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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217G4111999-10-12012 October 1999 Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed ML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use ML20217C5111999-09-30030 September 1999 Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method ML20217C2761999-09-30030 September 1999 Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted ML20211G1011999-08-25025 August 1999 Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year ML20210V0561999-08-17017 August 1999 Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1) ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML20210S6961999-08-12012 August 1999 Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp ML20210S6291999-08-11011 August 1999 Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal ML20210L0321999-08-0303 August 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6) ML20210H2701999-07-28028 July 1999 Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728 ML20209D6951999-07-0707 July 1999 Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One ML20210L0491999-06-30030 June 1999 Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl ML20209D7011999-06-21021 June 1999 Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20195D0371999-06-0303 June 1999 Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested ML20207F6631999-06-0303 June 1999 Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c) ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created ML20206P4501999-05-11011 May 1999 Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock ML20206P0921999-05-0707 May 1999 Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule ML20206H1011999-05-0404 May 1999 Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20206E7821999-04-29029 April 1999 Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program ML20206E3721999-04-29029 April 1999 Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required ML20206B7381999-04-26026 April 1999 Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined 05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999 Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable ML20196K7881999-03-29029 March 1999 Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept ML20205E3471999-03-29029 March 1999 Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to ML20204F4611999-03-19019 March 1999 Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML20203F8041999-02-11011 February 1999 Forwards Temporary Addendum to Security Plan Re Central Alarm Station,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21(c) ML20203C8971999-02-0808 February 1999 Informs That NRR Contracted with PNNL to Evaluate Storage of Spent Fuel at Number of Decomissioning Nuclear Power Facilities.Forwards Request for Info Re Spent Fuel Storage at Big Rock NPP ML20202H4891999-01-26026 January 1999 Informs That Exemption Request from Various 10CFR73 Physical Protection Requirements, ,was Improperly Based on Requirements of 10CFR50.12.Request Was Resubmitted by Ltr ML20199H2431999-01-15015 January 1999 Forwards Insp Rept 50-155/98-09 on 981201-990112 & Nov.One Weakness Identified Re Event Involving Ungrappling Fuel Bundle Without Being Fully Seated in Rack & Without Independent Verification That Ungrappling Bundle Was Proper ML20199E1841999-01-13013 January 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication ML20199E0781999-01-13013 January 1999 Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5 ML20199D9711999-01-13013 January 1999 Forwards Plant Defueled TS Administrative Replacement Pp.On 990104 Staff Informed NRC That Pp Numbering for Table of Contents Was Incorrect.Subj Pp Requested to Be Replaced with Encl ML20199E9051999-01-12012 January 1999 Submits Revised Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls ML20199E7671999-01-12012 January 1999 Informs That Licensee Has Elected to Comply with Listed 10CFR50.68(b) Requirements in Lieu of Maintaining Monitoring Sys Capable of Detecting Criticality as Described in 10CFR70.24 ML20199A4151999-01-0404 January 1999 Informs That Individuals Listed on Attachment 1 Will No Longer Maintain Operating License for Plant.Senior Licensed Operators & Licensed Operators No Longer Required at Facility ML20198K6551998-12-24024 December 1998 Forwards Amend 120 to License DPR-6 & Safety Evaluation. Amend Changes License DPR-6 & App A,Ts to Reflect Permanently Shutdown & Defueled Status of Plant ML20198J4001998-12-21021 December 1998 Requests That Words Decommissioning of in First Sentence of Paragraph a of Fol,License DPR-6 Be Removed from CPC 970919 Request ML20196H3171998-12-0303 December 1998 