|
---|
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
[Table view] |
Text
I COI1 Sum 8IS Power x,.,%
b a ikensing namnenus enaeuss General Offees: 1945 West Parnall Road. Jackson, MI 49201 . (517) 788 1636 September 2, 1986 James G Keppler, Administrator Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
RESPONSE TO INSPECTION REPORT 50-155/85022 - FIRE PROTECTION Three items of noncompliance were identified in Inspection Report 50-155/85022. One of the noncompliance items, identified as Item 3 in the Notice of Violation enclosed with the inspection report cover letter, con-cerned the storage of combustibles. With reapect to Item 3, the cover letter stated that the inspection showed that action had been taken to correct and prevent recurrence of that noncompliance and that the NRC had no further questions regarding Item 3 at this time.
This letter provides Consumers Power Company's response to the two noncompli-ances identified as Item 1 and Item 2 in the Notice of Violation enclosed with
! the Inspection Report. Attachment I provides a number of corrections and comments generated during our review of the subject Inspection Report.
ITEM 1 (NONCOMPLIANCE 155/85022-03) 10 CFR 50.48(b) in part requires that all nuclear power plants licensed to operate prior to January 1, 1979, shall satisfy the applicable requirements of Appendix R to this part, including, specifically, the requirements of Section III.G, Fire Protection of Safe Shutdown Capability.
Contrary to the above, the licensee failed to request an exemption from the requirements of Section III.G.2 of Appendix R after determining that the fire protection features in the Screenwell and Pump House did not meet the specific
, requirements of Section III.G.2 in that no fire suppression system was in-stclied in this area. In addition, no alternate shutdown capability was l
l provided for the Screenwell and Pump House.
i 8701090375 860902 i PDR ADOCK 05000155 i
G PDR OC0886-0139-NLO2 SEP L Y \\
5 20
9 Admi'nistrator, Region III 2 Big Rock Point Plant Response to IEIR 85-022 - Fire Protection September 2, 1986 Corrective Actions Taken and the Results Achieved As discussed in the July 18, 1986 meeting with the NRC at the Plant site, an exemption request to 10 CFR 50 Appendix R.Section III.G.2 was submitted to the NRC by letter dated July 1, 1986. Until such time as this item is re-solved, compensatory measures in the form of periodic surveillances have been implemented. This compencatory measure was described in our letters dated April 14, 1986 and April 23, 1986.
Corrective Actions to be Taken to Avoid Further Violations Compensatory action in the form of periodic surveillances will be continued until this item is resolved.
Date When Full Compliance Will Be Achieved Full compliance will be achieved when this iten is resolved with the NRC.
Until that time, adequate compensatory measures are being taken.
ITEM 2 (NONCOMPLIANCE 155/85022-04) 10 CFR 50, Appendix B, Criterion XVI requires corrective action measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, defective material and equipment, deviations, and nonconformances are promptly identified and corrected. In the case of signif-icant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.
Consumers Power Company Quality Assurance Program for operational Nuclear Power Plants, Section 5.9 states, " Conditions adverse to fire protection, such as test failures, malfunctions, defective components and uncontrolled combus-tible material and fire incidents, are documented and corrective actions are accomplished according to QAPP 17-51."
Contrary to the above, the licensee identified that a problem existed with the eight hour emergency lighting system on August 16, 1984, however, the lighting system deficiencies still existed on May 8, 1986.
Corrective Actions Taken and Results Achieved As discussed in our April 14, 1986 letter to NRC and modified by our August 12, 1986 letter, a modification is in progress which will increase the capacity of the emergency lighting units. The modification involves adding an additional battery unit at each location and removing one of the existing two lamps and connecting it to the new battery. Each battery will power only one 12-watt lamp instead of the previous two, thereby effectively doubling the time rating on each unit to insure the required eight hour operability.
As of the date of this letter, all the new batteries have been installed and the lighting units are operational.
OC0886-0139-NLO2
. ' Admihistrator, Region III 3 Big Rock Point Plant Response to IEIR 85-022 - Fire Protection 1 September 2, 1986 Corrective Actions to be Taken to Avoid Further Violations The installation of two batteries per 2-bulb inside lighting unit and yearly 8-hour testing of each unit will prevent recurrence. The delay experienced in determining proper corrective action is considered abnormal and was the result of a design deficiency which required the consideration, installation, and testing of other proposed modifications. Therefore, we consider this to be an isolated incident.
Date When Full Compliance Will Be Achieved Full compliance for the inside emergency lighting units has been achieved as of the date of this letter.
Clarification ,
1 The Notice of Violation and the Inspection Report refer to Section 5.9 of Consumers Power Company Quality Assurance Program for Operational Nuclear Power Plants, and then further reference QAPP 17-51. These references are outdated. The correct current references are the Big Rock Point Fire Protec-tion Program Report,Section IV.C.8 and the Consumers Power Company Quality Assurance Program Description for Operational Nuclear Power Plants, CPC-2A, Section 16.
I l Kenneth W Berry Director, Nuclear Licensing i CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Big Rock Point Attachment 1
i i
1 OC0886-0139-NLO2
9 ATTACHMENT I Consumers Power Company Big Rock Point Plant Docket 50-155 CLARIFYING COMMENTS AND CORRECTIONS DURING REVIEW OF INSPECTION REPORT 50-155/85022 September 2, 1986 O
4 Pages AT0886-0139-NLO2
ATTACHMENT I During our review of the inspection report, a number of corrections and clarifying comments were generated. This information is provided in order to ensure an accurate understanding of fire protection measures at the Big Rock Point Plant.
