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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 ML20058A9791990-10-17017 October 1990 Forwards Insp Rept 50-336/90-19 on 900910-14.No Violations Noted 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 ML20058E0661990-10-16016 October 1990 Forwards SE Granting 900926 Request for Relief from ASME Code Inservice Insp Requirements to Repair Svc Water Sys 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 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 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 ML20055J2711990-07-20020 July 1990 Forwards Safety Insp Rept 50-245/90-09 on 900515-0625 & Notice of Violation ML20055H7621990-07-19019 July 1990 Forwards Safety Evaluation Re Util 871030 Inservice Testing (IST) Program & Requests for Relief.Ist Program & Other Info Submitted by 871030 & s,Together W/Granting of Relief W/Conditions Acceptable for 10-yr Insp Interval IR 05000245/19900051990-07-16016 July 1990 Discusses Insp Rept 50-245/90-05 on 900221-0402 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty 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
December 9,1987 Docket No. 50-336 t'r. Edward J. Mroczka Senior Vice President )
Nuclear Engineering and Operations Northeast Nuclear Energy Cortpany P. O. Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Mroczka:
SUBJECT:
MILLSTONE NUCLEAR POWER STA110N, UNIT NO. 2 INSERVICE INSPEC110N (TAC NO. 59265) i We are in the process of reviewing the Inservice Inspection Program for Millstone Unit 2. In order that we tray ccrnplete our review, we request that you respond to the enclosed request for additional information within 60 days following re-ceipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respcodents; therefore, Cf'B clearance is not required under P. L.96-511.
Sincerely gm (M'7 Eff' David H. Jaffe, Project Manager Project Directorate I-4 Division of Reactor Projects I/II ;
Enclosure:
Request for Additional Information cc: Plant Service List I
Distribution; m
,; Docket Eile. NRC & Local PDRs PDI-4 Reading S. Varga B. Boger S. Norris D. Jeffe R. Ferguson J. Stolz OGC-Bethesda E. Jordan J. Particw ACRS (10) [ Gray File] j LAP I-4 PDI-4 ' ' . j' PD SN 1s DJaffe y JSt Iz 12/ 7 /87 12/%/87 ( 12/ /87
$712150209871209 R
G ADDCK 0500033$
PDR i
Mr. Edward J. Mroczka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc:
Gerald Garfield, Esq. Mr. Wayne D. Romberg Day, Berry & Howard Superintendent Counselors at Law Millstone Nuclear Power Station City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 1 Office of Executive Director for Operations 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems 4 Combustion Engineering, Inc. - '
7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat, Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Radiation Control Unit i Department of Environmental Protection State Office Building Hartford, Connecticut 06106 Mr. Theodore Rebelowski U.S. NRC P. O. Box 615 Waterford, Connecticut 06385-0615 Office of Policy & Management ATTN: Under Secretary Energy Division .
80 Washington Street l Hartford, Connecticut 06106 '
REQUEST FOR ADDITIONAL INFORMATION Millstone Unit 2 INSERVICE INSPECTION PROGRAM Your letter dated December 23,1986(1) submitted a revised inservice inspection (ISI) and inservice testing (IST) program, and relief requests for i the second 10-year inspection interval of Millstone Unit 2. This submittal l also included additional information in response to our specific questions transmitted in Reference 2.
A review of the necember 23, 1986 submittal indicates that certain ;
detailed information necessary for the NRC to review and approve the ISI plan has still not been incorporated into the MP-2 ISI program documentation. The following questions and comments address tne areas where additional detail and clarification are required.
S
- 1. In the MP-2 plan, many procedures are specified, others are referenced as "special", and some have been left blank, giving no reference. While the review of examination procedures is a Region function, they should be specified in the plan for completeness and as a reference for the Regional Office. Please describe all "special" procedures and reference all other procedures. For procedures that have not been finalized, please providt both a reference and an estimated date for final completion. '
- 2. In addition to providing the basis for the extent of the examination sample, the ASME Code provides guidelines for implementing the inspec-tions during each 10-year interval . Please provide an overall narrative description of the method used to meet the requirements of Sections IWB-2412, IWC-2412, IWB-2420, IWC-2420, and IWF-2420 for each examination category. (See paragraphs 8,13a, and 14 for additional discussion.)