Forwards Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted.Inspection Covered Activities in Areas of Radiological Safety ML20196G7541998-11-25025 November 1998 Requests Withdrawal of Listed Sections of 970919 Amend Request,As Supplemented by Ltrs ,0721 & 1014, Respectively.Util Proposed to Retain Certain Sections of Current Tech Specs (CTS) to Support Withdrawal Request ML20195G9851998-11-17017 November 1998 Forwards Rev 0 to Vol 9 of Defueled Emergency Plan & Rev 0 to Vol 9A of Defueled Epips ML20195H5321998-11-13013 November 1998 Provides Confirmation That Revs Required by NRC to Defueled Emergency Plan Prior to Implementation Have Been Completed by Licensee.Items Incorporated Into Plan,Listed ML20195F2271998-11-12012 November 1998 Forwards Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls.Request Withheld,Per 10CFR73.21 ML20154M5381998-10-14014 October 1998 Forwards Supplement to Plant Defueled TS & Bases, Incorporating Licensee Response to NRC 980416 RAI & Clarifying Listed Items ML20154M2211998-10-14014 October 1998 Forwards Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted.Insp Consisted of Examination of Activities in Areas of Facility Mgt & Control,Decommissioning Support (Including Physical Security),Sf Safety & Radiological Safety 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058G8921990-11-0707 November 1990 Forwards Insp Repts 50-155/90-20 & 50-255/90-20 on 900925-28 & 1015-19.Violations Noted ML20058G2461990-11-0202 November 1990 Forwards Safety Insp Rept 50-155/90-17 on 900904-1015 & Notice of Violation ML20058F7331990-10-31031 October 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058A7671990-10-22022 October 1990 Advises That Review of 900816 Response to NRC Bulletin 90-001 Re Loss of Fill Oil in Rosemount Transmitter Ongoing ML20059N0081990-09-28028 September 1990 Forwards Insp Rept 50-155/90-10 on 900723-27 & 0806-10 & Notice of Violation ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059L4771990-09-18018 September 1990 Forwards Safety Insp Rept 50-155/90-13 on 900724-0903. Noncited Violation Noted ML20059J3091990-09-10010 September 1990 Forwards Exemption from 10CFR55.45(b)(2)(ii) Re Use of Simulation Facility,Per 900404 Request.Util Request to Delay Submittal of Description of Performance Tests & Results Until 910526 Granted ML20059F2531990-08-31031 August 1990 Forwards Safety Evaluation Supporting Util 891229 Request to Dispose of Dredged Discharge Canal Sediment from Facility ML20059C6111990-08-27027 August 1990 Forwards Safety Insp Rept 50-155/90-15 on 900814-16.No Violations Noted ML20059B7771990-08-22022 August 1990 Advises That Util Commitment to Install Two New Recorders That Provide Containment Temp Indication on Front Panel During 1990 Refueling Outage,Acceptable ML20056B5191990-08-17017 August 1990 Forwards Final SALP Rept 50-155/90-01 & Revised Pages to SALP Rept.Overall Performance Did Not Decline,Per 900716 Meeting.Nrc Overstated Concern W/Radiological Controls Functional Area in Initial Rept & Cover Ltr ML20059A7571990-08-16016 August 1990 Advises That Response to Bulletin 90-001, Transmitters Mfg by Rosemount, Complete,Per ML20059A1741990-08-16016 August 1990 Informs That NRC NDE Mobile Lab Will Conduct Independent NDE Exams at Plant on 900924-1005.Selected Sys for Exam Listed on Encl ML20059A1661990-08-16016 August 1990 Forwards Safety Insp Rept 50-155/90-14 on 900730-0803.No Violations Noted ML20059A3721990-08-14014 August 1990 Ack Receipt of Informing NRC of Change in Completion Date Re on-the-job Training Procedure,Per LER 90-002 ML20058N2211990-08-0707 August 1990 Forwards Safety Insp Rept 50-155/90-12 on 900612-0723.No Violations Noted ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls ML20055G7301990-07-20020 July 1990 Requests Util Provide Ref Matls Listed in Encl for Requalification Program Evaluation on 901018 & Wk of 901105 ML20055G2881990-07-16016 July 1990 Advises of fitness-for-duty Insp Scheduled for Wk of 900925- 28 at Plant.Written Policies & Procedures Will Be Reviewed as Part of Insp Process ML20055G5051990-07-11011 July 1990 Advises That 900511 Rev 95 to Chapters 2,5,6,7,8 & Apps D, M & P for Plant Emergency Plan Consistent w/10CFR50.54(q) & Acceptable.Position of on-call Technical Adviser Should Be Inserted in Table 1 of Chapter 5 ML20055F1661990-07-0606 July 1990 Forwards Initial SALP Rept 50-155/90-01 for Jan 1989 - Apr 1990,prior to 900716 Scheduled Meeting.Two Areas of Improvement & No Areas of Decline Identified Since Last SALP Rept ML20055D7011990-07-0202 July 1990 Confirms Plans Re 900716 Meeting W/Util in Charlevoix,Mi to Present Initial SALP 9 Rept for Plant ML20055D1791990-06-28028 June 1990 Forwards Safety Insp Rept 50-155/90-11 on 