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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 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 ML20059A7571990-08-16016 August 1990 Advises That Response to Bulletin 90-001, Transmitters Mfg by Rosemount, Complete,Per 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 ML20247A3221989-05-12012 May 1989 Grants 880926 Request for Partial Exemption from Annual Fees of 10CFR171,based on Size & Age of Plant.Invoice Encl 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 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 ML20245L3221989-04-28028 April 1989 Ack Receipt of 881223 Submittal of Rev 8 of QA Topical Rept CPC-2A Re Transfer of QA Assigned Functions to Other Plant Organizations & Continuing QA Organizations Program Control. Topical Rept Acceptable & Meets 10CFR50,App B ML20245C8541989-04-20020 April 1989 Advises That Independent post-implementation Verification of Software Question Outstanding for Amend 91 Closed 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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.JUL 31 1389 Docket _No.150-155
. Consumers Power Company p ATTN: ' David P. Hoffman -l
,Vice President i Nuclear Operations 1
~1945 West Parnall Road- l Jackson, MI 49201 1 i
Dear Mr. Hoffman:
)
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SUBJECT:
OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS !
LIn a telephone ~ conversation on July 24, 1989, between Mr. Dennis'G. La Croix, Nuclear Traning Administrator, and Mr. Gregory M.-Nejfelt, Chief Examiner, )
arrangements were made for,the administration of examinations at the Big Rock point.
j The written and oral examinations are scheduled for the week of November 13, i 1$89. i In' order for us to meet this schedule, it will be necessary for the facility . i to furnish the approved reference material listed in Enclosure'1, " Reference
' Material Requirements.for Reactor / Senior Reactor Operator Licensing .
Examinations" at least 60 days prior to the examination date. Any delay in receiving approved properly bound and indexed reference material will result in a delay' in. administering the examinations. Mr. La Croix has been advised 1
-of our reference material requirements, the number of reference material sets j that'are required, and the examiners names and addresses where each set is ;
to be mailed. i The facility ~ management is responsible for providing adequate space and i accommodations in order to properly conduct the written examinations. !
~ Enclosure 2, " Requirements.for Administration of Written Examinations," l describes our requirements for conducting these examinations. j Mr..La'Croix has also been informed of these requirements. {
Enclosure 3 contains the Rules and Guidelines that will be in effect during the administration of the written examination. The frcility management is !
responsible' for ensuring that all applicants are aware of these Rules. ]
1
-The. facility staff' review of the written examination will be conducted in )
accordance with requirements specified in Enclosure 4, " Requirements for !
Facility Review of Written Examinations." Mr. La Croix has been informed )
of these requirements. j l
f, it .
JUL 31 m Consumers Power Company 2 All reactor operator and senior reactor operator license applications should be submitted at least 60 days prior to the first examination dates so that we will be able to review the training and experience of the. applicants, process the medical certifications, and prepare final examiner assignments after applicent eligibility has been determined. If the applications are not received at least 30 days prior to the examination dates, it is likely that a postponement will be necessary.
This request is covered by Offica of Management and Budget Clearance Number 3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing and mailing the required material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Informatiori Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Comrtission, Washington, D.C.
20555; and to the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington,.D.C. 20503.
Thank you for your consideration in this matter. If you have any l questions regarding the examinatico procedures and requirements, please contact G. M. Nejfelt at (312) 790-5528.
Sincerely, C 2' l li ;D BY GE0ffREY C. WU mii l Geoffrey C. Wright, Chief Operations Branch
Enclosures:
- 1. Reference Material Requirements for Reactor /Sanior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines For Written Examinations
- 4. Requirements for Facility Review of Written Examinations See Attached Distribution l
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Consumers Power Company 3 dCl 3 l' ?^'n ec w/ enclosures:
Mr. Kenneth W. Berry, Director
- Nuclear Licensing
. Thomas W. Elward, Plant Manager-DCD/DCB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen, Michigan Public Service Commission Michigan Department of Public Health D.' G.'La Croix, Plant Training Manager cc w/o enclosures:
L. Kelly, Project Manager, NRR K. E. Perkins, Branch Chief, OLB I.. N. Jackiw, Section Chief, DRP 1
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REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS
- 1. Existing learning ob,iectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.)
