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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:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20206N2621999-05-11011 May 1999 Application for Amend to License DPR-6 to Delete from Defueled Ts,Subsection 1.16,change Definition of Site & Other Associated Editorial Changes ML20217F5191998-03-28028 March 1998 Application for Amend to License DPR-6,per 10CFR50.90 Re Security Plan.Encl Withheld ML20138G1961997-04-30030 April 1997 Application for Amend to License DPR-6,requesting Name Change from Consumers Power Company to Consumers Energy Company, to Reflect Broader Scope of Energy Resources Available Through Company ML20138A9061997-04-22022 April 1997 Application for Amend to License DPR-6,requesting Change to TS to Withdraw Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20134H6281996-11-0707 November 1996 Application for Amend to License DPR-6,adding New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4611996-10-15015 October 1996 Application for Amend to License DPR-3,implementing Option B to Allow Use of Type a Test (Containment) Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining Boundaries) & Type C Test ML20056G3811993-08-24024 August 1993 Application for Amend to License DPR-6,revising 930719 Original Change,Reflects Revision to 10CFR50.36(a)(2) Re Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20128D7081993-01-29029 January 1993 Application for Amend to License DPR-6,revising TS to Reflect Administrative Changes in Engineering,Offsite Review & QA Organization ML20059A2091990-08-14014 August 1990 Application for Amend to License DPR-6,reflecting Administrative & Organizational Changes ML20247L0891989-05-25025 May 1989 Application for Amend to License DPR-6,to Align Specs to 10CFR50,App J Requirements That Permit Removal of 24 H Duration Restriction on Integrated Leak Rate Test ML20205P6231988-10-24024 October 1988 Application for Amend to License DPR-6,deleting Tech Spec Requirements to Calibr Portable Gamma & Neutron dose-rate Measuring Instruments at Least Once Every 3 Months & Instead Follow ANSI N323-1978 ML20154S6371988-09-22022 September 1988 Application for Amend to License DPR-6,allowing Independent Review & Audit Functions by Independent Organizational Unit Rather than Standing Committee.Changes Consistent W/Bwr STS, ANSI N18.7-1976 & ANS 3.1-1987.Fee Paid ML20154P2111988-09-21021 September 1988 Application for Amend to License DPR-6,revising Tech Specs to Provide Clarification & Consistency by Reflecting Administrative & Editorial Corrections.Fee Paid ML20154D4761988-09-0808 September 1988 Application for Amend to License DPR-6,proposing Removal of Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes.Fee Paid ML20150C7831988-07-0505 July 1988 Application for Amend to License DPR-6,changing Tech Specs Re Reactor Depressurization Sys (Rds) Surveillance Testing, Eliminating Quarterly Partial Stroke Exercising of Rds Depressurizing Valves ML20148H6271988-03-22022 March 1988 Application for Amend to License DPR-6,changing Tech Specs Re Frequency of Reactor Depressurization Sys Depressurizing Valve Testing ML20237B9661987-12-14014 December 1987 Application for Amend to License DPR-6,removing Numerical Designator from I-type Fuel for Fuel Operating Cycle.Fee Paid ML20236N5021987-11-0909 November 1987 Application for Amend to License DPR-6,changing Tech Specs Administratively to Reflect Features & Terminology Used W/ New out-of-core Power Range Nuclear Instrumentation ML20236B3221987-07-23023 July 1987 Application for Amend to License DPR-6,consisting of Accumulated Administrative Changes ML20210C5961987-02-0404 February 1987 Application for Amend to License DPR-6,changing Tech Spec Section 5.2.1.b by Adding Table of Uncertainty Factors Associated W/Analysis of Core thermal-hydraulic Parameters Heat Flux,Maplhgr & Max Bundle Power ML20212F0301986-12-30030 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Include Second Scram Dump Tank Vent & Drain Valve ML20207C9541986-12-22022 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reduce Station Battery Design Time Interval from 8 to 2 H. Fee Paid ML20215F9941986-12-17017 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Add Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R & Generic Ltr 81-12.Request Supersedes 860421 Application ML20210E5141986-12-17017 December 1986 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Tech Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20215C7211986-12-0505 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reflect Use of New Hybrid Control Rods Mfg by Nucom,Inc & to Include Reload I-2 Fuel.Fee Paid ML20206M5081986-08-15015 August 1986 Application for Amend to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation ML20203P8021986-05-0101 