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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 ML20217K3161999-10-19019 October 1999 Forwards Amend 195 to License DPR-61 & Safety Evaluation. Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements B17901, Submits Statement of Personal Qualification (NRC Form 398)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 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 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 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 CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam DD-99-11, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 9910041999-10-0808 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 991004 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 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 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 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 ML20212L1261999-10-0404 October 1999 Forwards Viewgraphs Presented by Licensee at 990923 Meeting with Nrc,In Response to Request 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 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 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 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 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 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 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 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 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 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 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 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 ML20212D0341999-09-20020 September 1999 Expresses Appreciation for Accepting NRC Request for Tour of Haddam Neck Facility During on 991014.Invites R Mellor to Participate in NRC 1999 Decommissioninng Power Reactor Work- Shop:Nrc Insp Program at Decommissioning Power Reactors 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 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) 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 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) 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 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 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 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 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8261999-10-25025 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 CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam 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 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 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 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 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 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 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 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 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 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 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 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 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) 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) 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) 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 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 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 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 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 CY-99-111, Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update1999-09-0202 September 1999 Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update ML20211N9241999-09-0101 September 1999 Forwards Document Classification Form for Insertion Into Emergency Planning Services Department Procedures B17851, Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d)1999-08-27027 August 1999 Forwards Semiannual fitness-for-duty Program Performance Data for 990101-990630 for Millstone Nuclear Power Station, Units 1,2 & 3,IAW 10CFR26.71(d) B17855, Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.7901999-08-17017 August 1999 Forwards NRC Forms 398 & 396 in Support of License Renewal for SRO TE Grilley,SOP-4053-04.Encl Withheld,Per 10CFR2.790 B17849, Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr1999-08-16016 August 1999 Forwards Second Quarter Backlog Performance Rept for 1999, Which Represents Fourth Rept on Mnps Performance Since Restart of Unit 3 & First Status Update for Unit 2.No Regulatory Commitments Are Contained in Ltr B17854, Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings1999-08-14014 August 1999 Forwards Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2,per TS 6.9.1.7.Revised Repts for May & June Also Encl Which Reflect Correct Faulty Printometer Readings B17850, Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept1999-08-11011 August 1999 Forwards First Lhc Quarterly Assessment Rept for Assessment Performed 990621 to 990701.NNECO Taking Appropriate Actions to Address Observations in Rept B17837, Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl1999-08-0707 August 1999 Forwards COLR for Cycle 7, for Millstone Unit 3,IAW TS 6.9.1.6.Explanation of Changes to COLR Also Encl B17657, Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 19991999-08-0303 August 1999 Requests Schedular Exemption from Emergency Plan Exercise Requirements of 10CFR50,App E,Part Iv,Section F,Paragraph 2.c.Requests That Nrc/Fema Evaluated Exercise Be Conducted in Mar 2000 Rather than Sept 1999 B17845, Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered1999-08-0202 