900501-0611.No Violations Noted ML20059M9181990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248A5351989-09-19019 September 1989 Forwards Safety Insp Rept 50-155/89-15 on 890725-0905.No Violations Noted.Unresolved Items Noted Re Compliance W/ Requirements of 10CFR50,App J for Reduced Pressure Testing ML20247D3541989-09-0606 September 1989 Forwards Environ Assessment & Finding of No Significant Impact Re Tech Spec Change to Delete Section 6.4.2(d) on Calibr of Portable Neutron or Gamma dose-rate Measuring Instruments ML20246D2191989-08-16016 August 1989 Forwards Amend 100 to License DPR-6 & Safety Evaluation. Amend Revises Tech Specs by Providing for New Organizational Unit Entitled Nuclear Safety Svcs Dept to Discharge Offsite Safety Review Functions Instead of Nuclear Safety Board ML20245K0581989-08-14014 August 1989 Forwards Safety Insp Rept 50-155/89-14 on 890710-0801 & Notice of Violation ML20245G1981989-08-10010 August 1989 Forwards Environ Assessment & Finding of No Significant Impact Re 880922 Application & 890117 & 0412 Ltr Suppls, Requesting Changes to Tech Specs to Allow Independent Review & Audit Functions Be Accomplished by Independent Unit ML20245G5131989-08-10010 August 1989 Forwards SER Accepting Util Response to Generic Ltr 83-28, Item 4.5.3 Re Reactor Trip Reliability on-line Functional Testing of Reactor Trip Sys ML20245E6301989-08-0202 August 1989 Forwards Safety Insp Rept 50-155/89-13 on 890618-0724 & Notice of Violation ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed ML20247R0971989-07-31031 July 1989 Advises That Operator & Senior Operator Written & Oral Exams Scheduled for Wk of 891113.Ref Matls Listed on Encl & Operator License Applications Should Be Provided at Least 60 Days Prior to Exam Date ML20245H8231989-07-28028 July 1989 Forwards Amend 98 to License DPR-06 & Safety Evaluation. Amend Requires Compliance W/Amended Physical Security Plan ML20246K8721989-07-12012 July 1989 Forwards Insp Rept 50-155/89-12 on 890612-14,20-22,26-28 & 0705-06.No Violations Noted ML20246F9181989-07-0505 July 1989 Forwards TE Murley to Ecology Ctr of Southern California Ack Receipt of Petition & Advising Ctr That Petition Will Be Treated Per 10CFR2.206 ML20246C1201989-06-30030 June 1989 Forwards Safety Insp Rept 50-155/89-09 on 890507-0617.No Violations Noted ML20245B1831989-06-0909 June 1989 Forwards Safety Insp Rept 50-155/89-10 on 890522-25.No Violations Noted NUREG-0828, Concurs W/Interpretation of Intent of Item 4(5) of SER Re NUREG-0828,Sections 4.5, Wind & Tornado Loadings & 4.8, Tornado Missiles. Alternate Shutdown Bldg Will Be Manned When Tornado Warning Broadcast for General Area1989-06-0808 June 1989 Concurs W/Interpretation of Intent of Item 4(5) of SER Re NUREG-0828,Sections 4.5, Wind & Tornado Loadings & 4.8, Tornado Missiles. Alternate Shutdown Bldg Will Be Manned When Tornado Warning Broadcast for General Area ML20248C0501989-05-31031 May 1989 Forwards Amend 97 to License DPR-6 & Safety Evaluation.Amend Adds Operability & Surveillance Requirements for Alternate Shutdown Sys to Tech Spec Sections 11 & 12 & Includes Tech Specs for Active Fire Barriers & Fire Detection ML20247K8741989-05-24024 May 1989 Forwards App to SALP 8 Rept 50-155/89-01 for Sept 1987 - Dec 1988,per 890328 Meeting ML20247A6281989-05-16016 May 1989 Forwards Safety Insp Rept 50-155/89-06 on 890326-0506.No Violations Noted ML20247A2921989-05-12012 May 1989 Advises That 890406 Rev 92 to Vol 9 of Site Emergency Plan Including Changes to Chapter 7, Emergency Facilities & Equipment & App J, Primary & Secondary Communications, Acceptable ML20247A3221989-05-12012 May 1989 Grants 880926 Request for Partial Exemption from Annual Fees of 10CFR171,based on Size & Age of Plant.Invoice Encl ML20246L8121989-05-0202 May 1989 Forwards Amend 96 to License DPR-6 & Safety Evaluation.Amend Revises OL to Allow Increase in Amount of Byproduct Matl Plant May Possess from 10.5 to 45 Ci Cs-137,as Sealed Sources 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212L9051999-10-0404 October 1999 Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use ML20212K7561999-09-30030 September 1999 Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted 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) 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 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) 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 ML20196E1601999-06-21021 June 1999 Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily ML20207D1151999-05-27027 May 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created 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 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 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 