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Category:CORRESPONDENCE-LETTERS
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217N8261999-10-25025 October 1999 Discusses Errata Re 991021 Filing of Northeast Nuclear Energy Co Answer to Request for Hearing & Petition to Intervene B17901, Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6)1999-10-18018 October 1999 Submits Statement of Personal Qualification (NRC Form 398) Along with Supporting Certification of Medical Exam by Facility Licensee (NRC from 396) in Support of License Renewal for PM Miner.Encls Withheld,Per 10CFR2.790(a)(6) B17886, Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 21999-10-18018 October 1999 Requests Permission to Utilize Code Case N-623, Deferral of Insps of Shell-to-Flange & Head-to-Flange of Reactor Vessel,Section Xi,Div 1, for Millstone Unit 2 05000336/LER-1999-012, Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-012-00,re Unrecoverable CEA Misalignment Entry Into TS 3.0.3 on 990917.Commitments Made by Util Are Encl B17900, Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 11999-10-14014 October 1999 Forwards Revised Assumptions Used in Fuel Handling Accident Analysis & Summary of Results.List of Regulatory Commitments Are Listed in Attachment 1 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217F0031999-10-0606 October 1999 Forwards Original Petition to Intervene Being Filed on Behalf of Clients,Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone,Iaw Provisions of 10CFR2.714 ML20217P1201999-10-0606 October 1999 Informs NRC of Proposed Acquisition of Parent Holding Company of Central Maine & Requests NRC Concurrence,Based on Threshold Review,That Proposed Acquisition Does Not,In Fact, Constitute Transfer Subject to 10CFR50.80 B17892, Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC1999-10-0505 October 1999 Requests Withdrawal of License Amend Application Re 24-month SG Tube Insp Surveillance Extensions,Submitted in Util 950726 & s to NRC ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl B17887, Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer1999-09-28028 September 1999 Requests Exemption from Requirements of 10CFR140.11(a)(4) Which Requires Licensees to Maintain Secondary Financial Protection Beyond Primary Layer ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 B17883, Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-62301999-09-27027 September 1999 Forwards Mnps Unit 3 ISI Summary Rept,Cycle 6, IAW ASME Section XI,IWA-6230 B17890, Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-09-27027 September 1999 Provides Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal B17888, Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 9909151999-09-24024 September 1999 Informs That There No Longer Exists Need to Maintain Millstone Unit 2 SRO License for CA Hines,License SOP-10741-01,effective 990915 B17884, Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-031999-09-24024 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, for Mnps,Units 2 & 3,per Administrative Ltr 99-03 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 05000336/LER-1999-001, Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-001-00 Re Thermal Reactor Power Limit That Was Exceeded.Commitments Made by Util Encl B17867, Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports1999-09-17017 September 1999 Requests Relief from Requirements of 10CFR50.55a(g),IAW ASME Section XI for Millstone,Unit 3.Util Requests Relief from Performing Visual Exam of Reactor Pressure Supports to Extent Required by Code for Class 1 Supports B17865, Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal1999-09-16016 September 1999 Provides NRC Staff with Updated Proposed Rev of FSAR Section 14.6.3, Radiological Consequences of SG Tube Failure. Updated Proposed Rev Will Replace Info Provided in Attachment 3 of Initial Submittal B17876, Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant1999-09-16016 September 1999 Informs That Util Will Adopt Last Approved Northeast Util QA Program (Nuqap) Tr,Rev 21,dtd 990630,as Unit 1 Nuqap,Per Decision to Permanently Cease Operations at Subject Plant B17882, Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Forms 398 & 369 in Support of License Renewal for Bb Parrish,License SOP-10399-2.Encl Withheld Per 