May 1986 Application for Amend to License DPR-6,revising Tech Specs to Ensure Consistency w/831230 Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6461986-04-21021 April 1986 Application for Amend to License DPR-6,changing Tech Specs Re Alternate Shutdown Battery Sys Operability & Surveillance Requirements ML20154K0181986-03-0404 March 1986 Application for Amend to License DPR-6,changing Tech Specs by Adding Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R ML20137V9621985-09-30030 September 1985 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Components of Alternate Shutdown Sys Installed in Accordance w/10CFR50,App R ML20132F4561985-09-24024 September 1985 Revised Application for Amend to License DPR-6,changing I1 Fuel MAPLHGR Limits,Per 850816 Request,In Order to Implement Operating Limits for Reload Il Fuel ML20135B7971985-09-0303 September 1985 Application for Amend to License DPR-6,supplementing 741101 Proposed Tech Spec Change to Eliminate Min Control Rod Withdrawal Rate Limit ML20134E3011985-08-16016 August 1985 Application for Amend to License DPR-6,changing Tech Specs to Implement Reactor Operating Limits for Reload I1 Fuel ML20133M1131985-08-0505 August 1985 Application for Amend to License DPR-6,changing Tech Specs to Implement Staff Reorganization ML20132B7311985-07-19019 July 1985 Revised Application for Amend to License DPR-6,providing Tech Specs for Containment Pressure Monitor & Containment Water Level Monitor,Per NUREG-0737,Item II.F.1 ML20128B9131985-06-27027 June 1985 Application for Amend to License DPR-6,changing Tech Specs to Allow Operation of Plant Between Refueling Shutdowns W/O Potential of Requiring Surveillance Test to Be Performed.Fee Paid ML20126A0521985-06-0707 June 1985 Application for Amend to License DPR-6,incorporating Requirement to Adhere to Encl Plan for Big Rock Point Integrated Assessment. Fee Paid ML20128E4931985-05-24024 May 1985 Revised Application for Amend to License DPR-6,revising 840730 Tech Spec Change Request by Renumbering Definition Section 1.2.8 to 1.2.14 Re Administrative Controls ML20058E4011982-07-20020 July 1982 Application to Amend License DPR-6,changing Tech Specs Re Safety Mgt Function ML20058E3881982-07-20020 July 1982 Application to Amend License DPR-20,revising Tech Specs Re Safety Mgt Function ML20054J7321982-06-25025 June 1982 Application to Amend License DPR-6,changing Tech Specs to Change Technical Advisor from Shift to 24-h on-call Schedule 1999-05-11
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20206N2621999-05-11011 May 1999 Application for Amend to License DPR-6 to Delete from Defueled Ts,Subsection 1.16,change Definition of Site & Other Associated Editorial Changes ML20198K6581998-12-24024 December 1998 Amend 120 to License DPR-6,changing License DPR-6 & App a, TS to Reflect Permanetly Shutdown & Defueled Status of Plant ML20217F5191998-03-28028 March 1998 Application for Amend to License DPR-6,per 10CFR50.90 Re Security Plan.Encl Withheld ML20141J8651997-08-14014 August 1997 Amend 119 to License DPR-6,revising Plant License & TS to Reflect Company Name Change from CPC to Consumers Energy Co ML20138G1961997-04-30030 April 1997 Application for Amend to License DPR-6,requesting Name Change from Consumers Power Company to Consumers Energy Company, to Reflect Broader Scope of Energy Resources Available Through Company ML20138A9061997-04-22022 April 1997 Application for Amend to License DPR-6,requesting Change to TS to Withdraw Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20137J9321997-04-0202 April 1997 Amend 118 to License DPR-6,revising TS 4.2.9,to Add Additional Air Compressor ML20134H6281996-11-0707 November 1996 Application for Amend to License DPR-6,adding New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4611996-10-15015 October 1996 Application for Amend to License DPR-3,implementing Option B to Allow Use of Type a Test (Containment) Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining Boundaries) & Type C Test ML20058A1511993-11-15015 November 1993 Amend 112 to License DPR-6,changing TS to Implement Reorganization of Plant Staff ML20057E1951993-10-0505 October 1993 Amend 111 to License DPR-6,changing Reporting Requirements for Effluent Releases from Semiannual to Annual ML20056G3811993-08-24024 August 1993 Application for Amend to License DPR-6,revising 930719 Original Change,Reflects Revision to 10CFR50.36(a)(2) Re Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20056E1651993-08-16016 August 1993 Amend 110 to License DPR-6,clarifying TS Re Undervoltage Breakers in RPS ML20128D7081993-01-29029 January 1993 Application for Amend to License DPR-6,revising TS to Reflect Administrative Changes in Engineering,Offsite Review & QA Organization ML20059A2091990-08-14014 August 1990 Application for Amend