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 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 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 ML20199E0781999-01-13013 January 1999 Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5 ML20199E1841999-01-13013 January 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication 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 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 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 ML20154E0121998-09-30030 September 1998 Forwards Exemption from 10CFR50.54(q) Re Plant & Suppls ,1120& 980302,0429 & 0828 Which Requested Exemption from Certain Protions of 10CFR50.47(b) & App E to 10CFR50 to Allow Brpnp to Discontinue Offsite EP Activities ML20239A2491998-09-0303 September 1998 Forwards Insp Rept 50-155/98-06 on 980716-0826.No Violations Noted.Overall,Reactor Decommissioning Activities Were Generally Performed Satisfactorily & as Planned.Potential Weaknesses Were Identified in Review of SE Procedure ML20237E2731998-08-25025 August 1998 Discusses NRC Insp Rept 50-155/98-03 on 980527.Violations Noted.Insp Findings Documented in NRC Insp Rept Sent to Util by Ltr ML20237C5461998-08-19019 August 1998 Refers to Revs 133,134 & 135 to Portions of Big Rock Point Plant Emergency Plan.Based on Determinations That Changes in Revs 133-135 Do Not Decrease Effectiveness of Emergency Plan,Nrc Approval Not Required ML20236Y0441998-08-0505 August 1998 Forwards Summary of Decommissioning Insp Plan Through March 1999.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events & Resource Availability ML20236V0651998-07-28028 July 1998 Ack Receipt of 980605 Request for Withdrawal of 980325 Request for License Amend for DPR-6,paragraph 2.C.(5), Physical Protection & Closes TAC MA0756 ML20236U4311998-07-24024 July 1998 Forwards Insp Rept 50-155/98-05 on 980528-0715.No Violations Noted.Nrc Concern That Programmatic Assessments of RPP Were Not Initiated Following Identification of Multiple Deficiencies in RP Program During First Half of 1998 IR 05000155/19980041998-07-0808 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-155/98-04 ML20236M4131998-07-0707 July 1998 Ack Receipt of Ltr Dtd 980512,transmitting Changes Identified as Rev 14 to Big Rock Point Security Suitability, Training & Qualification Plan.No NRC Approval Required ML20249C4391998-06-25025 June 1998 Ack Receipt of ,Which Transmitted Changes to Rev 14 to Suitability,Training & Qualification Plan,Submitted Under Provisions 10CFR50.54(p) ML20249B3041998-06-16016 June 1998 Forwards Insp Rept 50-155/98-03 on 980407-0527.Violation Noted & Being Considered for Escalated Enforcement Action. Notice of Violation Not Presently Being Issued for Insp Finding ML20248F3541998-05-28028 May 1998 Responds to to P Harris Which Requested That NRC Retain Resident Inspector at Big Rock Site to Monitor Project for Period of Five Years.Informs That NRC Intends to Assign Inspector to Site for One Year ML20247M9481998-05-15015 May 1998 Ack Receipt of Ltr Dtd 980312,which Transmitted Changes Identified as Rev 7 to Safeguards Contingency Plan,Submitted Under Provisions of 10CFR50.54(p) ML20217D1221998-04-21021 April 1998 Forwards Insp Rept 50-155/98-02 on 980203-0406.No Violations Noted.Emergency Preparedness Exercise Was Completed Satisfactorily,However,Unusual Event Was Declared When Algae Containing Co-60 Alarmed Discharge Canal Radiation Monitor ML20217A5991998-04-16016 April 1998 Forwards Request for Addl Info Re Proposed Changes to Proposed Defueled TS as Detailed in .Questions Were Discussed W/Licensee Staff on 980121-22 & 980311.RAI Summarizes Questions That Remain ML20216J4411998-04-16016 April 1998 Informs That Consumer Request for Exemption from Certain Requirements of 10CFR50.54, Condition of Licenses, Based On,In Part,Determination That Plant Permanantly Shut Down & Defueled Not Required ML20216J9861998-04-16016 April 1998 Forwards SE Approving Licensee 970919 Submittal of Training Program for Certified Fuel Handlers.Comments Also Encl ML20247L4021998-04-14014 April 1998 Discusses Rev 131 to Chapter 5 & Rev 132 to Chapters 2,3 & Appendix H of Big Rock Point Plant Emergency Plan Submitted Under Provisions of 10CFR50.54(q).No NRC Approval Required ML20216G9071998-04-0808 April 1998 Responds to Asking Number of Questions Re Activities at Big Rock Point Nuclear Plant.Particularly on 980203 NRC Requested Addl Info from Utility Re Proposed Changes to Emergency Preparedness Plan ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided IR 05000155/19970151998-03-20020 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-155/97-15 ML20246H0091998-03-19019 March 1998 Discusses Rev 130 to App a of Big Rock Point Nuclear Plants Emergency Plan,Received in Sept 1997.NRC Approval Not Required Based on Determination That Changes Do Not Decrease Effectiveness of Emergency Plan ML20203K7501998-02-26026 February 1998 Forwards Summary of Decommissioning Insp Plan for Remainder of Fy 1998.