10CFR2.790(a)(6) B17881, Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Le Olsen,License SOP-10398-2.Encl Withheld Per 10CFR2.790(a)(6) B17859, Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 9801281999-09-15015 September 1999 Forwards up-to-date Distribution Lists for NRC Correspondence to NNECO & NUSCO.Side-bars Indicate Changes from Previous Lists Provided to NRC on 980128 B17880, Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6)1999-09-15015 September 1999 Forwards NRC Form 398 & NRC Form 396 for Rf Martin,License SOP-10397-0.Encls Withheld Per 10CFR2.790(a)(6) B17872, Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 11999-09-14014 September 1999 Informs of Election to Consolidate Previous Commitments Re Work Observation Program with Two New Programmatic Commitments Listed in Attachment 1 ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl B17838, Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls1999-09-10010 September 1999 Forwards Revs 34 & 35 to Physical Security Plan.Explanation of Changes Provided as Attachment 1.Without Encls ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 05000336/LER-1999-010, Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 11999-09-0202 September 1999 Forwards LER 99-010-00,documenting 990804 Event of Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve Following Maint Activities.List of Util Commitments Contained in Attachment 1 ML20216H0591999-09-0202 September 1999 Responds to Re Issues Submitted by Cullen on Behalf of Several Petitioners Concerning Offsite Emergency Prepardeness for Millstone Nuclear Power Station ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F4991990-11-16016 November 1990 Forwards List of Unimplemented GSIs at Facilities,Per Generic Ltr 90-04.Timely Completion Requested ML20062G2441990-11-16016 November 1990 Forwards Combined Insp Repts 50-245/90-23,50-336/90-25 & 50-423/90-23 on 901001-05.No Violations Noted ML20217A6661990-11-15015 November 1990 Requests Addl Info Concerning Boraflex Degradation in Millstone 2 Spent Fuel Pool Storage Racks to Support Review of Util 901001 Submittal.Info Re Gamma Doses to Boraflex Matl During Blackness Testing & Storage Patterns Requested ML20058J1111990-11-14014 November 1990 Forwards Safety Insp Rept 50-423/90-19 on 900905-1015 & Notice of Violation ML20217A2021990-11-0909 November 1990 Forwards Insp Repts 50-213/90-83,50-245/90-82 & 50-336/90-82 & 50-423/90-83 on 900924-28.No Violations Noted ML20217A0821990-11-0505 November 1990 Forwards Safety Insp Rept 50-336/90-18 on 900822-1001 & Notices of Violation & Deviation ML20058F7061990-11-0101 November 1990 Forwards Amend 47 to License DPR-21 & Safety Evaluation. Amend Deletes Requirement That Combined Time Interval for Any Three Consecutive Surveillance Intervals Not to Exceed 3.25 from Tech Spec 1.0.X ML20062D5441990-10-30030 October 1990 Confirms 901018 Telcon Re Possible Unanalyzed Condition Re Repairs for Steam Generator Tube Plugs in Mar 1989 ML20058C3761990-10-30030 October 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $25,000 for Violations Re Main Steam Line High Flow Setpoints & Gas Turbine Generator Surveillance Testing ML20058G3421990-10-29029 October 1990 Forwards Exam Rept 50-245/90-10OL Administered During Wk of 900827 ML20058E5871990-10-26026 October 1990 Discusses Programmed Enhancements for Generic Ltr 88-17, Loss of Dhr ML20058E6201990-10-26026 October 1990 Forwards Safety Insp Repts 50-245/90-19,50-336/90-21 & 50-423/90-17 on 900904-07.No Violations Noted ML20058E0931990-10-25025 October 1990 Advises That Schedule for Installation of Alternate Ac Acceptable,Per 900925 Response to Station Blackout Rule ML20058G6121990-10-25025 October 1990 Advises That 900926 Response to Station Blackout Evaluation Acceptable,Based on Installation of Alternate Ac Prior to Startup ML20062C7041990-10-24024 October 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900418 Request from Section IV.F.3 of App E to 10CFR50,Section IV.F.3 ML20058D5601990-10-24024 October 1990 Forwards Team Insps 50-213/90-82,50-245/90-81,50-336/90-81 & 50-423/90-82 on 901001-12 ML20058G0151990-10-23023 October 1990 Forwards Exemption to 10CFR50,App E,Section IV.F.3 Re Conduct of Full Participation Emergency Exercise,Per 900418 & 0801 Ltrs ML20058B3181990-10-17017 