to License DPR-6,reflecting Administrative & Organizational Changes ML20246D2351989-08-16016 August 1989 Amend 100 to License DPR-6,revising Tech Specs to Provide for New Organizational Unit Entitled Nuclear Safety Svcs Dept to Discharge Offsite Safety Review Functions Instead of Nuclear Safety Board ML20245H8341989-07-28028 July 1989 Amend 98 to License DPR-6,requiring Compliance W/Amended Physical Security Plan ML20248C0571989-05-31031 May 1989 Amend 97 to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys to Tech Spec Sections 11 & 12 & Including Tech Specs for Active Fire Barriers & Fire Detection Instrumentation ML20247L0891989-05-25025 May 1989 Application for Amend to License DPR-6,to Align Specs to 10CFR50,App J Requirements That Permit Removal of 24 H Duration Restriction on Integrated Leak Rate Test ML20246L8191989-05-0202 May 1989 Amend 96 to License DPR-6,revising OL to Allow for Increase in Amount of Byproduct Matl Plant May Possess & Use from 10.5 to 45 Ci Cs-137,as Sealed Sources ML20245F8251989-04-14014 April 1989 Amend 95 to License DPR-6,changing Tech Specs to Include Second Vent & Second Drain Valve to Scram Dump Tank ML20235J0231989-02-15015 February 1989 Amend 94 to License DPR-6,revising Station Battery Surveillance Test Time from 8 to 2 H ML20205S1241988-11-0404 November 1988 Amend 93 to License DPR-6,modifying Tech Specs by Replacing Requirements to partial-stroke Test Reactor Depressurization Sys Depressurizing Valves Quarterly W/Requirement to full- Stroke Test for Depressurizing Valves Each Outage ML20205P6231988-10-24024 October 1988 Application for Amend to License DPR-6,deleting Tech Spec Requirements to Calibr Portable Gamma & Neutron dose-rate Measuring Instruments at Least Once Every 3 Months & Instead Follow ANSI N323-1978 ML20154S6371988-09-22022 September 1988 Application for Amend to License DPR-6,allowing Independent Review & Audit Functions by Independent Organizational Unit Rather than Standing Committee.Changes Consistent W/Bwr STS, ANSI N18.7-1976 & ANS 3.1-1987.Fee Paid ML20154P2111988-09-21021 September 1988 Application for Amend to License DPR-6,revising Tech Specs to Provide Clarification & Consistency by Reflecting Administrative & Editorial Corrections.Fee Paid ML20154G1081988-09-14014 September 1988 Amend 92 to License DPR-6,modifying Paragraph 2.C.(5) of License Re Physical Security ML20154D4761988-09-0808 September 1988 Application for Amend to License DPR-6,proposing Removal of Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes.Fee Paid ML20150C7831988-07-0505 July 1988 Application for Amend to License DPR-6,changing Tech Specs Re Reactor Depressurization Sys (Rds) Surveillance Testing, Eliminating Quarterly Partial Stroke Exercising of Rds Depressurizing Valves ML20154J1871988-05-17017 May 1988 Amend 91 to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core Power Range Instrumentation ML20154H5251988-05-17017 May 1988 Amend 90 to License DPR-6,allowing Inclusion of All Reloads of I Fuel Design in Tech Specs ML20148H6271988-03-22022 March 1988 Application for Amend to License DPR-6,changing Tech Specs Re Frequency of Reactor Depressurization Sys Depressurizing Valve Testing ML20237B9661987-12-14014 December 1987 Application for Amend to License DPR-6,removing Numerical Designator from I-type Fuel for Fuel Operating Cycle.Fee Paid ML20236N5021987-11-0909 November 1987 Application for Amend to License DPR-6,changing Tech Specs Administratively to Reflect Features & Terminology Used W/ New out-of-core Power Range Nuclear Instrumentation ML20236B3221987-07-23023 July 1987 Application for Amend to License DPR-6,consisting of Accumulated Administrative Changes ML20211P1321987-02-19019 February 1987 Amend 89 to License DPR-6,revising Tech Spec Section 5.2.1.b to Add Table of Uncertainty Factors Re Analysis of Core Thermal Hydraulic Parameters for Reload I-2 Fuel & to Provide Footnotes Delineating Use of Values ML20211N5181987-02-17017 February 1987 Amend 88 to License DPR-6,revising Tech Spec Section 5.1 to Reflect Use of New Nucom,Inc Hybrid Control Rods in Cycle 22 Core ML20210C5961987-02-0404 February 1987 Application for Amend to License DPR-6,changing Tech Spec Section 5.2.1.b by Adding Table of Uncertainty Factors Associated W/Analysis of Core thermal-hydraulic Parameters Heat Flux,Maplhgr & Max Bundle Power ML20209H0481987-01-28028 January 1987 Amend 87 to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used in Conjunction W/Installation of New source-range Monitoring Instrumentation ML20212F0301986-12-30030 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Include Second Scram Dump Tank Vent & Drain Valve ML20207C9541986-12-22022 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reduce Station Battery Design Time Interval from 8 to 2 H. Fee Paid