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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: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] |
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Y-9 m ..
JAN 1 i 1931 s
Docket No. 50-336 File Nos. RI-90-A-180, RI-90-A-198 ct e ton FolA. Ib 1- ---
==Dear
Subject:
==
Allegations Concerning (1) Wide Range Nuclear Instrumentation Operability, (2) Operator Attentiveness, and (3) Alignment of Reactor Coolant Flow Transmitters.
The Region I office has completed its followup in response to the concerns you brought to our attention on October 8,1990 and October 26, 1990 alleging that (1) wide range nuclear instrumentation was not operable as required by technical specifications, (2) personnel were not attentive to duties or were sleeping, and (3) alignmeat of the reactor coolant flow transmitters was not accomplished properly.
We found your allegation concerning the operability of wide range nuclear instrumentation to be unsubstantiated and have documented our findings in NRC inspection report, 50-336/90-22, section 5.3.3. We concluded that at least two of the four instruments were operable during fuel movement, although one channel was spiking.
We also found your allegation concerning two licensee workers who were reportedly found asleep to be unsubstantiated and have documented our findings in section 3.7 of the above noted report. We were unable to confirm that the ,
individuals were inattentive or that they compromised work control. _
Finally, we found your allegation concerning the improper alignment of reactor coolant flow transmitters to be unsubstantiated and documented our findings in section 5.3.1 of the above noted report. We concluded that the alignments were completed adequately although a proposed revision to the alignment procedure provided more detailed instructions for use of an improved test rig.
Copies of the above noted reports are attached for your information. We appreciate your informing us of your concerns and feel that our actions in this matter have been responsive to those concerns. Should you have any additional questions, or if I can of of further assistance in this matter, please call tse collect at (215) 337-5120.
Sincerely, Orivn9105ned By Donald R. Haverkamp, Chief Reactor Projects Section 4A Division of Reactor Projects 0FFICIAL RECORD COPY ALLEGATION COL RI-90-A-0198 - 0001.0.0 01/09/91 9212220052 920608 PDR FOIA CUILD91-162 PDR
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SAMPLE RECORD OF ALLEGATION PMEL DECISIONS
$1TE: N)/- i ' /4 - O/ i$ PANEL ATTENDEES:
l ALLEGATION NO.: /77 5 - 2 Chairman - f (Mtg.(J12345) Branch Chief - lA)en a, cc.4 y DATE: to l15 /9 0
! PRIORITY: High Medium Q.,w- Section Chief (AOC) -
SAFETY $1GNIFICANCE: Yes No Unknown Others - 1/ai( ,
1 CONCURRENCE TO CLOSE00T: 00 BC SC No CONFIDENTIALITY GRANTED: Yes
($ee Allegation Receipt Report) /
Yes No i IS THEIR A 00L F]NDING:
15 CHILLlHG EFFECT LETTER WARRANTED: Yes No l Yes No HAS CHILLING EFFECT LETTER BEEN SENT:
No HAS LICENSEE RESPONDED TO CHILLING EFFECT LETTER:Yes l l ACTION:
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203 443 BOW i OCi 25 '90 15:06 HRC MILLSTONE OFFICE P01 Q- n l
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OVERTIME AND RCS FLOW ALLEGATION INFORMATION A11eger set internal n. ail on 10/22/90 and inspector aware of 9 issues on 10(25/90. 4..,.
Refer to Memo dated 10/22 :
k i 1. 'This its is addition'al information/ licensee response to
.t speed calibration.
I alleger's Refer to 10/12/90 concerns in fon RCS orma tion.. flow: and 7,i
E *
- 2. Self-exp1anatory ,
s *
- 3. Overtime Issues -
- a. Service Water Gresup (alleger believes is is CNF contractor personnel). g
"{ . b. Alleger received information from a maintenance I mechanic and a maintenance electrician.
- c. The inspector identified the source of the alleger's k, , information was a senior reactor operator. The k operator involved was a plant equipment operator with the event occurring app eximately 2-3 weeks ago.