A copy of the facility Job and Task Analysis (JTA), specifying the knowledges and abilities required of an operator at the facility. Each particular knowledge and/or ability will include an importance rating correlating it to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG-1122 (1123) will be used to establish content validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room complex and, as identified in the facility JTAs, outside of the control room, i.e., local operations.
Training materials should include all substantive written material used for preparing applicants for initial R0 and SR0 licensing. The written material should include learning objectives and the details presented during lectures, rather than outlines. Training materials should be identified by plant and unit, bound, and indexed. FAILURE TO PROVIDE COMPLETE, Pa~?ERLY B0UND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials which include the following should be provided:
- System descriptions including descriptions cf all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels !o the actual procedures used for operating the applicable systea
- Complete and operationally useful descriptions of all safety-system interactions and, whcre available, B0P system interactions uMer emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
- Training material used to clarify and strengthen understanding of emergency operating procedures. J l
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- Comprehensive theory material that includes fundamentals in the area of theory of reactor operation, thermodynamics, heat transfer and fluid f1w. as well as specific application to actual in plant components. For example, mechanical theory material. on pumps should include pump theory as well as descriptions of how these principles actually apply to major plant pumps and the systems in which they are installed (i.e., Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps, Feedwater pumps and Emergency Feedwater pumps).
Reactor Theory material should include descriptions that draw explicit ties between the fundamentals and the actual operating limits followed in the plant (i.e. , reactor theory material should contain explanations how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
- 2. Complete Procedure Index (including surveillance procedures, etc.)
- 3. All administrative procedures (as applicable to reactor operation or safety)
- 4. All integrated plant procedures (normal or general operating procedures)
- 5. Emergency procedures (emergency instructions, abnormal or special procedures)
- 6. Standing orders (important orders that are safety related and may supersede the regular procedures)
- 7. Surveillance procedures (procedures that are run frequently, i.e. , weekly or that can be run on the simulator)
- 8. Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate)
- 9. Annunciator / alarm procedures
- 10. Radiation protection manual (radiation control manual or procedures)
- 11. Emergency plan implementing procedures
- 12. Technical Specifications (and interpretations, if available) for all units for which licenses are sought.
- 13. System operating procedures
- 14. Piping and instrumentation diagrams, e betrical single-line diagrams, or flow diagrams 2
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- 15. Technical Data Book, and/or plant curve information as used by operators and' facility precautions, limitations, and set points (PLS) for.the facility.
Questions and answers specific to the facility training program which may 16.
be used.in the written or operating examinations (voluntary by facility licensee)
- 17. The following on the plant reference simulation facility
- a. List of all praprogramed initial conditions
- b. List of all preset malfunctions with a clear identification number.
The list should include cause and effect information. Specifically, for each malfunction a co vise description of the expected result, or range of results, that 'ill occur upon implementation should be provided. Additionally, an indication of which annunciators are to be initially expected should be given.
- c. A description of simulator failure capabilities for valves, breakers, indicators and alarms
- d. Where the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.e. ,
ability to vary the size of a given LOCA or steam leak, or the -
ability to cause a slow failure of a component such as a feed pump, turbine generator or major valve (e.g. , drifting shut of a main feedwater control valve)
- e. An identification of modeling conditions / problems that may impact the examination
- f. Identification of any known performance test discrepancies not yet corrected
- g. Identification of differences between the simulator and the reference plant's control room
- h. Copies of facility generated scenarios that expose the applicants to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR) and containment challenges (PWR and BWR) may be provided (voluntary by licensee)
- i. Simulator instructors manual (voluntary by licensee)
- j. Description of the scenarios used for the training class (voluntary by licensee) t 1
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- 18. Additional material required by the examiners to develop examinations that meet the requirements of these Standards and the regulations.
The above reference material should be approved, final issues and should be so marked. _If a plant has not finalized some of the material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is available and that' agreement has been reached with the licensee for limiting changes befo.e the administration of the examination. All procedures and reference material should be bound with appropriate indices or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material could result in cancellation or rescheduling of the examinations.
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REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS L 1. A single room shall be pre ided for administration of the written examina-tion. The-location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the written examination. If necessary, the facility should make arrangement for the use of a suitable room at a local school, mote, or other building. Obtaining this room is the responsibility of the licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. Minimum spacing should be one applicant per table, with a three foot space between tables.