ML20215F9941986-12-17017 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Add Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R & Generic Ltr 81-12.Request Supersedes 860421 Application ML20210E5141986-12-17017 December 1986 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Tech Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20215C7211986-12-0505 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reflect Use of New Hybrid Control Rods Mfg by Nucom,Inc & to Include Reload I-2 Fuel.Fee Paid ML20206M5081986-08-15015 August 1986 Application for Amend to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation ML20211P3751986-07-11011 July 1986 Amend 86 to License DPR-6,adding Tech Spec Table Sentence Establishing Min Requirements for Shift Crew Composition During Various Operating Conditions ML20198A3801986-05-12012 May 1986 Amend 85 to License DPR-6,adding Definition for Reportable Event & Deleting Reporting Requirements Included in 10CFR50.72 & 50.73 ML20210P1651986-05-0606 May 1986 Amend 84 to License DPR-6,adding Condition to CRD Surveillance Testing Requiring Testing Prior to Startup Following Outages of More than 120 Days ML20203P8021986-05-0101 May 1986 Application for Amend to License DPR-6,revising Tech Specs to Ensure Consistency w/831230 Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6461986-04-21021 April 1986 Application for Amend to License DPR-6,changing Tech Specs Re Alternate Shutdown Battery Sys Operability & Surveillance Requirements 1999-05-11
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@ym AIEMAW5 PROGRE55 Consumers Power Kenneth W Berry Director Nuclear Licensing General Ot'eces: 1945 West Parnell Road, Jackson, MI 49201 . (517) 788 1636 Cecember 17, 1986 Director, liuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
TECHNICAL SPECIFICATION CHANGE REQUEST - ALTERNATE SHUTDOWN SYSTEM Attached are three (3) originals and thirty-seven (37) conformed copies of a request for change to the Big Rock Point Technical Specifications. This change request supersedes our change request dated April 21, 1986. The change request is being resubmitted to resolve concerns raised during NRC staff review of our previous submittals.
These proposed changes add technical specification operability and surveillance requirements for the alternate shutdown system installed in accordance with Apperdix R to 10CFR50 as required by Item 8(j) of Generic Letter 81-12. This change request also includes proposed technical specifications for the active fire barriers and the fire detection instrumentation for the new Auxiliary Shutdown Building.
Pursuant to 10CFR170.12(c) a check in the amount of $150.00 was attached to our September 30, 1985 submittal, hence no fee is remitted with the submittel.
(,,-
Kenneth W Berry m
- ~ }h P Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point Attachment __
8612240179 861217 00 PDR ADOCK 05000155 b
k OC1286-0194-NLO2 I
/-
6 0 3
CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter set forth, it is requested that the Technical Specifications contaired in the Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1, 1964, for the Big Rock Point Plant be changed as described in Section I.below:
l I. CHANGES A. Table of Contents Revise Section 12.0 of the Table of Contents to read as follows:
"12.0 Fire Protection Program ........................ 150-157d (Section 3.3.3.8/4.3.3.8) Fire Detection Instrumentation ............................ 150-151 (Section 3.7.11.1/4.7.11.1) Fire Suppression Water System ................... 152-153 (Section 3.7.11.2/4.7.11.2) Fire Spray / Sprinkler Systems .................... 154 (Section 3.7.11.5/4.7.11.5) Fire Hose Stations ................................... 155 (Section 3.7.12/4.7.12) Penetration Fire Barriers ................................... 156 (Section 3.7.13/4.7.13) Alternate Shutdown System ............................ 157-157b Bases .......................................... 157c-157d f
B. Section 11.3.5.3 and 11.4.5.3 Add the Alternate Shutdown Battery System to the specificaticn for Emergency Power Sources as follows:
11.3.5.3 EMERGENCY POWER SOURCES "A. For all reactor operating conditions except cold shutdown, there shall normally be available one 138 kV line, one 46 kV line, one diesel generator system, one statica battery system, four RDS uninterruptible power supplies including batteries and one alternate shutdown battery system, except as specified below:"
"A. 5. The station battery system and the alternate shutdown battery system shall be operable under all conditions except during cold shutdown. If the station battery or the alternate shutdown battery is inoperable, no actions shall be taken which result in a reactivity addition, except cooldown, or which might result in the primary coolant system being drained."