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events, Resource Availability ML20203H8511998-02-23023 February 1998 Forwards Request for Addl Info Re Exemption from Offsite Emergency Planning Requirements.In Accordance with 10CFR50.30(b),response Must Be Executed in Signed Original Under Oath or Affirmation ML20202J8111998-02-14014 February 1998 Forwards Insp Rept 50-155/97-15 on 971205-980202 & Notice of Violation.Activities in Areas of Facility Mgt & Control, Decommissioning Support & Spent Fuel Safety ML20203E0811998-02-13013 February 1998 Informs That on 980331 & 0401,NRR Will Be Holding 1998 Decommissioning Power Reactor Counterparts Meeting in Arlington,Tx.Recipient Requested to Make Presentation at Subj Meeting.Meeting Agenda Encl ML20202D7751998-02-0808 February 1998 Ack Receipt of Ltr Dtd 980116,which Transmitted Changes Identified as Rev 32 to Big Rock Point Security Plan, Submitted Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan 1999-09-30
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, ,4,.- jog UNITED STATES y w p, NUCLEAR REGULATORY COMMISSION r,,
-y WASHINGTON, D. C. 20555
- April 18, 1986 Docket No. 50-155 Mr. Kenneth W. Berry Director, Nuclear I.icensing Consumers Power Company 1945 W. Parnall Road Jackson, Michigan 4920'
Dear Mr. Berry:
SUBJECT:
IMPLEMENTATION OF GENERIC REQUIREMENTS Re: Big Rock Point Plant The Comptroller Ceneral in a Report to the Congress dated September 19, 1984, stated "NRC ne'eds better management controls to ensure implementation of aeneric issue solutions." To correct this situation, the Nuclear
%culatory Commission is workirg on a long-term program which will improve its documentation on the status of power reactor licensees' implementation of aonraved reaulatory improvements.
To assist me in developina this information for Big Rock Point Plant, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the date that all aspects of each identified requirenent were conoleted/imolemented or are expected to be completed. For each requirement that has been completed, enter "comoleted" under the Status column and the date the item was completed. For requirements that have not been completed / implemented provide the oro.iected date and enter " pro.iected" under the Status column. I do not expect or want a major effort made to obtain orecise dates. Rather, I will accept readily-known or best-estimate dates for actions that have been completely implemented. For example, the year only would be acceptable for comnletions prior to 1984; the month as
~
well as year is neeced for requirements completed after that t1me. For pro.iected completions / implementations in 1986, use month and year. Use year only for projections thereafter. Please provide a response in the '
form of a marked un listing by May 31, 1986. To the extent that you cannot mark up the list for all items by this date, please give priority to those items resulting from TMI and submit remaining items at a later date.
In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation. ,
gRO4250352 860418 p ADGCK 05000155 PDR L
1 In order to assess the maanitude.of this effort I would appreciata vour estimate of the burden (in man hours) to your staff to accomplish the above task. P' ease work closely with your project manaaer.
Sincerely, OFTCT y U STGM7D BT John A. Zwolinski, Director RWR Project Directorate #1 Division of RWR Licensing
Enclosure:
As stated (
cc w/ enclosure:
See next pace DISTRIBiliIDN Docket NRC PDP Local PDR for each docket DDel Reading PMc CJanerson JZwolinski PRernero OELD EJordan RGrimes JPartlow '
I ACRS (10)
Service list for each RWD#1 plant db '
DRL:PD#1 JZwolinski:ja
/\/gs/86 IDENTICAL COPIES SENT TO THE ATTACHED LIST.
[
IDEiiTICAL ALS0 SEilT TU:COPIES OF IMPLEMENTATI0tl 0F GENERIC REQUIREMENTS LETTER set 1T TO B Mr. William D. Harrinaton Senior Vice President, Nuclear Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 Mr. Dennis L. Farrar Director of Nuclear Licensing Comonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 Mr. Kenneth W. Berry Directnr, Nuclear Licensing tonsumers Power Company 1945 W. Parnall Road
, Jackson, Michigan 49201 Mr. James W. Taylor General Manaaer Dairvland Power Cooperative
, 2615 East Avenue South La Crosse, Wisconsin 54601 Niagara Mohawk Power Corporation Attn: Mr. C. V. Mangan Senior Vice President c/o Miss Catherine R. Seibert 300 Erie Boulevard West Syracuse, New York 1320?