October 1990 Ack Receipt of Forwarding Payment of Civil Penalty in Amount of $50,000.Penalty Not Mitigated IR 05000336/19900271990-10-17017 October 1990 Forwards Operator Exam Rept 50-336/90-27OL on 901003.Exam Results:Operator Passed Retake Exam ML20058A9791990-10-17017 October 1990 Forwards Insp Rept 50-336/90-19 on 900910-14.No Violations Noted ML20058E0661990-10-16016 October 1990 Forwards SE Granting 900926 Request for Relief from ASME Code Inservice Insp Requirements to Repair Svc Water Sys ML20062B8751990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062B8831990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20059N4061990-10-0303 October 1990 Forwards Safety Evaluation Accepting pressure-temp Limits Re Generic Ltr 88-11.Current pressure-temp Limits for Heatup, Cooldown,Leak Test & Criticality of RCS Acceptable ML20059N9681990-10-0303 October 1990 Forwards Partially Withheld Safeguards Insp Repts 50-245/90-16,50-336/90-17 & 50-423/90-16 on 900827-31 & Notice of Violation ML20059N3291990-10-0202 October 1990 Forwards Response to Comments Contained in Util Re Installation of Hardened Wetwell Vent IR 05000336/19900091990-10-0101 October 1990 Ack Receipt of 900727 & 0907 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-336/90-09. Actions Will Be Examined During Future Insps ML20059M1471990-09-27027 September 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $50,000 Proposed by NRC .Corrective Actions Will Be Examined During Future Insps ML20059M0471990-09-14014 September 1990 Advises That NRC Does Not See Need for Formal Relief from ASME Code Section XI to Repair Leak in Svc Water Piping ML20059J8621990-09-12012 September 1990 Grants 900911 Request for Temporary Waiver of Compliance from Tech Spec Table 3.2.2 Re Containment Spray Interlock ML20059J7621990-09-12012 September 1990 Forwards Amend 45 to License DPR-21 & Safety Evaluation. Amend Changes Tech Spec Section 3/4.5.C by Adding Operability & Surveillance Requirements for Mods Made to Tie Breakers 14A to 14G ML20059F3301990-08-29029 August 1990 Forwards Safety Evaluation Accepting Util 890417,0530 & 900330 Responses Concerning Method of Dealing W/Station Blackout Provided Util Make Mods,Procedure Changes & Calculations Discussed.Technical Evaluation Rept Also Encl ML20059C8261990-08-28028 August 1990 Forwards Safety Insp Repts 50-245/90-11,50-336/90-12 & 50-423/90-09 on 900611-15 & 25-29.No Violations Noted ML20059D7281990-08-27027 August 1990 Requests Listed Ref Matls Needed for Senior Reactor Operator Licensing Exams Scheduled for Wk of 901112.Completed License Applications Required 30 Days Before Exam Date ML20059E2201990-08-24024 August 1990 Forwards Radiological Controls Insp Repts 50-245/90-14, 50-336/90-15 & 50-423/90-13 on 900723-27.One Noncited Violation Identified ML20059D7341990-08-23023 August 1990 Forwards Safety Insp Rept 50-423/90-10 on 900612-0723 & Notice of Violation.Util Should Respond to Violation Re Inaccurate Statement in LER 90-013 Concerning Rev of Procedure by Following Instructions in Encl App a ML20059J8481990-08-16016 August 1990 Forwards Training Effectiveness Team Insp Rept 50-423/90-06 on 900604-08.Training Programs Well Implemented & Personnel Effectively Trained.Few Weaknesses Identified ML20058M7711990-08-0909 August 1990 Requests Addl Info Re License Amend Application Under Generic Ltr 87-09 for Facility.Affirms That Remedial Measures Prescribed for Affected Action Statements Consistent W/Updated SAR & Supporting Safety Analysis ML20056A9451990-08-0707 August 1990 Forwards Insp Rept 50-423/90-80 on 900416-25.Weaknesses Identified ML20058N0581990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Encouraged to Start Similar Initiative to Provide for Sharing of Info & Experiences Involving Engineering & Solutions of Problems Common to All ML20058M5361990-08-0606 August 1990 Forwards Review of Westinghouse Rept WCAP-12277, Westinghouse Owners Group Bounding Evaluation for Pressurizer Surge Line Thermal Stratification, Per NRC Bulletin 88-011 ML20056A6901990-08-0101 August 1990 Forwards Insp Rept 50-336/90-11 on 900530-0711.No Violations Noted ML20058L3331990-07-25025 July 1990 Forwards Safety Insp Repts 50-245/90-13,50-336/90-13 & 50-423/90-11 on 900609-13.No Violations or Deviations Noted ML20055J2121990-07-25025 July 1990 Advises That Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Concludes Adequate Bases Not Provided That Facility Meets All Appropriate Code Limits for 40-yr Plant Life ML20056A3551990-07-24024 July 1990 Forwards Requalification Exam 50-336/90-10OL-RQ on 900618-22 IR 05000245/19900081990-07-23023 July 1990 Discusses Insp Rept 50-245/90-08 on 900510-25 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty. Violation Occurred on 900507 When Stated Cask Arriving at Barnwell,Sc Found to Contain Contaminated Water ML20055H3621990-07-23023 July 1990 Grants Temporary Waiver of Compliance Re Facility Tech Spec 3.6.6.1, Supplemental Leak Collection & Release Sys 1990-09-27
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 ML20217G9491999-10-14014 October 1999 Forwards Exemption from Requirements of 1-CFR50,App E, Section IV.F.2.c,re Conduct of full-participation Exercise in Sept 1999,at Plant,Units 1,2 & 3 ML20217D9671999-10-12012 October 1999 Forwards Copy of Transcript of Public Meeting Held by NRC Staff & NNECO on 990825 at Waterford,Connecticut on Decommissioning Program for Millstone,Unit 1.Without Encl ML20217D3011999-10-0707 October 1999 Forwards Request for Addl Info Re Util 990118 Request for Amend to License NPF-49 to Allow full-core Offloads to Spent Fuel Pool During Core Offloads to Spent Fuel Pool During Core Offload Events ML20217B4711999-10-0404 October 1999 Informs That Staff Did Not Identify Any Safety Concerns Re Licensee Proposals to Modify Commitments Made for Action Items 4.2.1,4.2.2,4.5.1 & 4.5.2 of GL 83-28 by Providing Addl Justifications or Safety Bases for Changes ML20212J3051999-10-0101 October 1999 Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212J2451999-10-0101 October 1999 Informs That Util 980807 & 990629 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Considers Subj GL to Be Closed for Units 2 &3 ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl ML20217A9271999-09-30030 September 1999 Discusses Investigation Conducted at Millstone Nuclear Power Station by NRC OI Region I on 980319 to Determine If Contract Training Instructor Was Terminated for Raising Concerns About Quality of Training Matls ML20217B3221999-09-30030 September 1999 Refers to Investigation Rept 1-1997-035 Conducted at Millstone Nuclear Power Station by NRC Ofc of Investigation Field Ofc,Region I on 970915 to Determine Whether Former Health Physics Technician Discriminated Against ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy ML20212A9011999-09-10010 September 1999 Forwards Environ Assessment & Finding of No Significant Impact Re Application for Exemption,Dtd 990803.Proposed Exemption Would Provide Relief from Requirement of 10CFR50 ML20212A7501999-09-10010 September 1999 Forwards Staff Requirements Memo Response,Dtd 990525,which Provides Actions NRC Plans for Continued Oversight of safety-conscious Work Environ & Employee Concerns Program ML20212A3171999-09-10010 September 1999 Discusses Investigation Rept 1-1998-045 Conducted on 981112 to Determine If Former Senior Health Physics Technician Being Denied Employment at Millstone in Retaliation for Having Raised Safety Concerns in Past.Synopsis Encl ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review ML20211H9971999-08-27027 August 1999 Forwards Insp Rept 50-423/99-07 on 990614-0715.Violations of NRC Requirements Occurred Re Adequacy of C/As for Organizational Changes & Being Treated as NCVs DD-99-09, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 9908261999-08-26026 August 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 990826 ML20211F5841999-08-23023 August 1999 Discusses Proposed Rev 21 to Northeast Utils Quality Assurance Program TR for NRC Review & Approval,Iaw 10CFR50.54 ML20211D5701999-08-20020 August 1999 Informs That in May 1999,Northeast Nuclear Energy Co, Restarted Millstone Nuclear Power Station,Unit 2.Licensee Has Been Tasked Charter with Listed Specific Responsibilities ML20211C4621999-08-18018 August 1999 Discusses Rev to TS Bases Sections 3/4.5.2 & 3/4.5.3, Emergency Core Cooling Sys Subsystems ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210N4921999-08-0909 August 1999 Ack Receipt of 990331 Electronic Transfer of $88,000 for Civil Penalty,Proposed on 990309.Corrective Actions Will Be Examined During Future Insp ML20210C0751999-07-21021 