- 3. Suitable arrangements shall be made by the facility if the applicants are to have lunch, coffee or other refreshments. These arrangements shall comply with Item 1 above and shall be reviewed by the examiner and/or.
proctor.
- 4. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each applicant's use in completing the examination. The examiner shall distribute these pads to the applicants.
- 5. Applicants may bring pens, pencils, calculators or slide rules into the examination room. Only black ink or dark pencils should be used for writing answers to questions.
- 6. The licensee shall provide one set of steam tables for each applicant.
The examiner shall distribute the steam tables to the applicants. No wall charts, models, and/or other training materials shall be present in the examination room. No other equipment or reference material shall be allowed unless provided by the examiner.
PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. Check identification badges.
- 2. Pass out examinations and all handouts. Remind applicants not to review examination until instructed to do so.
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.
READ THE FOLLOWING INSTRUCTIONS:
- 1. Restroom trips are to be limited and only one applicant at a tira may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 2. Use black ink or dark pencil on'.i to facilitate legible reproductions.
- 3. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 4. Fill in the date on the cover sheet of the examination (if necessary).
- 5. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 6. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. 00 NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 7. Print your 11ame in the upper right hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
- 8. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination questinn page.
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- 9. If you are using separate sheets, number each answer as to category and number (i.e., 1.04,6.10) and skip at least 3 lines between answers to allow space for grading.
- 10. Write "End of Category " at the end of your answers to a category.
- 11. Start each category on a new page.
- 12. Write "Last Page" on the last answer sheet.
- 13. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
- 14. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
- 15. Show all cal.;ulations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted ar.d your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
- 18. If the intent of a question is unclear, ask questions of the examiner only.
- 19. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80% or greater and at lease 70% in each category.
- 21. There is a time limit of (6) hours for completion of the examination.
(Or some other time if less than the full examination is taken).
PARAGRAPH 7: LICENSE EXAMINATIONS ENCLOSURE 3 (Cont'd)
- 22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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i REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS
- 1. At the option of the Section Chief, the facility may review the written examination up to two weeks prior to its administration. This review may take place at the facility or in the Regional office. The Chief Examiner will coordinate the details of the review with the facility. An NRC examiner will always be present during the review.
Whenever this option of examination review is utilized, the facility reviewers will sign the following statement prior to being allowed access to the examination. The examination or written notes will NOT be retained by the facility.
- a. Pre-Examination Security Agreement I agree that I will not knowingly divulge any information concerning the replacement (or initial) examination scheduled for to any unauthorized persons.
I understand that I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheduled to b administered the above replacement (or initial) examination from now until after the examination has been administered. I understand that violation of this security agreement could result in the examination being voided.
Signature /Date In addition, the facility staff reviewers will sign the following statement after the written examination has been administered.
- b. Post-F.xamination Security Agreement I did not, to the best of knowledge, divulge any information concerning the written examination administered on to any unauthorized persons. I did not participate in providing any instruction to l those reactor operator and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination.
l- Signature /Date
- 2. Regardless of whether the above examination review option is exercised, immediately following the administration of the written examination, the facility staff shall be provided a marked-up copy of the examination and the answer key. The copy of the written examination shall include pen and ink changes made to questions during the examination administration.
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- If2the facility did not review the examination prior to its administration, they will have five (5) working days from the day of the written examination to submit formal comments. If the facility reviewed the
. examination prior to its administration, 'any additional comments must be given to an examiner prior to his/her leaving the site at the 'end of the week of the written examination administration. In either case, the comments will be addressed to the responsible Regional Office byLthe' highest onsite level of corporate management for plant operations, e.g.,
-Vice President for Nuclear Operations. A copy of the submittal will be forwarded to the Chief Examiner, as appropriate. Comments not submitted within the required time frame will be considered for inclusion in the grading process on a case-by-case basis by the Regional Office Section Chief. Should the comment submittal deadline not.be met, a long delay in. grading the examinations may occur.
L- 3. The following format should be adhered to for submittal of specific comments:
- a. Listing'of NRC Question, answer and reference
- b. Facility comment / recommendation
- c. Reference (to support facility comment)
NOTES: 1. -No change to the examination will be.made without submittal of a reference to support the facility comment. Any supporting l- documentation that was not previously supplied, should be provided.
- 2. Comments made without a concise facility recommendation will not be addressed.
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