Mr. D. M. Musolf Nuclear Support Services Department Northern States Power Company 414 Nicollet Mall - 8th Floor Minneanolis, Minnesota 55401 Mr. P. B. Fiedler Vice President & Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jerse.y 09731
1 i
Mr. Kenneth W. Rerry Consumers Pcwer Company Bia Rock Point Plant cc:
Mr. Thomas A. McNish, Secratary Consumers Power Company 217 West Michigan Avenue Jackson, Michioan 49?01 Judd I_. Bacon, Escuire Consumers Power Company 212 West Michiaan Avenue Jackson, Michigan 49701 Bio Pock Point Plant '
ATTM: Mr. David P. Hoffman i Plant Superintendent l Route 3 Post Of fice Rox 591 Charlevoix, Michioan 497?0 l Mr. I. Lee Moerland Chairman, Bnard of Comnissioners P. G. Box ?l8 Charlavoix, Michiaan 49720 Office of the Governcr Room 1 - Caoitol Building Lansino, Michigan 48913 Peaional Administrator Nuclear Reaulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Nuclear Facilities and Environmental Monitoring Section Office Division of Radioloaical Health P. O. Rox 30035 Lansina, Michioan 48900 Resident Insoector Bio Rock Point Plant c/o l!.S. NRC RR #3, Box 600 Charlevoix, Michigan 49720
R-1208731-001 REGULAt 0RY INF0RMATION TRACKING SYSTEM PAGE NO. 27 FACILITY IMPLEMENTATION 03/31/86 FACILITY: BIG ROCK POINT 1 PLANT LOCATION: 4 MI NE OF CHARLEVOIX, MICH LICENSED P0HER: 0240 MHT PROJECT MANAGER: T. ROTELLA DOCKET NUMBER s 050-00155 DESIGN POWER: 0072 MHC BRANCH CHIEF: J. ZHOLINSKI ARCH / ENGINEER: BECH . NSSS VENDOR: GE LIC. ASSISTANT: C. JAMERSON IE INSPECTOR: S. GUTHRIE .
LIC ACT LICENSEE TAC N0m MPA 8 TITLE COMPLETE STATUS DATE N08312 A-01 10 CFR 50.55 A(G) - ISI 06/10/83C M08096 A-02 APPENDIX I - ALARA 08/26/85C M06497 A-03 SECURITY REVIENS-MODIFIED AMENLMENT PLANS 04/10/79C M08679 A-04 APPENDIX J - CONTAINMENT LEAK TESTING - 11/23/82C M11371 A-09 PRESSURE VESSEL BELTLINE MATERIAL SUC'.'EILLANCE 07/23/80C M10499 A-10 CONTINGENCY PLANNING 10/01/80C N07767 A-11 GUARD TRAINING PLANS 02/25/81C
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M10502 A-12 VITAL AREA ANALYSIS - 04/30/82C M11269 A-14 .10CFR 50.55 A(G) - INSERVICE TESTING 12/10/82C A-15 07/25/80C M12549 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT M47105 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 11/16/81C M51072 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN 03/13/86r.
M55536 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 05/30/86 M59071 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 09/30/86 M06903 B-02 FIRE PROTECTION 04/04/79C M11613 B-02 FIRE PROTECTION 07/26/79C
""M08207 B-05 STRESS CORROSION CRACKING - ENR RCSPB 10/17/79C M46651 B-05 STRESS CORROSION CRACKING - BWR RCSPB 06/26/84C M12630 B-16 EMERGENCY PLANNING AND REVISIONS 01/01/81C M08442 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 04/02/82C Y
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R-1208731-001 R E o U '. A T 0 R Y INF0RMATION TRACKING SYSTEM PAGE NO.