'The inspector plans to ciscuss the specifics with the senaar reactor operator on 10/26. As of 10/25 the 1
operator has a day off. ,
y c. The alleger received this issue from the same senior
, reactor operator. -
h
?, 4. Inspector has nothing further to add to this issue.
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j SAMPLE RECORD OF ALLEMTION PANEL DECISIONS
$11E: b ~1 PANEL ATTENDEES:
(A) gai. s At. LEGATION NO.: kl- 90 -M - C 2C 4 Chairu n - il m
DATE: it/u/10 (Mtg.(J/2345) Branch Chief - EcW t PRIORITY: High Medium h Section Chief ( AOC) bi SAFETY $1GNIFICANCE: Yes Others - b rs f 6faq-hh$ '
No(WUnkh
l CONCURRENCE TO CLOSE0VT: 00 (BC/ SC CONFIDENTIALITY GRANTED: Yes No (See Allegation Receipt Report) 15 THEIR A 00L FINDING: Yes No __
Yes No 15 CHILLING EFFECT LETTER WARRAkiED:
Yes No HAS CHILLING EFFECT LETTER BEEN SENT:
Yes No KAS LICENSEE RESPONDED TO CHILLING EFFECT LETTER:
ACTION:
1)% rm 1 .L, J s wa s leIuwec i efw h i,ss M. nl ied; bc.vh Curan ( m et L<
- 2) c Whr i d %.
Ct.bcGBm, m e[ m'e,\ _t b Ac,swud 6 d cWMtotb NRC
- 3) [ $1tu> =+ - $ tk U . .
E b a.M e,e. d 4 0 6 -. <,2 tv(ce N4 E ttu w.b kt at mbs
- 4) \b MOC e a O r, v 1-o k e we a tb e k8n be WreEed .
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t .v nM , Mmbi information in this record was delete I
in accordance with et)d motInfoma Act, exegtion F01A - .
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~ ALLEMTION RECEIPT REPORT l . ,. E' Mv (' $ Ic h d 9 0 nm Awegatson uo.&qb-4-oto P (leave blank)
Name: Address: \
Phone: City / State / Zip:_ .
Confidentiality:
Was it requested? Yes No k' ,
Vas it initially granted? Yes No Was it finally granted by the allegation panel Yes No Does a confidentiality agreement need to be sent to a11eger? Yes No Has a confidentiality agreement been signed? Yes No Memo documenting why it was granted is attached? Yes No e b- Position /
Title:
Facility: /W 5 -L oocket No.: So/33 (Allegation Sumary (brief description of concern (s)[. ') bwhend cSet, dica
[('. 2 Y/9 6 ,, c3 ~ .c 24 A l C_ 'OdM t . u k W - d'. J (
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Number of Concerns: I _
Employee Receiving Allegation: bdic /,cM /Mce )$d M b-Iaiur (first two initials and last name)
Type of Regulated Activity a ,y', Reactor (d) _ Safeguards b Vendor (e) ~ Other:
c ~ Haterials (Specify)
Haterials License No (if applicable):
FunctionalArea(s): 'F(a Operations e Emergency Preparedness (b Construction f Onsite Health and Safety (c Safeguards ~g Offsite Health and Safety (d) Transportation h Other:
(NRC Region I Form 207
/ Revised 10/89) . .\
- Information in this record was deleted -
in accordance with lh Freedom of Informat(on se ,
.y n . : ,.4 ' R ' ' Act,'exMptions' V '#':" 9 ' ' * ! S F F N. R * ~ '2 ' .
F0lA M HM "/-
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l CONCERNS FROM A NORTHEAST EMPLOYEE The res' nt insoector received en internal memorandum dateo The inspector had follow-up discussions on A he clarification of the memorandum with the alleger on
)
Issue The alleger poses concerns and questions on proceduraltion in adequacies and implementation. The proc re and he question are IC 2419C Section 5.5.6. 01 er mocou e (HJTC) alleger was tasked with heater junction reinstallation using IC 242iC.