1 1
l SPECIFIC COMMENTS INTRODUCTION - Paragraphs 1.0 and 1.3 ,
l l
- 3. Paragraph 1.0 of the Introduction states that the applicable code for developing the MP-2 ISI program is the ASME Boiler and Pressure Vessel ;
Code,Section XI, 1980 Edition with addenda through Winter 1981 Addenda l (ASME 80W81). Paragraph 1.3 of the Introduction states that ASME 74S75 will continue to be used for extent of examination of Class 1, Category B-J and Class 2, Category C-F and C-G pipe welds. l Please list any ASME Code cases that have been applied in developing the MP-2 ISI plan in conjunction with the stated codes and describe specifi-cally where and how the code cases have been applied.
APPLICABLE ASME SECTION XI EXEMPTIONS EMPLOYED AT MILLSTONE UNIT 2
- 4. This section restates the paragraphs from ASME 80W81 which relate to exemptions with very few references to specific applications at MP-2.
The section also acknowledges that the exemptions stated in IWC-1220, Table IWC-2520, Categories C-F and C-G, and paragraph IWC-2411 in ASME 74S75 will be applied. The application of the stated and implied exemptions to development of the MP-2 ISI program should be clarified and documented in the plan. For example, the system classification diagrams given in Section 3.0 include a much broader range of piping and systems within Class 1 and 2 than is scheduled for inspection in sections 4.0 and 5.0. Presumably, many piping systems, subsystems, and components were exempted from inspection through application of Code exemptions.
Please provide a listing of systems, subsystems, components, or zones exempted from inspection for each class because the sample of welds selected for examination cannot be determined without this information.
Also, please provide supporting information to explain each exemption '
based on Code requirements.
2
l SECTION 4.0 - ISI PROGRAM CLASS 1 COMPONENTS Cateaory B-A (Shell and Bottom Head Welds in Reactor Vessel)
- 5. This section lists the 20 reactor vessel shell and bottom head welds in Category B-A "for information" but does not specify which welds will be examined in the second interval. Please state specifically which Category B-A reactor vessel shell and bottom head welds (including code item number) will be examined during the second interval to meet the requirements in Table IWB-2500-1 of ASME 80W81. i l
Cateaory B-A (Welds in RV Head)
- 6. This section lists the eight reactor vessel head welds in Category B-A "for information" but does not specify which welds will be examined in the second interval. Please state specifically which reactor vessel head I welds (including code item number) will be examined during the second interval to meet the requirements in Table IWB-2500-1 of ASME 80W81.
Cateaory B-B (Welds in Steam Generators - Primary Side)
- 7. The note indicated by " * " in this section of the MP-2 ISI plan states that the " code does not consider Combustion Engineering (C-E) design steam generators with tubesheet-to-tubesheet extension weld." The Examination Requirements for Category B-B, Item B2.40, Tubesheet-to-Head )
Weld, are shown in Figure IWB 2500-6 of ASME 80W81. Design A in this figure is representative of the C-E steam generator design and shows that the required examination volume (ABCD) includes the circumferential weld on each side of the extension ring and any meridional welds in the extension ring. Accordingly, circumferential welds BHC-2 and BHC-3 as well as meridional welds in the extension ring (BHV-1, 3, 5, 7) are all included in the examination volume for Item B2.40.
3
' 8 Unless there is additional technical information to support your con-clusion that the weld is exempt from examination, please respecify the examination of the steam generator primary side to meet the requirements of Category B-B of the Code; i.e., in addition to the tubesheet weld area, the scheduled examinations must also include (a) a circumferential weld in the SG head such as BHC-1 (stay cylinder base to hemisphere) and (b) a meridional head weld, such as BHM-3 already scheduled.
Cateaory B-F (Dissimilar Metal Welds) 1
)
- 8. Of the 28 Category B-F welds scheduled for examination, almost 30% are being examined in a different period of the secono inspection interval The ASME Code requires, within the
~
than they were in the first interva..
limits of practicality (IWB-2420), that examination sequences established in the first interval be maintained in subsequent intervals such that the time interval between repeated inspections from inspection interval to inspection interval is approximately ten years.
Please provide justification for the significant changes in the sequence of Category B-F examinations in the second interval.
Cateaory B-J (Pressure Retaining Welds in Piping)
- 9. The plan indicates that ASME 74S75 is being used to determine the extent of examination of Class 1 pipe we'ds in accordance with 10 CFR 50.55a(b)
(2)(ii). ASME 74S75 requires that the extent of examinations performed each interval include (i) 25% of circumferential joints (including any adjoining 1-ft sections of longitudinal welds) and (ii) 25% of the pipe branch connection joints. Longitudinal welds covered under Items B9.12 and B9.22 are required '.n be examined only if the longitudinal weld intersects a circumfered bl weld to be examined under Items B9.11 and 89.21. The longitudinal welds are not to be included in the calculation of the percentage of welds examined.