August 1999 Forwards Revised Commitment for Surveillance Scheduling & Tracking.Options for Surveillance Scheduling & Tracking Methodologies to Be Incorporated in Standardized Station Surveillance Program Are Currently Being Reconsidered CY-99-048, Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls1999-07-29029 July 1999 Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls B17831, Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap1999-07-26026 July 1999 Informs NRC Staff That Change 3 to Rev 25 of Mnps Emergency Plan Was Implemented on 990715.Change Removes Facility Organizational Charts from Emergency Plan & Identifies Relocation to Nuqap B17834, Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld1999-07-20020 July 1999 Forwards Proprietary Revised NRC Form 398,which Certifies That SL Doboe Has Completed Eligibility Requirements for Sro,Per 10CFR55.31.Proprietary Info Withheld B17811, Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 20011999-07-20020 July 1999 Submits Response to NRC AL 99-02,requesting That Licensees Provide Numerical Estimates of Licensing Actions to Be Expected to Be Submitted in Fy 2000 & 2001 B17836, Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl1999-07-20020 July 1999 Forwards Revised NRC Form 396 & Supporting Physician Rept for Licensed Operator Restricted from Licensed Duties, Effective 990628,due to Medical Condition.Without Encl CY-99-066, Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors1999-07-20020 July 1999 Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors ML20210S9911999-07-18018 July 1999 Requests NRC Intervene for All Shareholders of New England Electric System & to Help with Merger with National Grid Group & That NRC Petition Security & Exchange Commission to Investigate Matter Relative to No Shareholder Options B17835, Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1)1999-07-16016 July 1999 Forwards Rev 33 to Millstone Station Physical Security Plan, Per 10CFR50.54(p)(2).Licensee Determined That Changes Do Not Decrease Effectiveness of Plan.Rev Withheld from Public Disclosure,Per 10CFR2.790(d)(1) B17818, Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.591999-07-16016 July 1999 Provides NRC Staff with Change to TS Bases Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only.Change Was Reviewed & Approved by Unit 3 Plant Operations Review Committee IAW Provisions of 10CFR50.59 B17824, Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 21999-07-13013 July 1999 Forwards Monthly Oeprating Rept for June 1999 & Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident B17816, Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual1999-07-0101 July 1999 Provides Certification That M Lettrich,Has Completed Eligibility Requirements,Per 10CFR55.31 for Operator License.Util Requests That Licensing Action Be Taken for Named Individual ML20209C3911999-06-30030 June 1999 Forwards TS Page 6-3 for Haddam Neck Plant 1999-09-03
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/ [ Northerst Nuclear Energy unstone Noacar power smiion Northeet Ntricar Energy Cornpany P.O. Box 128 Waterford. CT 06385-0128 (860) 447-1791 i
Fax (860) 444-4277 The Northeast l'tditica Systern 1
l April 22,1997 i Docket No. 50-213 50-245 i 50-336 l 50-423 i B16375 l Re: CAL 1-97-010 U. S. Nuclear Regulatory Commission i ATTN: Document Control Desk l Washington, DC 20555 Haddam Neck Plant Millstone Nuclear Power Station, Units 1,2 and 3 Response to Confirmatory AcJon Letter l References (a): H. J. Miller and W. D. Travers, USNaC letter to B. D. Kenyon,
" Confirmatory Action Letter," dated March 7,1997.
(b): J. K. Thayer letter to USNRC, " Response to Confirmatory Action Letter," dated March 31,1997.
In our letter dated March 31,1997 [ Reference (b)], Connecticut Yankee Atomic Power l Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) committed to l conduct a review of currently licensad operators to determine the extent to which the ;
submitted medical certifications (NRC Forms 396) accurately reflect the required I physical examinations and medical tests, and to submit the results of this review by April 23,1997. This commitment is reflected in Confirmatory Action Letter 1-97-010 ,
[ Reference (a)] as commitment #6. Summarized below is the results of our review. !
l An independent medical study was conducted to determine the extent to which license applications submitted to the NRC for the Millstone Units and the Haddam Neck Plant !
f have been based on correct and complete medical information, and that changes in the i E90042 *'
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. ,' B16375\Dage 2 medical status for licensed operators have been submitted as required by 10CFR55.
The medical study was performed on-site at Millstone Station and the Haddam Neck Plant from March 24 to March 28,1997, to perform a 100% review of licensed nuclear plant operators' medical records and related medical applications. The review encompassed January 1,1993, through March 1,1997. Overall, it was determined that both Millstone station and the Haddam Neck Plant medical facilities provide an excellent standard of compliance with ANSI 3.4 and NRC Form 396.
The independent medical review team was comprised of medical professionals led by Dr. Benjamin Hoffman, MD. Dr. Hoffman is a principalin Business Health Management (BHM). BHM provides medical services to Seabrook Nuclear Station. BHM, Dr. ,
Hoffman, and his associates have not previously been contracted to provide medical services to the Millstone Station or the Haddam Neck Plant. Attachment 1 to this letter provides the Executive Summary of the medical team's conclusions.
i The medical study had three objectives. Each objective is described below with the esults of the study and any interim compensatory action that have been taken.