The specific issues associated with procedure IC 2419C ares
- a. IC 2421C step 5.5.6.i requires a visual inspection Notify IC of HJTC connector assemblies on eachThe cable.
alleger said he supervision is damage is apparent.
identified problems with 3 connectors (Zi #4 and #7; Z2
- 8). The specific problems with the 8-pin connector was not identified to the inspector, however the alleger notified his immediate upgrade supervisor at the job location. The supervisor notified his
' department head who told the workers to reconnect the HJTC connections. During the work activity a Quality Service Inspector was on location. The inspector asked the alleger if this item was documented in the QSD surveillance form. The alleger did not know.
- b. IC 2421C step 5.5.o.1 also requires a visual e:: amination of a grafoil gasket at the Litton Veam connector for signs of degradation. The alleger did :
not know where to look for this item, and therefore ~
auestioned if the procedure should require additional drawings to incluce the location of the grafoil gasket.
Tne alleger's indecencent research identified the locat2cn of the grafo11 gaskets in NUSCo drawing 2500!-39108 sheet 2.
- c. No procedure drawing is present to identify connec ors and there location. This task was accomplished by measurement of relative length of cables by the alleger. According to the alleger the cables have etched ID numbers however, their physical location makes it impossible to acquire the numbers.
- d. The caution procedure action prior to steo 5.5.6.7 requires the the connectors mate up snug and turn the collar 90 degrees. This action crimps the copper seal and keeps the collar from moving during operation.
According to the alleger, the caution step was recently A 90 PORC approved as a Intent procedure change.
V degree turn from hand tight according to the alleger ~
f rom discussions with NNECo engineering appro: imates to 25 ft-lbs. On October 30, NNECo engineering identified the correct torque value for the connector collar as 31 A l ft-lbs as referenced in a 1986 Combustion Engineering '
1etter. The licensee incorporated-this into the procedure as a non-intent procedural _ change on October
- 30. The alleger does not believe this change to a ,
caution note in procedure IC2421C as a non-intent change. ,
- e. According to the alleger dust covers are installed on the HJTC connectors when disconnected as depicted on procedure figure G.5 of IC2421C. Inspector review of procedure IC 2421C section 5'.5.6 on reconnection of connections did not identify a specific procedural step i
to remove dust covers on the connectors.
- 1. IC 2421C step 5.6.4 requires verification of HJTC per IC 2419C. The verification per IC 2419C is normally completed prior to reconnection of cable per IC2421C. 1 j
I i Overall, the alleger believes the licensee is not following procedures based on the condition of IC 2421C, or if the procedure is followed no other technicians are identifying the problems and requesting ;
l i
resolutions.
INSPECTOR ASSESSMENT l The inspector believes this item should be turned ove to the licensee for response. HJTC connectors are EED components and part of the inadequate core cooling ~ .
J
! (ICC, system. R l
ADDITIONAL INFDPMATION l
The allecer heard third hand. that a recent polovee to the l l
t1111 stone 3 IC department was labeled as the/EEEEEEEEEE at l
Millstone 3. The technician recently transfered 1-om the ,
chnical tr '7ing organi:ation. His previousThe position was i
l f ame of the l ~ associated'The with Millstone alleger 2. is f' individual presenting this for use ised on his past H61 issues.
Recommendation: Refer to 01.
i l
1C 2421C Page 13 Rev.6 g
'5 5.5.5 CEDM Power Cabling 5.5.5.1 Visually inspect the connector assemb'ies on each cable N
for signs of degradation or damage.
- a. If the connector must be reworked or replaced, ,j _
reference IC 2421E, Head Area Cable Support l System Connector Assembly Procedure. .,
5.5.5.2 Reconnect the CEDM power cabling at disconnect l panels T323, T326, T333 and T336. Utilize Table 2 l l
and Figure 8.3 to insure proper connections, 5.5.5.3 Reconnect the CEDM power cabling to the CEDM stack on the head. Utilize Table 2 and Figure 8.1 to-locate and identify the appropriate CEA assembly.