July 1999 Forwards 990721 Notice of Public Meeting Re post-shutdown Decommissioning Activities Rept ML20210A9681999-07-14014 July 1999 Responds to Re Changes to Millstone Physical Security Plan Identified as Rev 32,submitted Per Provisions of 10CFR50.54(p).No NRC Approval Is Required,Based on Util Determination That Revs Do Not Decrease Plan Effectiveness ML20209E7341999-07-12012 July 1999 Discusses Util Responses to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. Responses Acceptable.Info Revised in Reactor Vessel Integrity Database (Rvid) & Is Releasing as Rvid Version 2 ML20209G2921999-07-0909 July 1999 Forwards Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy DD-96-23, Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 9508211999-07-0101 July 1999 Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 950821 ML20196J2111999-06-30030 June 1999 Forwards SE Concluding Licensee USI A-46 Implementation Program Meets Purpose & Intent of Criteria in Generic Implementation Procedure for Seismic Verification of NPP Equipment, Rev 2 ML20196J5031999-06-30030 June 1999 Responds to 990414 Petition,Submitted Per 10CFR2.206 to Nrc. NRC Solicited Support from FEMA to Ensure That Appropriate Response to Enhancements Identified to Offsite EP in Event of Radiological Emergency at Millstone,Developed ML20196J1131999-06-29029 June 1999 Forwards Notice of Receipt & Availability for Comment of Post-Shutdown Decommissioning Activities Rept, Re .Notice Provided for Public Comments to Be Submitted within 30 Days of Notice Date ML20196G9531999-06-24024 June 1999 Discusses Changes Provided by NNECO on 990504 to TS Bases Sections 3/4.7.7 & 3/4.7.8.Returns TS Bases to NNECO to Be Inserted in TS to Ensure That NRC Staff & NNECO Have Identical TS Bases Pages ML20212H9661999-06-21021 June 1999 Confirms 990611 & 14 Telcons with M Selden,In Which Beckman & Assocs,Inc Was Advised to Stop Work Under Mod 4 to Task Order 005,under Contract NRC-03-98-021 ML20212H6661999-06-15015 June 1999 Forwards RAI Re 990315 Application Request for Approval of Proposed Indirect Transfer of Seabrook Station,Unit 1 License & Proposed Indirect Transfer of Millstone,Unit 3 License to Extent Held by Nepco ML20212J0751999-06-15015 June 1999 Forwards Notice of Withdrawal of Amend Request for Allowed Outage Time Extensions for Emergency Diesel Generators & Low Pressure Safety Injection Trains of Emergency Core Cooling Sys ML20195J3121999-06-15015 June 1999 Expresses Concern Re M Casey 990523 Column, Gaffes Turn Into Cash at NRC, & Disagrees with New London Day Earlier Editorial Criticism of NRC Investigations of Harassment & Intimidation of Employees at Millstone NPPs ML20195K0601999-06-15015 June 1999 Forwards Request for Addl Info Re fire-related IPEEE Analysis,Per GL 88-20 ML20195J4761999-06-10010 June 1999 Forwards Insp Rept 50-336/98-219 on 981214-18,990126-29 0208-19 & 0301-05.Four Violations Identified & Being Treated as Noncited Violations ML20195J0321999-06-10010 June 1999 Expresses Appreciation for Serving as Moderator for 990209 Public Meeting at Waterword,Ct.Questions Raised by Interested Members of Public & NRC Responses Encl.Staff Reply to Blanch Also Encl ML20196J5091999-06-0404 June 1999 Requests Assistance to Review Petition Submitted Under 10CFR2.206 of NRC Rules.Petition Concerns EP Issues for Millstone Nuclear Power Station ML20207G1121999-06-0303 June 1999 Forwards Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05 on 990302-0419.No Violations Noted.Closure of 15 Significant Items List (SIL) Issues at Unit 2 Signifies Completion of Insp for Entire Unit 2 SIL ML20207G6271999-06-0303 June 1999 Forwards Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Replace Specific Titles in Section 6.0 of TSs for All Three Millstone Units with Generic Titles 1999-09-30
[Table view] |
Text
.. . .A AUG 2 71990 Docket No. 50-423 Northeast Nuclear Energy Company ATTN: Mr. E. J. Mroczka Senior Vice President - Nuclear Engineering and Operations ~ Group P. O. Box 270 Hartford, Connecticut 06141-0270 Gentlemen:
SUBJECT:
REACTOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS In a' telephone conversation between Mr. P. Bonnett and Mr. R. Stotts,
. arrangements were made for the administration of licensing examinations at Northeast Nuclear Energy Company,-Unit No. 3.