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Big Rock Point Plant 2 TSCR - Alternate Shutdown System 11.4.5.3 EMERGENCY POWER SOURCES "A. 1.(e) Verify the cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration for the station battery, the RDS batteries and the alternate shutdown battery.
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"A. 1.(f) Verify the cell-to-cell and terminal connec-tions are clean, tight, free of corrosion and coated with anti-corrosion material for the station battery, the RDS batteries, and the alternate shutdown battery."
"A. 1.(h) Verify that the capacity of the station battery, the RDS batteries and the alternate shutdown battery is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for the design time interval when the battery is subjected to a battery service test. The design time interval for the RDS batteries is one hour, eight hours for the station battery and eight hours for the alternate shutdown battery."
"A. 2.(b) Verify that the cell voltage is 22.0 volts and specific gravity is 21.2 of each cell of the station battery; and verify that the cell voltage is 26.0 volts and specific gravity is 21.2 on each cell of the RDS batteries; and verify that the cell voltage is 22.1 volts and specific gravity is 21.2 of each cell of the alternate shutdown battery."
"A. 3. (a) Verify the electrolyte level of each RDS battery pilot cell, the station battery pilot cell and the alternate shutdown battery pilot cell is between the minimum and maximum level indication marks.
(b) Verify the pilot cell specific gravity for RDS, station and alternate shutdown batteries corrected to 77*F, is 21.2.
(c) Verify the station battery pilot cell voltage is 22.0 volts, the RDS battery pilot cell voltage is 26.0 volts and the alternate shutdown battery pilot cell voltage is 22.1 volts.
(d) Verify the overall battery voltage is 2125 volts for the station battery, the RDS batteries and the alternate shutdown battery."
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Big Rock Point Plant 3 TSCR - Alternate Shutdown System "A. 5 Sixty Months - At least once per 60 months during shutdown, verify that the RDS batteries, the alternate shutdown battery and the station battery capacity is at least 80% of the manufac-turer's rating when subjected to a performance discharge test. This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test of Part 11.4.5.3.A.I.(h)."
C. Bases for Section 11.3.5.3 and 11.4.5.3 Add the following:
"The alternate shutdown battery supplies power to the main steam isolation valve, the emergency condenser outlet valves and other alternate shutdown equipment. The battery is sized such that loss of the charger does not affect operability of the battery for up to six (6) days at a minimum of 25*F (nine (9) days at minimum of 40*F)."
D. Section 3.3.3.8 Add to Table 3.3-8, the smoke detection instruments for the Alternate Shutdown Building, as follows:
"13. Alternate Shutdown Building 2 -
1" E. Section 3/4.7.12 Change the Limiting Conditions for Operation to read as follows:
"3.7.12 All penetration fire barriers including fire doors and fire dampers protecting safety-related areas shall be functional."
F. Section 3/4.7.13 i' Add the following specifications for the alternate shutdown system:
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Big Rock Point Plant 4 TSCR - Alternate Shutdown System
" PLANT SYSTEMS a 3/4.7.13 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITIONS FOR OPERATION 3.7.13 The alternate shutdown system (ASD) equipment shown in Table 3.3-9 shall be OPERABLE.
APPLICABILITY During power operation.
-ACTION With less than the minimum ASD equipment in Table 3.3-9 OPERABLE, restore the inoperable equipment to OPERABLE
< within 7 days, or provide equivalent shutdown capability and restore the inoperable equipment to OPERABLE within 60 days, or be shutdown as described in Section 1.2.5(a) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and shutdown as described in Section 1.2.5(a) and (b) within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
- The #1 control rod drive pump, its associated ASD power source and the two emergency condenser indicating lights are the ASD equipment considered to have equivalent shutdown capability.