Objective 1 100% review of currently licensed operators to determine the extent to which the medical certifications (NRC Form 396) accurately reflect the required physical examinations and medical tests.
l Results Three operators (out of approximately 170 reviewed) had developed medical conditions that were potentially disqualifying. In the first two cases, the potential disqualifiers were not noted on supplemental NRC Forms 396. In the third case, the appropriate restriction for corrective lenses was noted on the Form 396, but the operator did not meet the visual acuity acceptance criteria. The medical review team concluded that all three operators had adequately compensated medical conditions, and it was not necessary to place any restriction on their solo operation.
The medical review team recommended that potentially disqualifying conditions should l be identified to the NRC, along with the analysis and conclusions of the medical examiner.
( . Case #22 (RO/MP1). Onset of adult diabetes. Following the medical review team's 4
audit, the Millstone Medical Examiner prepared a letter describing the case facts,
- analysis, and conclusion. Dr. Hoffman reviewed and concurred with the analysis i and conclusion that the operator did not require any medical restriction. A letter l
] describing the analysis of the medical condition will be submitted to the NRC by May 15,1997.
l l
y.S. Nucl:ar Regulatory Commission B16375\ Pag 3 3 l
. Case #3 (SRO/MP2). Colon cancer. Following the medical review team's audit, the Millstone Medical Examiner prepared a letter describing the case facts, analysis, and conclusion. Dr. Hoffman concurred with the analysis and conclusion that there is no requirement for a medical restriction. A letter describing the analysis of the medical condition will be submitted to the NRC by May 15,1997.
. Case #87 (SRO/MP2). Visual acuity. The operator was examined on March 13, 1997, and the operator's visual acuity did not meet the acceptance criteria. The Medical Examiner accepted the physical examination in error. After the medical team identified the error, the operator was reexamined with a new corrective lens prescription. The April 2,1997 visual acuity exam was acceptable. The operator currently has a license restriction that requires corrective lenses.
Obiective 2 100% review of currently licensed operators' medical records to determine the extent to which medical restrictions, which were identified after Northeast Utilities submitted the i license [ applications) to the NRC, resulted, as appropriate, in a supplemental NRC l Form 396 being filed. l Results
. The medical review team reviewed approximately 170 licensed operators, and identified a number of cases at Millstone in which supplemental NRC Form 396 may l not have been submitted for restrictions requiring corrective lenses, restrictions which developed after the operator's initial NRC Form 396 was submitted. This condition affects approximately ten operators.
. Corrective Action
. As an interim compensatory corrective action, the Millstone Operations Managers i have issued the following directive to all Operations licensed operators: "If you wear ,
prescription corrective lenses, you are required to have the corrective lenses ;
available when standing watch as a licensed operator." )
l
. As a final corrective action, NNECO will submit a supplemental NRC Form 396 for l l
each case not currently docketed in which an operator wears prescriptive corrective lensas. This action will be completed by May 15,1997.
Objective 3 Determine the extent to which the process for licensed operator physicals is defined and documented in accordance with normal industrial medical standards and Millstone administrative procedures.
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U.S. Nuclear Regulatory Commission B16375\Page 4
( Results The medical review team identified a number of charts with missing documentation for
, examination and laboratory elements. One notable omission was urinalysis results l during 1993. This was a transition period based on new Clinical Laboratory j lmprovement Act (CLIA) regulations that were effective in 1993. The issue was .
corrected later in 1993, as evidenced by appropriate lab results being documented in the charts from 1994 to date.
The medical review team concluded that the interfaces, roles and responsibilities, and ;
l process for the administration of operator medical certifications are not currently well i l defined in written administrative procedures.