The examinations are scheduled for the week of November 12, 1990.
To meet the above schedule, it will be necessary for you to furnish the reference material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by September 10, 1990. Any delay in receiving approved, properly bound and indexed reference' material, or the submittal of inadequate or incomplete reference material may result in -the examination being rescheduled. Mr. Stotts has been advised of our reference material requirements, and the address where each set is to be mailed.
You are responsible for providing adequate space and accomodations for administration of the written examination as listed'in Enclosure 2,
" Requirements For the Administration- of Written Examinations." The facility management is responsible for ensuring that all applicants are aware of the examination rules as stated in Enclosure 3, "NRC Rules and Guidelines for Written Examinations."
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."
To better document simulator examinations, the Chief Examiner will have the simulator operator record predetermined plant conditions ~ (i.e. ,
plant pressure, temperature, pressurizer level, etc.), for each simulator scenario. The applicants will be responsible for providing this information, with any appeal of a simulator operating examination.
Therefore, your training staff should retain the original simulator examination scenario information until all applicants who took-examinations have either passed tt ' operating examination, accepted the denial of their license, or filed an appeal.
nn -- 0FFICIAL RECORD COPY l _.)
9009070159 900827 /
\ l', y" i
PDR ADOCK 05000423 V PDC )
Northeast Nuclear Energy Co. 3 cc w/ encl:
R. Stotts, Training Manager W. D. Romberg, Vice President, Nuclear Operations L D. O. Nordquist, Director of Quality Services
-R. M. Kacich, Manager, Generation _ Facilities Licensing S. E. Scace, Station Superintendent E. A. DeBarba, Station Director, Haddam Neck Public Document Room (PDR) i Local Public Document Room'(LPDR) l Nuclear Safety Information Center (NSIC) s NRC Senior Resident Inspector j State of Connecticut bec w/ encl: '
Region I Docket Room (with_ concurrences)
Management Assistant, DRMA (w/o encl) '
R. Bellamy,_DRSS DRP Section Chief l P. Bonnett, DRS P. Eselgroth W. Raymond, SRI, Millstone 1, 2& 3 J. Caldwell, EDO D. Jaffe, LPM, NRR OL Facility File '
DRS Files (2)
Official Record Copy RI:DRS R !
Curley E h gil/
08/ /90 08/g /90
4 I
i f
2 1 Northeast-Nuclear Energy Company
~
All completed license applications should be submitted at least 30 days before the first examination. dates so that we will be able to review i
' the training and experience of the candidates, process the medical !
certifications, and prepare final examiner assignments after applicant !
- eligibility has been determined. If the applications are not received ;
at least 30 days before the examination-dates, it is likely that a 1 postponement will be necessary. ;
Mr. Stotts has been informed of the above requirements. !
This request is covered by Office 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 j mailing the required' material. Send comments regarding this burden t 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 Information Support Services, i Office of Information Resources Management, U.S. Nnclear Regulatory 1 Commission, Washington, D.C. 20555; and to the Paperwork Reduction i Proj ect ' ( 3150-0101) , Office of-Management and Budget, Washington, D.C.
20503. 1 Thank you for your considerat3r<. in--this matter. If you have any j questions regarding the examination procedures and' requirements, please !
contact me at (215) 337-5211.
Sincerely, LPeter W. Eselgroth, Chief PWR Section i
. Operations Branch Division of Reactor Safety !
Enclosures:
- 1. Reference Material Requirements -for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinatior.s
- 3. NRC Rules and Guidelines for Written Examinations
- 4. Requirements'for Facility Review of Written Examinations 0FFICIAL RECORD COPY
a
-, ES-201 1 Rev 5 01/01/89 Enclosure 1 x
REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR i
~
OPERATOR LICENSING EXAMINATIONS I
i 1.
Existing learning objectives, Job Performance Measures and lesson plans !
-(including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.)