SURVEILLANCE REQUIREMENTS 4.7.13.1 The ASD monitoring instruments shall be demonstrated OPERABLE by performing a check and a. calibration per Table 4.3-9.
4.7.13.2 Each transfer switch, power supply and control circuit shall be demonstrated OPERABLE at each major refueling shutdown
- by operating each actuated ccmponent from both the control room and the remote location.
4.7.13.3 At each major refueling shutdown
- perform a verification to insure that equipment (alternate power sources) needed to achieve and maintain cold shutdown is available.
4.7.13.4 The ASD battery charger shall be demonstrated OPERABLE by performing a weekly verification that the float voltage is greater than 130 volts.
j 4.7.13.5 The ASD battery surveillance requirements are contained i in Section 11.4.5.3.
- But no less than once every 18 months."
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Big Rock Point Plant 5 TSCR - Alternate Shutdown System
" TABLE 3.3-9 ALTERNATE SHUTDOWN SYSTEM EQUIPMENT INSTRUMENT READOUT LOCATION
- 1. Steam Drum Level /LI-6819 Panel C31
- 2. Steam Drum Pressure /PI-6819 Panel C31
- 3. Emergency Condenser Low Level Panel C31 Alarm Indicating Light /LS-3550
- 4. Emergency Condenser Firewster Panel C31 Makeup Flow Indicating Light /FS-4947 TRANSFER SWITCHES / POWER SUPPLIES / CONTROL CIRCUITS SWITCH LOCATION
- 1. Emergency Condenser Outlet Valve ASD MO-7053 Motor Control MO-7053* Starter OR Emergency Condenser Outlet Valve ASD MO-7063 Motor Control M0-7063* Starter
- 2. Main Steam Isolation Valve Control MO-7050 Motor M0-7050 Starter
- 3. Emergency Condenser Firewater Makeup Panel C31 Valve Control SV-4947
- 4. Control Rod Drive Pump No. I and Equipment Lock associated ASD Power Source
- Section 3.7.13(a) applies only if the alt'ernate shutdown controls for both emergency condenser outlet valves, M0-7053 and M0-7063, are inoperable at the same time.
j NOTE: Alternate Shutdown Battery operability requirements are contained in Section 11.3.5.3."
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Big Rock Point Plant 6 TSCR - Alternate Shutdown System
" TABLE 4.3.-9 ALTERNATE SHUTDOWN SYSTEM INSTRUMENT SURVEILLANCE REQUIREMENTS INSTRUMENT SURVEILLANCE FREQUENCY METHOD
- 1. Steam Drum Level, A. Check Weekly compare to known level LI-6819 B. Calibration Every 18 apply known differential months pressures to transmitters
- 2. Steam Drum Pressure, A. Check Weekly compare to known pressure PI-6819 B, Calibration Every 18 apply known pressures to months transmitter
- 3. Emergency Condenser A. Check Monthly initiate flow in line Makeup Line Flow Switch Indicating Light, FS-4947
- 4. Emergency Condenser Low A. Check Monthly simulate low level Level Alarm Indicating Light, LS-3550 B. Calibration Every 18 apply known differential (Panel C31) months pressure to switch" TSB0985-0289-NLO4 L >
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Big Rock Point. Plant 7 TSCR - Alternate Shutdown System G. Bases for Section 3/4.7.12 Revise the last sentence of the first paragraph to read as follows:
"The~ penetration fire barriers include active and passive elements in the facility fire protection program which are subject to periodic inspections."
H. Bases for Section 3/4.7.13 Add the following to the bases:
"3/4.7.13 ALTERNATE SHUTDOWN SYSTEM The requirements for the Alternate Shutdown System provide assurance that safe shutdown and cooldown to approximately 212*F can be achieved in the event of major fire in critical areas of the plant. i This capability is in accordance with the criteria of Appendix R to ,
10 CFR 50."
II. DISCUSSION These changes add technical specification operability and surveillance requirements for components of the alternate shutdown system installed in accordance with Appendix R to 10 CFR 50 as required by Item 8(j) of Generic Letter 81-12. System design was reviewed and approved as discussed in the NRC Safety Evaluations dated March 8, 1983 and March 26, 1985. The added requirements are based on applicable portions ;
of draft standard Technical Specifications. The equipment represents the minimum required to reach safe " hot" shutdown conditions for a fire that destroys the normal systems. Operability requirements on equipment required to reach " cold" shutdown was not included in the proposal for the following reasons:
- 1. The equipment included in this proposal is adequate to provide assurance that safe " hot" shutdown of the reactor can be achieved and maintained indefinitely. This involves the use of the main steam isolation valve to limit any primary system leakage, the emergency condenser to cooldown the system, and a control rod drive pump to provide make,up to the primary system. At Big Rock this condition is very stable. The reactor can be maintained in safe i shutdown status indefinitely under these circumstances. !