5.5.6 HJTC Cabling dwwxwwwwwwwNwwwwwNwwwwwwxwwwNwN q CAUTION t -
- The HJTC cabling and connectors are environmentally qualified ;
) (EEQ) components. Copper seal rings must be installed in the ;
s G&H connector assemblie: at the probe to mineral cable interface s
& t rest re qua ifi ati n f 11 wint h'ead cable removal.' Seal rine I H(ShM D
~
replacement is specifically addressed in the body of the procedure 1 -
( below. ! -
hww wwwwumwwwwmwwwummwmmm' 5.5.6.l' Visually inspect the cc=ctor assemblies en eac }
for signs of degrad_ation_or_ damage.
~ - . - - . . -
_- m Visually inspect the Graf6il~gE~sk6t at the I~itton Veam ,
connectors for the HJTC cables for signs of .'
. -Megradation 'or damage ._. _
- a. Notify the Assistant I&C Supervisor if d[ mage 7s
- - - apparent. -
5.5.6.2 Reconnect the HJTC c$bling at disconnect panels T323, T326, T333 and T336. Utilize Table 2 and-Figure 8.3 to insure proper connections.
g 5.5.6.3 Carefully uncoil the HJTC mineral cables stored in the
// HACSS trays and route the cables to the appropriate t
HJTC probe assembly. Reference Figure 8.4 for HJTC mineral cable routing.
5.5.6.4 Obtain new copper seal rings for the G&H connectors at the probe-to-mineral cable interface.
%:.J.
- a. Seal rings stock code is 50700943 (Comb. Eng.).
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1C 2421C Page 14 Rev. 6 m
V
- 'E NI: 5.5.6.5 OA HOLD POINT - Visually inspect the copper seal rings to ensure they are clean and free from radial '
~
scratches and indentations.
5.5.6.6- QA HOLD POJNT - Install the copper seal ring on the <
G&H receptacle to rest on the seal collar. !
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f' N \\\\ \ \ \ \ \ \ \ \\\\\\ \\
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Iwo nwr neans - the surface of 1:cth trale and female cwEm g g*[
f \ are z:nted and snug, then turn the threaded collar 90 degrees. ,
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\ niis will c: ring the copper seal and keep the collar fran m:nr.mg \s ,
\. g aurir.g operation. . \
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5.6.7 Carefully mate the G&H connector plug and receptacle,j'
_s_._ . _ _ _
engage the threads and_ha.nd tighten. - -
5.5.6.8 Repeat Steps 5.5.6.6 and 5.5.6.7 for the remaining HJTC probe connections.
5.5.6.9 QA HOLD POINT - Jnitial and date 1&C Form 2421C-1.
h*
5.5.6.10 Secure the HJTC mineral cable to the head cable support unistrut using "TEFZEL, TYZ-27M" radiation .
resistant ty-raps. Do not exceed three feet between ty-raps. Ty-wrap stock code is 6?4n0350.
5.6 Cable Verification ,
5.6.1 CEA Position freed Switch) Cable Verification
$'9 5.6.1.1 Energize the +5.140 VDC reed switch power supplies ,
P' and the +28 VDC logic power supplies located in the 14'6" East DC Switchgear Room, CEDS Logic Panel (Reference Table 1 items,11 and 12).
5.6.1.2 Energize the metrascope at Control Room Panel C04F.
'5.6.1.3 Establish Communications between the metrascope and the reactor vessel head cable 5 .
74
/[
5.6.1.4 Raise and lower the reed swi *est magnet assembly along the side of CEA #1 reed switch shroud.
l 5.6.1.5 Verify that the metrasco'pe display for CEA #1 changes with the magnet position. Record on 1&C Form 2421C-1.
." 5.6.1.6 Repeat Steps 5.6.1.4 and 5.6.1.5 for the remaining reed
/ switches.
[ 5.6.1.7 ]f any reed switch display does not respond correctly,
m IC 2421C Page 15 Rev. 6 f
( -
5.6.2 CEDM Power Cable Verification 5.6.2.1 Verify that CEDM motor generator output breakers are (
red tagged open.
5.6.2.2 Disconnect the coil power cables identified on l&C Form 2421C-1 for the CEDM under test.
5.6.2.3 Using a 500 volt meggar, test the cables listed on 1&C Form 2421C-1 to ground. Record the "As Found" readings on 1&C Form 2421C-1.