A copy of the f acility Job and Task Analysis (JTA), specifying the knowledges and abilities required of an operator at the facility.. Eacn ;
particular knowledge and/or ability will include: an import &nce rating correlating it to ensuring the health and the safety of the public. If a JTA is nct furnished, the Knowledges and Abilities Catalog. for Nuclear Powei Plant validity Operators, for the NUREG 1122(1123) will be used to esi.sMish content examination, j
All Job Performance Measures (JPMs) used to asc9ttain the competence of-the operators in performing tasks within the control room complex and, as
-i identified in the facility JTAs, outside of the control room, i.e., local operations.- l Training materials shall include all substantive written material used for preparing applicants for initial RO and SRO licensing. The written material shall include learning objectives .and the details presented during lectures, rather than outlines. Training materials shall be identified by plant and unit, bound, and indexed. FAILURE TO PROVIDE COMPLETE, PROPERLY BOUND AND INDEXED PLANT REFERENCE MATERIAL MAY RESU IN THE RETURN OF THE MATERIAL TO THE PERSON 9HO IS THE ti!GHE CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VI PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATER COVER LETTER EXPLAINING THE DEFICIENCIES'IN THE REFERENC FACT THAT THIS WAS THE REASON THE EXAMINATIONS ~WERE CANCELL POSTPONED.
provided: Training materials which include the.following shall-be System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual.
procedures used for operating the applicable system.
Complete and operationally useful descriptions of all safety-system interactions and, where auilable, BOP systen interaction: under emergency and abnormal conditions, including consequences of e tic-ipated operator error, maintenance error, and equipment failure.
Trainirq material used to clarify and strengthen understanding of emergency operating procedures.
Comprehensive theory material that includes fundamentals in the area j
of theory of reactor operation, thermodynamics, heat transfer and i M
. ES-201-Rev 5 01/01/89 Enclosure l'(Continued) fluid flow,.as well as specific application to actual 'n plant com-ponents.
For examole, mechanical theory aterial on pumps shall include pump theory as well as descriptions of how these principles actually apply to major plant pumps and the systems in which they are L
installed (i.e., Reactor Coolant Pumps, all ECCS pumps, Recirculation -
pumps, Feedwater pumps and Emergency Feedwater pumps). Reactor-Theory material shall. include descriptions that draw explicit ties between the fundamentals and the actual operating limits fcellowed in the plant (i.e., reactor theory material shall 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 :.urveillance procedures, etc.)
3.
All administrative procedures (as applicable to reactor operation or safety) 4.
All integrated plant procedures;(normal or general operating procedures)'
5.
All emergency procedures) ' procedures (emergency instructions, abnormal or special s 6.
Standing orders (important orders that are safety related and may super-sede the regular procedures) 7.
Surveillance procedures (procedures that are run frequently, i.e. weekly or that can be run on the simulator) 6.
- Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate)
- 9. All annunciator / alarm procedures 10.
l Radiation protection manual (radiation control manual or procedures)
- 11. Emergency plan implementing procedures l 12.
Technical Specifications (and'ir'.erpretations, i' available) for all units for which licenses are sought.
'13. System operating procedures 14 Piping &nd instrumentation diagrams, electrical single-line diagrams, or flow diagrams 25.
Tecnnical Data Book, and/or plant curve information as used by operators and facility facility precautions, limitations, and set points (PLS) for the 1
,J-,. - - - . , . n l
-- - - - -- - . _ _ . . - . . . ~-
I ES-201 I l
Rev 5 01/01/89 i ik losure 1 (Continued) 16.
Questiens and answers specific to the facility training program which ma) be used in the written or operating examinations (voluntary by fatilitylicensee)
- 17. I The following on the plant reference simulation facility
- a. List of all preprogrammed initial coiditions l
b.
l List of all preset malfunctions with a clear identification number.
The list shall include cause and effect information. Specifically, for each malfunction a concise description of the expected result, or range provided. of results, that will occur upon implementation shall be.
Additionally, an indication of which annunciators are to be initially _xpected shall be given.
! c.
t A description of simulator failure capabilities for valves, breakers, indicators and alarms
- d. i l Where the capability exists, an explai .cion of the ability to vary l the severity of a particular malfunction shall be provided,1 e.,
l 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., drif_ ting shut of a main ,
i 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 plant #
of differences between the simulator and the referen s control room
- h. i 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) 1.
Simulator instructors manual (voluntary by licensee) j.