- 2. The proposed operability and surveillance requirements are for the most part compatible with existing Technical Specification require-ments for the equipment involved (for example, as explained later, the battery surveillance requirements proposed exceed the recommen-dations of the draft Standard Technical Specification).
- 3. The ability to take the plant from the " hot" shutdown condition described above to the " cold" shutdown condition (temperature
<212*F) is required by Appendix R. Modifications have been per-formed, procedures have been prepared, and complete preoperational acceptance testing of the equipment needed to meet this requirement he.s been done.
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r ~3 Big Rock Point Plant 8 TSCR - Alternate Shutdown System
- 4. This " cold" shutdown equipment, namely, alternate power sources for a shutdown cooling system pump, reactor coolant water pump, fuel pit pump, control rod drive booster pump, and a service water pump, provides very little added margin of safety in performing it's function. This equipment is provided merely to lower the tempera-ture of the primary system from just above the boiling point to below the boiling point.
- 5. The " cold" shutdown equipment listed does not currently have any operability requirements in the Big Rock Point Technical Specifications.
It would be inconsistent to add operability requirements for equip-ment that has very little importance to nuclear safety. In each case, if the equipment were to fail, the ability to maintain safe
" hot" shutdown (approximately 212*F) indefinitely is not affected, thereforr: time would be available to repair any defective component.
- 6. It would be beyond the requirements of Appendix R to assume that the emergency condenser will fail at the time of the design basis fire -
Appendix R does not require consideration of unrelated single failures concurrent with a fire and loss of offsite power.
Based on these reasons, it is considered inconsistent and inappropriate to include operability requirements for listed " cold" shutdown equipment in the Technical Specifications. However, to insure that equipment needed to achieve and maintain " cold" shutdown is available, a surveil-lance requirement (4.7.13.3) was included in this proposal.
The #1 control rod drive pump and its associated ASD power source are considered to have equivalent shutdown capability. This is due to the fact that an alternate method of makeup to the primary system is already available from the fire system by manually operating core spray valves inside containment with a pressure of less than 110 psig. This alternative is included in the operating procedures fer the alts:nate shutdown system and can be relied on during any time C.e pump itself is inoperable. (If the normal power supply were inoperable, but the pump itself was ready for service, the alternate shutdown method would still be considered operable.) This therefore follows the guidance of the draft Standard Technical Specifications. Note that under the conditions i of loss of the ability to open the core spray valves remotely from I
outside containment, with no other source of makeup available to the primary systen the RDS system would be manually inhibited as long as the core spray system is inoperable.
The emergency condenser makeup line flow switch and low level alarm indicating lights are also considered to have equivalent shutdown capability. The loss of these indicating lights in no way affects the ability of the system to provide makeup to the shell of the emergency condenser. They provide information to assess the need for makeup and the actual makeup flow. Without either of these lights operable, the function can still be performed by entering containment and checking the sight glass at the emergency condenser. It is also known that makeup is TSB0985-0289-NLO4
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Big Rock Point Plant 9 TSCR - Alternate Shutdown System required within four hours and that lack of makeup would cause the primary system to eventually repressurize, of which indication is function can still be performed by entering containment and checking the sight glass at the emergency condenser. It is also known that makeup is required within four hours and that lack of makeup would cause the primary system to eventually repressurize, of which indication is available. As these backup measures are available, it is appropriate to consider these items to have squivalent shutdown capability.
The ensrgency condenser consists of two redundant loops. Existing Technical Specification 4.1.2(b) states that, should one emergency condenser tube bundle develop a leak during power operation, it will be permissible to isolate the leaking tube bundle until the next outage.