5.6.2.4 If the. values recorded in Step 5.6.2.3 are within specification, record them "As Left". If any values are not within specification, initiate an AWO to investigate and correct the problem.
5.6.2.5 Measure the coil resistances listed on 1&C Form 2421C-1 and record the "As Found" values.
5.6.2.6 If the resistances recorded in Step 5.6.2.5 are within (
the " Desired" values, record them "As Left".
5.6.2.7 If the resistance values are not within tolerance, initiate on AWO to investigate and correct the problem.
C a. 5.6.2.8 Reconnect the coil power cables disconnected in Step 5.6.2.2, initiating the appropriate blocks on 1&C ,
Form 2421C-1.
- 6 5.6.3 Verification of ICI cables is nerformed under SP 2407.
pm #4 Verification of heated junction thermocouple probes is performed !
pr.6 i 5.6.4
]
tg -g. under IC 2419C. ,,
5.7 EEO Maintenance Activities 0 h
5.7.1 Required EEQ Maintenance activities are identified in 242.10 Attachment 9.1. Assure that these tasks are accomplished during Mf Head Cabling removal and installation.
- 6. RESTORATION 6.1 Ensure that all data sheets are properly completed.
,6.2 Inform Operations that IC 2421C is complete, e
' 6.3 Ensure that all lifted leads / removed weidmuller pins have been replaced.
- 7. TABLES l, 7.1 Table 1, Equipment Tag Out
" 7.2 Table 2, Cable Connections
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(Typ. D pinces) .
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(Typ. 8 places) ,
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. , llJTC PROBE ASSEMBLY IF-2 .'
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1C 2421C Page 1 of 2 -
Rev.6 Attachment 9.1 y . ..
. ATT ACHMENT 9.1 t'
EED COMPONENT M AINTENANCE REOUIREMENTS ,
EOUTPMENT: HEAD ASSEMBLY CABLING / CONNECTOR ASSEhBLIES -
(PMMS ID) :
A. INCORE DETECTOR ASSEMBLY CABLING B. HEATED JUNCTION THERMOCOUPLE ASSEMBLY CABLING , ,
C. HEAD VENT SYSTEM CABLING MANUFACTURER: LITTON VEAM/G&H/KERITE/ITT MODEL NUMBER: REFERENCE IC 2421E FOR SPECIFIC PART NUMBERS ,
SERVICE: A. INCORE DE1 eCTOR ASSEMBLY: CORE EXIT C THERMOCOUPLE INPUT TO INADEQUATE CORE
'd COOLING CABINET (ICC). .
B. HEATED JUNCTION THERMOCOUPLE '
ASSEMBLY: REACTOR VESSEL LEVEL
-MONITORING SYSTEM (RJTC). ,
C. HEAD VENT ASSEMBLY: REACTOR VESSEL i- HEAD VENT SYSTEM.
! ENVIRONhENTAL -
BOUNDARIES: A. HJTC CONNECTORS (G&H) ARE AN INTEGRAL PART OF TrIE MINERAL CABLE ASSEhBLY.
COPPER SEAL RING PROVIDES WATERTIGHT l BOUNDARY BETWEEN MATING CONNECTORS.
B. INCORE DETECTOR AND HEAD VENT
,, CONNECTOR TO FIELD CABLE INTERFACE.
2.
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(^
t^ l IC 242]C Page 2 of 2 --
Rev.6 Attachment 9.1
.e t
ATTACHhfENT 9.1 g
'i EEO COMPONENT M AINTENANC2 REOt3IREMENTS <
.(continued)
MAINTENANCE ,
REOUIREMENIS: A. MF W COPPER SEAL RINGS SHALL BE INSTALLED IN THE HJTC GJ H CONNECTORS EACH TIME THE CONNECTOR IS REMATED.
B. THE HJTC AND ICI THERMOCOUPLE , , ,
ELECTRICAL PENETRATION FIELD CABLE INTERFACE SHALL BE SEALED WITH RAYCHEM WCSF-N.
i MISCELLMJEOUS: 1. CONNECTOR ASSEMBLIES SHALL BE VISUALLY INSPECTED FOR SIGNS OF DEGRADATION OR WATER INTRUSION EACH TIME THEY ARE
'3 g DISCONNECTED _FOR REFUELING ACTIVITIES.