Description by licensee) of the scenarios used for the trair.ing class (voluntary
.e.
scottionai material reou1reo by the examiners to develop examinations that ;
meet the requirements of these Stancaros and the regulations,
. - ~ . .
E$-201 Rev 5 01/01/89 Enclosure 1 (Continued)
The above reference material shall be approved, final issues and shall 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 before the administration of the examination. All procedures and reference material shall 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 exar.inations.
\
O
I
. ES-201 :
Rev 5 01/01/89 i
2 Enclosura 2 RE0VIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS 1
- 1. I A single room shall be provided n act: ,1stration of the written examina-tion.. The location of this room , ? .pporting restroom facilities shall !
be such as to prevent contact with 3 . other facility and/or contractor personnel during the written exanthesion. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the licensee. i 1
- 2. i Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. i with a 3 foot space betweenMinimum tables, spacing shculd be one appitcant per table, !
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, e
i
A j *
, E5-201 Rev 5 01/01/89 Y
Enclosure 3 PROCEDURF' FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. Check identificatien 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 followinq 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 leave. trips are to be limited and only one applicant at a time may 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 only 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 separate sheetyour answers on the examination question page or on a of paper.
THE BACK $1DE OF THE PAGE.USE ONLY THE PAPER PROVIDED AND 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. DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
7.
Print your name 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 pa on the examination question page. ges inserted when writing your answers
E;-;;l 4
4 Rev 5 01/01/89
/
Ecclesure 3 (Continued)'
9.
- f 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 cuestion.
NOT an indication of the depth of answer required.The amount of blan 15.
Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00choice NOT ouestions, LEAVE ANY ANSWER BLANK.' Partial credit will NOT be given on
, multiple
- 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, 0.20 and you give five responses, each of your responses will be worth points.
If one of your five responses is incorrect. 0.20 will be deducted and 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
- f 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 least 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.)
20.
When you are done anc have turned in your examination, leave the examinati:n a t i:E:INE ThE AREA). If y:u are f0und in this area wnile the examination is sti.i in progress, your license may ce cenied or revoted.
23.
Ensure is on yourthat all information answer sheet. you wish to have evaluated as part of your answer immediately following the examination. Scrap paper will be disposed of without review
, ES-231 4 Rev 5 01/01/89 Enclosure 4 REQUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS 1.
At the option of the Chief Examiner, 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 to will sign the following statement prior to being allowed access the examination.
by the facility. The examination or written notes will not by retained
- a. Pre-Examination Security Agreement I
information concerning the replacement (or initial) examinationagree tha scheduled for to any unauthorized persocO I understand that I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheduled to be administered the above replacement (or initial) examination administered. from now until after the examination has been could result in the examination being voided,I understand that violation s
Tignature/Date In addition, the facility staff reviewers will sign the following statement after the written examination has been administered,
- b. Post-Examination Security Agreement I_
divulge any information concerning the written examinationdid not, to the be administered on to any unauthorized persons.
did not participate in providing any instruction to those reactor I operator and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination, Signature /Date
,1
, E5-201
. Rev 5 01/01/89 En:losure 4 (Continued)'
2.
Regardless of whether the above examination review option is exercised, immediately following the administration of the written examination, the facility the staffkey.
answer shall be provided a marked up copy of the examination and ink changes made to questions during the examination adminis If the facility did not review the examination prior to its administration, they will have five written examination to submit formal (comments.5) If theworking facility. days from the day of the 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 by the highest on site level of corporate mana Vice President for Nuclear Operations. gement for plant operations, e.g.,
forwarded to the Chief Examiner, as appropriate.A copy of the submittal will be 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.
grading the examinations may occur.Should the comment submittal deadlin 3.
j The following ramments: format should be adhered to for submittal of specific a.
Listing of NRC Question, answer and reference
- b. Facility comment / recommendation c.
Reference (to support facility comment) i NOTES: 1.
No change to the examination will be made without submittal of a reference to support the facility comment.
documenta'.
provided. ion that was not previously supplied, should beAny supporting 2.
Comments be addressed.made without a concise facility recommendation will not 4
A twoExaminer.
Chief hour post examination review may be held at the discretion of the If this review is held, the facility staff should be informed that only written comments that are properly supported will be considered in the cradino of the eramination.
I a . -