4
(e) The plan indicates that 64 Class 1, Category B-J, circumferential welds will be examined during the second interval. In RR#3, relief is requested in the examination of 29 of these welds. Please explain the method used to select the Category B-J welds in order to minimize the number of welds for which relief is requested.
Cateaory B-K-1 (Integral Attachments for Piping, Pumps, and Valves)
- 10. The only items in Category B-K-1 of the MP-2 plan are the 16 welded attachments to the primary coolant pumps. C-E plant designs have included welded attachments to Class 1 piping, such as safety injection piping, that are covered by Category B-K-1 requirements. Please confirm that all items in this category have been listed.
Cateaory B-P (System Pressure Tests for all Class 1 Components)
- 11. The only items identified for examination under Category B-P in the component listing of Section 4.2 are the pressurizer nozzles in Item B15.20 (system leakage on the pressure retaining boundary of the pres-surizer). Please provide a description of other itens to be examined under Category B-P.
SECTION 5.0 - ISI PROGRAM CLASS 2 COMP 0NENTS l
Cateaory C-A (Pressure Retaining Welds in Pressure Vessels)
- 12. Weld 2-SC-1A is listed as an Item C1.20 head circumferential weld in Section 5.1 under steam generators. This weld is not included on the component list in Section 5.2 nor is it shown on the drawing in Section 5.3. Please clarify the wela designation 2-SC-1A and its location.
6
Cateaory C-B (Pressure Retaining Nozzle Welds in Vessels) 13(a) Note 3 of Table IWC-2500-1 under Category C-B requires that the nozzles selected initially for examination be examined over the service lifetime of the component. One feedwater nozzle on SG #1 and one main steam nozzle on SG #2 were examined during the first interval. For the second interval, examination of both nozzles on :
SG #2 is proposed. Please explain why MS-1 on SG #1 has been selected rather than MS-1 on SG #2. ,
1 13(b) The Code requires that nozzle welds included under Item C2.20 must be examined with both surface and volumetric methods. Only surface examination appears to be scheduled for the nozzle welds of the Shutdown Heat Exchangers. Please explain the reason that both the surface and volumetric examinations are not included.
Catecory C-C (Integral Attachments for Vessel Piping, Pumps, and Valves)
- 14. In reviewing Category C-C of the plan, some differences have been iden-tified between the zone drawing, the examination sample (Section 5.1),
and the component list (Settion 5.2). For example, Component No. 312012 is listed for examination in the first period of the second interval in Section 5.1, but this component is not listed in Section 5.2. Component No. 307009 is listed in Sections 5.1 and 5.2 under Item C3.20 (integ-rally welded piping attachment), but Drawing 25203-20160 for Zone 2-15 does not indicate that 307009 is an integrally welded attachment.
Several welded attachments to the piping, such as 404024, 407005, 507001, 504001, 304029, 312016, 4120166, 412009, and 412003 are shown on the zone isometric drawings for Zones 2-15 and 2-16, but are not included in either the examination sample in Section 5.1 or in the component list in Section 5.2.
Please clarify the specification and selection of the examination sample under Category C-C. Please explain the basis for not including in the 7
q
. j component listing (Section 5.2) or in the examination sample (5.1) all welded attachments to the pressure boundary, as identified in the zone drawings.
Categories C-F and CF/CG (Pressure Retaining Welds in Piping) l
- 15. The plan indicates that 74S75 is being used to determine the extent of examination for Categories C-F and C-G in all Class 2 piping. The l information required to complete the review is essentially the same as i described for Category B-J in Paragraph 9 above. Please provide the same general information as requested in (a), (b), and (c) of Paragraph 9.
SECTION 7.0 - COMPONENT SUPPORTS Cateaory IWF (Component Supports)
- 16. The ISI Program includes a selection and schedule for 578 component support examinations, including 115 Class 1 supports, 96 Class 2 supports, and 367 Class 3 supports. The supports have not been classified according to Code Category F-A, F-B, and F-C.
(a) Please revise the component listing (Section 7.3) to include i
Category and Item No.
(b) Please provide a brief narrative of the basic concepts used for determining the examination sample, including the application of exemption criteria. I References
- 1. E. J. Mroczka (NNECo) to A. C. Thadani (NRC), December 23, 1986; response to request for additional information, revised inservice inspection l report attached. l
- 2. D. H. Jaffe (NRC) to J. F. Opeka (NNECo), July 29, 1986; request for additional information on the inservice inspection program.
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