- 2. IF CONNECTOR ASSE.MBLIES MUST BE -
RE-WORKED.OP REPLACED, IC 2421E SHALL u BE UTILIZED AS THE ASSEMBLY PROCEDURE. -
- 3. THE LITTON VEAM CONNECTOR AT THE- )
HACSS DISCONNECT PANEL FOR THE HJTC CABLING HAS BEEN RETROFTITED \\TTH A GRAFOIL GASKET TO ENSURE QUALIFICA' HON.
l l APPROVEQ .- ,
^
[ I&C DEPT.
L MAINTENANCE .
- li TASF*.: 1. REMOVAL AND RESINTALLATION OF HEAD l ,, CABLING.
L
// 2. AU. ELECTRICAL TESTING AND TROUBLESHOOTING ACTIVITIES l
ASSOCIATED \;rrH THE HEAD CABLING.
- . 3. RE-MAKE AND FE# INSTALLATION OF ,-
6 - -
CONNECTOR ASSEMBLIES AS DIRECTED :
BY IC 2421E. ,
n _ - , - .-
-_ _ . . . . , - . . . , . . . _ _ , . , _ _ - . _ . , . _ _ , _ , _ . . , . _ . . . . _ _ . . . _ . r .. _ _. _. _ _ . , _
IC 2419C
- 1. OBJECTIVE (
KL.1. T o ve ri f y the integrity of the Heated Junction Thermocouple probe (HJTC) assemblies upon; i
1.1.1 Initial receipt of probe assemblies, or; 1.1. 2 Removal from the reactor head assembly pressure boundary, or; ,
- w. ~
1.1.3 Reinstallation following refueling outages, j
/
'~
- 2. ACCEPTANCE CRITERIA
' ' ' ' "] ._
2.1 All temperature display readings, test voltages and continuity checks defined within this text meet the specified criteria.
- 3. TECHNICAL SPECIFICATION REFERENCES 3.1 None
- 4. PREREOUISITES 4.1 All required test equipment is available and within its
(..}f N' calibration frequency. ,
4.2 Access to the probe assemblies is available.
- 5. IHITIAL CONDITION 5 ;
5.1 The 55/SCO has authorized the test and has signed I&C Form -
2419C-1 or 2419C-2 as applicable.
5.2 120 Vac power is available at the test location. The HJTC test box requires this 120 Vac source power.
5.3 The necessary Radiation Work Permits (RWP) have been obtained if the probe checks are to be performed in a contaminated area.
- 6. PRECAUTIONS
/ 6.1 Use caution when working with the HJTC probe cabling and connectors. Do not bend or kink cabling.
6.2 Observe all RWP requirements, the HJTC probe assemblies are highly irradiated once installed and exposed to primary coolant.
6.3 Do not exceed 50 Vdc when performing insulation resistance checks.
(3/
M Concern The alleger's concern surrounds the operation of channel 'C' '
of the' reactor protection system. Specifically, the concern is the operation of the reference voltage output. The reference test voltage was not maintaining its acceptance -
criteria of +/ .003 vdc. The ref erenr.e test voltage is for the reactor protection system calculators for TMLP trip, RCS flow signal process, and for a DVM output at the RPS panel.
Recently, the alleger completed the RCS flow calibration under procedure SP-2404A. The u11eger submitted an ICR to document an out-of-specification for the test voltage output. The output values were 004 vde and +.005 vdc.
The alleger was questioning the orerability of channul 'C' of the RPS with historic out-of-spec test voltage outputs.
Historically, the alleger provided dates and times that the reference voltage was out-of-specification Enig Authorized Work Order 3/9/90 M2-90-02559 5/5/90 M; cc-o 7:e MC-90-05:0~
MC-90-05460 9
8/50 Surveillance for SP-2401F e ri SP-2401G Reference drawings are 25203-09069 sheet 40, and 05 00-25190 sheet 6 to identify the reference test voltage aoolication.
- - . - - _ - - ,___