(1) Page 9 Section 3.a
.The list of systems required for shutdown includes:
- Demineralized Water Tank (pump cannot be connected to EDG)"
COMMENT: It should be clarified that for the cases where the demineralized water system is used for emergency condenser shell makeup, the demineralized water pump can be connected to the emergency diesel generator (EDG) through the manual alignment of breakers in the electrical equipment room. In the case of a screenhouse fire, the standby diesel generator can be connected to the demineralized water pump in the same fashion using a different breaker alignment. These actions are covered by existing procedures dealing with loss of offsite power.
(2) Page 10, Section 3.a(1)
The report states that " Loss of offsite power also causes the reactor to trip. In the event that offsite power is not lost, the reactor can be tripped by throwing the breakers for the control rod drive pumps".
CORRECTION: Loss of station power, not necessarily offsite power, causes the reactor to trip. Opening the breakers supplying the reactor protection system will scram the reactor. Opening the CRD pump breakers would not cauee a scram.
(3) Page 10, Section 3.a(2)
In the description of inventory control, if the control rod drive pumps are unavailable, low pressure makeup is provided by the fire system through the core spray valves. The report states "the plant would remain in hot shutdown in this case".
COMMENT: The plant would remain in hot shutdown if both of the reactor cooling water pumps were also unavailable due to the fire.
(The cables for the CRD pumps run within 20 feet of the RCW pumps.) If a reactor cooling water pump remains available, such as for a fire in the control rod drive pump room, the plant would proceed to cold shutdown.
AT0886-0139-NLO2
2 (4) Page 11, Section 3.a(3)
The report states "the water on the shell side of the EC is allowed to boil off and is discharged into atmosphere through a high stack".
4 Minor Correction: The emergency condenser vents at the top of the containment sphere, not through the plant stack.
(5) Page 12, Section 3.a(3)
The fourth paragraph on this page states that the remotely operated solenoid valve for EC makeup was not identified in the March 8, 1983 SER.
CORRECTION: Page 5 of Enclosure 2 of the March 8, 1983 SER identifies the fact that the " auxiliary shutdown control station will contain controls for the ... valves for firewater make-up to the emergency condenser".
(6) Page 13, Section 3.a(5)
This section deals with support systems to maintain hot shutdown, "re-quired for either method of shutdown, ie, use of the EC or use of the RDS/ core spray systems, except as noted:
(a) Domineralized water system including air compressor and air-operated
- demineralizer flow isolation valve (for EC method only)."
COMMENT: Note that this system is used for EC makeup whenever it is available. If it is not available, the firewater system is used through the firewater makeup solenoid valve.
Note also that EC makeup is used to achieve cold shutdown rather than maintain hot shutdown in almost all cases, as it
! lowers the primary system pressure to the point where the shutdown cooling system is put into service. EC makeup is l
used to maintain hot shutdown only in cases where normal cold I
shutdown pumps are lost due to the fire and hot shutdown is l maintained rather than use ' feed and bleed' to achieve cold i shutdown (eg, loss of both shutdown cooling pumps), or in cases where cold shutdown could be achieved but hot shutdown is maintained only for convenience.
(b) " Firewater system including core spray valves and flow paths (RDS method only)".
COMMENT: This system can also be used for low pressure primary system makeup in the EC method by opening the core spray valves manually.
(c) " Control rod drive pumps and condensate storage tank".
i AT0886-0139-NLO2
3 COMMENT: This system is never used in conjunction with the RDS/ core spray method of shutdown, only for the EC method.
(d) "AC power from the EDG" COMMENT: For hot shutdown, for the EC method, the EDG is used only for powering the control rod drive pump.
(e) "AC power from the SDG (see Section 4.2.2)"
COMMENT: There is no nection 4.2.2. Apparently refers to Section 3.b.2.
(7) Page.14, Section 3.a(6)
The report states that "each fire pump is capable of 1200 gym at 115 psia".
COMMENT: Each fire pump is rated at 1000 gpm at 110 psig. Note that the intent of the analyses referred to on this page was merely to show that the flow rate necessary to remove decay heat after two or three days is very small, less than 50 gpm.
(8) Page 15. Section 3.a(6)
The report advises against using the CRD pumps in place of the fire pumps for feed and bleed, becaase of the high discharge pressure capability of the purps. It states that " based on the above, operating procedures for
, feed and bleed, procedures should be written and implemented accordingly".
COMMENT: The only procedures in place that would be associated with a feed and bleed method of operation are the existing proce-dures dealing with the RDS and core spray stems. No mention is made of using a CRD pump. In addition, existing technical.
specifications contain the restrictions on acceptable cool-down limitations.
- (9) Page 19, Section 3.b(2) j
^
The report states that " diesel-driven fire pump was proposed to be used to provide makeup to the EC shall side and also to the FCS by means of the DC powered core spray valves in conjunction with the DC powered RDS".
CORRECTION: It is true that in this case (loss of the EDG) the DC core spray valves would be used with the fire pump for PCS makeup, but not in conjunction with RDS. RDS is not used ic this 4 scenario.
AT0886-0139-NLO2
4 (10) Page 24, Section 5.b(3)
The table lists M07062 as disabled c.losed.
CORRECTION: The resolution for M07062 should be the same as for M07052, ie, reroute cable for coil actuation. It is not disabled closed.
(11) Page 28, Section 7.b(2)
The first sentence states "..... a postulated fire in the Emergency Diesel Generator Rcom that involves both redundant fire water pumps, the use of .....".
CORRECTION: The sentence should read .... a postulated fire in the Emergency Diesel Generator Room or in the Screenhouse, the use of .... (The screenhouse contains portions of the EDG feeder cable.)
t AT0886-0139-NLO2
-- -