- ' ?,
a FACILITY IMPLEMENTATION 03/31/86 BIG ROCK POINT 1 (CONTINUATION)
LIC ACT LICENSEE TAC NO. MP A _ 9 TITLE COMPLETE STATUS DATE M10280 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 02/25/81C M10342 B-21 LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANNUNCI A 02/28/82C M08441 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 01/11/84C M10008 B-23 DEGRADED GRID VOLTAGE 03/08/82C M42607 B-24 VENTING AND PURGING CONTAINNENTS HNILE AT FULL P0H 06/28/83C M10198 B-24 VENTING AND PURGING CONTAINMENTS HHIL E AT FULL P0H 08/25/80C M10873 B-27 REVIEH RESPONSES TO IE 89LLETIN 78-03 (DFFGAS EXPL 02/13/81C M11096 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 02/06/81C M43704 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 03/08/83C M48578 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 03/08/83C
"" B-42 TMI FOLLOH UP - ALL PLANTS M11756 05/02/80C M12423 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C 9'
M30640 B-44 LESSONS L EARNED IMPLEMENTATION 05/02/80C M30641 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C M30642 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C M30643 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C
- M30644 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C M30645 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C H3G646 5-44 LES%nNS LEARNED IMPLEMENTATION 05/02/80C '
"~M30647 B-44 LESSONS LEARNED IMPLEHENTATION 05/02/80C M30648 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C M50649 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C M30650 B-44 LESSONS LEARNED IMPLEMENTATION 05/02/80C 7
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TRACKING SYSTEM PAGE NO. 29 R-1208731-001 REGULAT0RY INF0RHATION 03/31/86
.O FACILITY IMPLEMENTATION BIG ROCK POINT 1 (CONTINUATICH) l e
LIC ACT LICENSEE i
TITLE EQMPL ETE 1T AT U2 RAlf TAC NO. MPA 8 05/02/80C M30651 B-44 LESSONS LEARNED IMPLEMENTATION HASH 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 08/12/80C e. .
M12911 B-45
- 05/15/80C M42071 B-46 ANALYSIS OF TURBINE DISC CRACKS 07/20/80C M12694 B-47 ECCSs CLAD SHELLING AND RUPTURE
- 11/30/81C M12781 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 06/08/81C M43082 B-51 EVALUATION OF BULLE11N 79-06 AND 79-08
- 11/08/82C M42214 B-53 SDV CAPABILITY 08/31/83C I
M47368 B-58 SDV CAP %BILITY
~~ 08/27/84C M42907 B-59 MASONRY HALL DESIGN 11/15/85C M42515 B-60 ENVIRONMENTAL QUALIFICATION =,
' 07/28/82C M42653 B-61 LOSS OF NON CLASS IE I8C POWER 03/12/82C M42723 B-62 ESF RESET CONTROL DESIGN DEFICIENCY a.
11/24/81C 4
M43905 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 07/08/82C
$ M43715 B-65 SAFETY CONCERNS ASSOCIATED WITh PIPE BREAKS IN BNR .
HUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 10/10/84C M51668 B-7 2 11/05/85C M52738 B-76 ITEM 1.1 - POST TRIP REVIENs PROGRAM DESCRIPTION 8 q> -
09/30/86 M52819 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENCOR INTER 11/19/85C M52900 B-7 8 ITEMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU '
11/19/85C M52981 B-7 9 ITEM 3.1.3 - POST MAINTENANCE TESTING - CNANGES TO
"~ 07/05/84C M54517 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- ~
07/02/85C M55589 B-84 INSPECTIONS OF BWR STAIHLESS STEEL PIPING ACCORDIN 07/31/86 M53570 B-85 SALEM ATHS 1.2 DATA CAPABILITY 12/31/86 M53553 B-86 SALEM ATHS 2.2 S-R COMPONENTS w
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l R-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO. 30 FACILITY IMPLEMENTATION 03/31/86
. BIG ROCK POINT 1 (CONTINUATION) en
' LIC ACT LICENSEE TAC NO. MPA 4 TITLE LOMPLLTE STATUS RAIE M53736 B-37 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS 11/19/85C M53810 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/19/85C M54043 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 11/19/85C M53963 B-93 SALEM ATHS 4.5.2 8 4.5.3 TEST ALTERNATIVES 10/31/86
! M08284 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 01/12/82C M46646 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 05/09/84C M52209 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF MPA 06/28/85C -
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M10063 D-11 FISSION GAS RELEASE 10/01/80C , , ,
M07960 D-12 NON-JET PUMP BWR CORE SPRAY PERFORMANCE 10/01/79C M11141 D-12 N0g-JETPUMPBHRCORESPRAYPERFORMANCE 0?d2446 u M12284 D-15 HIGH ENERGY LINE BREAK & CON $EBBE#'Ess aTSTEM FAIL 02/18/81C M43044 _D_1,I D UIu WEUn T OPERABLE 10/02/85C M55839 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 08/19/85C M12230 E-01 SPENT FUEL POOL EXPANSIONS 08/14/81C M11823 E-01 SPENT FUEL PCOL EXPANSIONS 05/15/81C M44003 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 03/31/82C
, M46071 F-02 1.A.1.3 SHIFT MANNING 06/30/83C -
, M44142 F-G3 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 11/08/82C M44213 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/07/84C
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M44283 F-05 I.C.1.2/3.'8 PROCEDURES GENERATION PACKAGES (HUREG 06/30/87 M47193 F-06 1.C.5 FEEDBACK OF OPERATING EXPERIENCE 02/04/82C M47368 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 02/04/82C M51142 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 11/07/84C
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I R-1208731-001 REGULAT0RY IKF0RMAT ION TRACK ING SYSTEM PAGE NO. 31 FACILITY IMPLEMENTATION 03/31/86 FIG ROCK POINT 1 (CONTINUATION) m.