It also requires immediate shutdown if both loops are inoperable. The proposed alternate shutdown section allows loss of one loop, consistent with 4.1.2(b), and requires shutdown in seven days for loss of alternate shutdown control of both loops. (Loss of normal control of both loops would require immediate shutdown per 4.1.2(b).) This makes the proposal consistent with existing and draft standard technical specifications.
A calibration surveillance is not included for the Emergency Condenser Make-up Line Flow Switch Indicating Light, FS-4947. The intent of this flow switch is to provide a positive indication that SV-4947 had ener-gized and that water flow has been established. It is not intended to have a calibrated flow switch to provide a calibrated flow reading.
The alternate shutdown system battery was not put in Standard Technical Specification format as was Section 3/4.7.13. It replaces the station battery as the power source for the main steam isolation valve and emergency condenser outlet valves, and therefore requires more restric-tive requirements than those of Appendix R. The surveillance require-ments are consistent with the existing station battery requirements and with applicable IEEE Standards for Class 1E battery installations.
The battery is sized to allow several days following loss of the charger before it would nc longer be able to support the equipment operations required for alternate safe shutdown. Therefore the function of the charger is not critical to the Class 1E function of the battery and is not added to the Technical Specifications other than weekly verification of float voltage.
Note that the eight hour design time interval listed is in reality far exceeded during the actual service test. This test is designed to simulate the load profile that would exist under the Appendix R assumptions (minimum of nine days without a charger followed by seventy-two hours of alternate shutdown loads). This twelve (12) day load profile is condensed into an equivalent eight (8) hour load test.
(In other words, a service test is not required by Appendix R, but the eight (8) hour test that is done simulates the more extensive Appendix R loads, exceeding both Class IE and Appendix R requirements.)
Additional fire detection requirements are proposed to the existing requirements in Section 3.3.3.8 of the technical specifications in ordec TSB0985-0289-NLO4 L
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e Big Rock Point Plant 10 TSCR - Alternate Shutdown System
.to cover the new Alternate Shutdown Building. This structure houses safety-related equipment required to operate the main steam isolation valve and emergency condenser outlet valves. This addition makes the new area consistent with technical specification requirements for all other safety-related areas of the plant.
The proposed change to the existing requirements in Specification 3/4.7.12 and bases adds active fire barriers (fire doors and dampers).
This change establishes surveillance and operability requirements which verify the active barriers are capable of performing their safety function.
The surveillance interval for items 3A and 4A of Table 4.3-9 are listed as " monthly" in lieu of " weekly" as items IA and 2A for the following reasons:
- 1. Both test procedures for functionally testing the flow switch and indicating light require manual valve manipulations which remove the emergency condenser level control scheme and fire water make-up source from service. Weekly testing of those devices creates a high unavailability of these components to perform their safety functions during power operation.
- 2. As discussed in the last paragraph on page 8, without either light operable the assessment functions can still be performed as described within.
III. Analysis of No Significant Hazards Considerations This change adds operability and surveillance requirements for equipment I
required to operate to assure a safe method of cooling the primary system, in the event of a fire. This proposed change (and associated modifications as previously appreved in NRC Safety Evaluations dated March 8, 1983 and March 26, 1985) decreases significantly the conse-i quences of a design basis fire.
The alternate shutdown system battery replaces the station battery as the power source for the main steam isolation valve, and emergency condenser outlet valves. The design and operability requirements of this battery system are consistent with those of the station battery currently addressed by the Big Rock Point Technical Specifications, thus not increasing the probability or consequences of an accident previously evaluated.
The proposed changes do not change the existing requirements for operability or surveillance of the shutdown system equipment except to
- place additional restrictions and surveillance requirements on such equipment. The changes do not allow the equipment to be operated in any new or different way from what is currently allowed and therefore do not create the possibility of a new or different kind of accident from any l accident previously evaluated.
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Big Rock Point Plant 11 TSCR - Alternate Shutdown System Existing Technical Specification operability and surveillance require-ments have in no case been reduced by the proposed change. Only addi-tional operability and surveillance requirements are added for safe shutdown equipment, thus no margins of safety will be reduced with issuance of this proposed change. Consequently, this proposed change does not involve a significant hazards consideration.
IV. Conclusion The Big Rock Point Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.
CONSUMERS POWER COMPANY 15y 7/
/u <d F V Buckman, Vice PresTaent Nuclear Operations Sworn and subscribed to before me this 17th day of December, 1986.
M Elaine E Buehrer, Notary Public
.Tackson County, Michigan My commission expires October 31, 1989 l
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