working with Region III personnel in the near term, on exploring ways to use the ILS process in prioritizing inspection based plant betterments.
Consumers Power Company understands that high quality and timely licensing documents are essential in maintaining a sound licensing basis for Big Rock Point and continue to support this objective. Corporate and plant licensing personnel will continue to advocate frequent meetings with NRR and Region personnel to understand and prioritize issues from both a NRC and Consumers Power Company perspective. Our goal will be to recognize unique or complex technical issues and ensure that related submittals are timely with suf-ficient detail to minimize interaction.
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Nuclser Rtgulatory Commission 6 Big Rock Point Plant-SALP 7 Report-Comments January 20, 1988 Consumers Power Company believes the overall SALP evaluation presented a balanced assessment of plant performance during the appraisal period. The issue concerning resource allocation that was raised in the SALP report is one to which we will remain sensitive, but Consumers Power Company strongly.
believes that management commitment to excellence cannot be measured by the amount of money spent on a plant. We will continue to work closely with the NRC staff in communicating the establishment of priorities and schedules for action to improve plant safety and performance.
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Frederick W Buckman Senior Vice President Energy Supply CC Administrator, Region III, NRC NRC Resident Inspector - Big Rock Point l
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