t LIC ACT LICENSEE
- TAC HJ. MPA 8 TITLE COMPLLIC STATUS RAIX M51222 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEit 11/30/86 M52485 F-10 II.B.1 RCS HIGH POINT VENTS 07/17/85C M44354 F-10 II.B.1 RCS HIGH POINT VENTS 09/28/83C l
M47020 F-11 II.B.2 PLANT SHIELDING 09/20/84C
' M34422 F-12 II.B.3 POST ACCIDENT SAMPLING 08/17/84C M04492 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 11/08/82C i M44563 F-14 II.D 1 RV AND SV TRAINING 01/13/85C M44760 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 08/24/81C Mo4831 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 10/18/82C M44902 F-20 II.F.1.1 NOBLE GAS MONITOR 10/20/81C M44073 F-21 II.F.1.2 IODINE /PARTICUL ATE SAMPLING 10/20/81C i
M45004 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 10/18/82C 1
M07581 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 04/16/84C ~
M'e 76 52 F-24 II.F.1.5 CONTAINMENT MATER LEVEL INSTRUMENT 04/16/84C M51974 F-24. II.F.1.5 CONTAINMENT MATER LEVEL INSTRUMENT 10/29/85C ,
M47723 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 10'05/84C M45115 F-26, II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 02/12/86C
M45324 F-38 II.K.3.3 REPORTING SV AND RV FAILURES ANO CHALLE 03/05/82C M45531 F-43 II.K.3.13 HPCI AND RCIC INITIA1 ION LEVELS 04/02/82C -
"M46529 F-44 II.K.3.tw ISOLATION CONDENSER ISOLATION MODIFICAT 12/15/81C l
M45583 F-46 II.K.3.16 CHALLENGES AND FAILURES OF RELIEF VALVE 03/04/83C -
M45610 F-47 II.K.3.17 ECCS OUTAGES 08/05/83C M45679 F-48 II.K.3.18 ADS ACTUATION 10/20/82C
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REGU* AT0RY INF0RHATION TRACKING SYSTEM PAGE NO.: 32 R-1208731-001 ~.
FACILITY IMPLEMENTATION , ,, 03/31/86
- b. g t,
BIG ROCK POINT 1 (CONTINUATION) -,
a LIC ACT LICENSEE TITLE COMPLLIX STATUS pal [
TAC NQi MPA 9' m M45703 F-49 II.K.3.19 INTERLOCK RECIRCULA110N PUMP MDDIFICATI 08/12/81C M45727 F-50 II.F.5.21 RESTART OF CSS AND LPCI 06/27/83C em M45751 F-53 II.K.3.25 POWER ON PUMP SEALS 10/27/82C M45175 F-54 II.K.3.27 COMMON REFERENCE LEVEL 10/15/31C w
M46578 F-56 II.K.3.29 PERFORMANCE OF ISOLATION CONDENSERS 09/15/81C M45806 F-57 II.K.3.30 SB LOCA METHODS 12/27/83C M48147 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 12/27/83C M45875 F-59 II.K.3.44 ANTICIPATED TRANSIENTS HITH SINGLE FAIL 03/15/84C
- 10/20/82C M45899 F-60 II.K.3.45 MANUAL DEPRESSURIZATION M45926 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 03/10/86C M45997 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 03/10/86C M46069 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 03/10/86C
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M".6141 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C M46212 F-67 III.A.2.1 EMERGl.NCY PLAN UPGRADE TO MEET RULE 05/16/83C M46285 F-68 III.A.2.2 NETE0kOLOGICAL DATA UPGRADE 03/10/86C M46356 F-69 III.D 3.5 IMPLAAT RADIATION MONITORING 02/03/82C M46427 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 12/30/83C M56103 F-71 I.D.1.7 DETAILED CONTROL ROOM REVIEH (FDLLOWUP TO 11/30/86 e
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