Corrective Actions
. NU has committed to improve the operator licensing application and medical l certification process (reference the Corrective Action Plan, item 4.6.3.c, submitted in l our March 31st letter). This will be completed by June 10,1997. ;
1 1 l . The Millstone Health Facility will develop a method to track all physical examination and laboratory elements on a routine basis to ensure that all examinations and laboratory work are completed and documented. This action will be completed by June 15,1997.
1
. The Millstone Health Facility will assess the effectiveness of the corrective actions l outlined above. This assessment will be complete by September 15th,1998. !
i The following are CYAPCO's and NNECO's commitments contained within this letter.
All other statements within this letter are for information on!y.
l
! B16375-1 NNECO will submit updated NRC Forms 396 for Case #3 and Case #22, including letters describing the analyses of the medical conditions. This action will be completed by May 10 1997.
B16375-2 NNECO will submit a supplemental NRC Form 396 for each case not currently docketed in which an operator wears prescriptive corrective lenses. This action will be completed by May 15,1997.
, B16375-3 The Millstone Health Facility will develop a method to track all physical i l examination and laboratory elements on a routine basis to ensure that all examinations and laboratory work are completed and documented. This f action will be completed by June 15,1997.
B16375-4 The Millstone Health Facility will assess the effectiveness of the corrective actions. This action will be completed by September 15th,1998.
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U.S. Nuglear Regulatory Commission
. B16375\Page 5 l
Please contact Mr.W. J. Temple at (860) 437-5904 should you have any questions l regarding this matter. !
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY !
NORTHEAST NUCLEAR ENERGY COMPANY A W
- g. Thayer, Recafvery Officer l Nuclear Engineering and Support Services j Attachment (1) :
cc: H. J. Miller, Region I Administrator G.W. Meyer, Chief of Operator Licensing, NRC Region I F. J. Miraglia, Deputy Director, NRR W.D. Travers, PhD., Director, Special Projects Office {
W.D. Lanning, Deputy Director, inspections, Special Projects Office i P. F. McKee, Deputy Director, Licensing and Oversight, Special Projects Office J. P. Durr, Branch Chief Inspections, Special Projects Office j M.B. Fairtile, NRC Project Manager, Haddam Neck Plant :
W.J. Raymond, Senior Resident inspector, Haddam Neck Plant S. Dembek, NRC Project Manager, Millstone Unit 1 T.A. Eastick, Senior Resident inspector, Millstone Unit 1 D.G. Mcdonald, Jr., NRC Senior Project Manager, Mil! stone Unit 2 ,
D.P. Beaulieu, Senior Resident inspector, Millstone Unit 2 J.W. Andersen, NRC Project Manager, Millstone Unit 3 :
A.C. Cerne, Senior Resident inspector, Millstone Unit 3 l
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. l Docket No. 50-213 !
50-245 50-336 j 50-423 B16375 l i
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Attachment 1 )
1 Haddam Neck Plant j Millstone Nuclear Power Station, Units 1,2 and 3 j Executive Summary of Medical Review Team Findings l
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WTITTUTT5T5UU555535TT3 Executive Summary INDEPENDENT INVESTIGATION OF OPERATOR LICENSE MEDICAL RECORDS CONTENTS q
INTRODUCTION...............................................................................................................................................1 P U R POS E . . . . . . . . . . . . . . . . . . . . . . . . .... . ........ . .. ..... ........... .... ............................................................................1 PROCEDURE....................................................................................................................................1 FINDINGS........................................................................................... ................................................2 MILLSTONE REGULATORY COMPLIANCE ....... ............... .. ... . .. .... ... .. ... ... ................. . ... .. .. ... ....... .... .... ... ..... 2 CLIN lC al STANDARDS OF CARE AT MILLSTONE....... .... .. .. . . ..... ... . ..... . ...... .. ..... . . ...... ......... .. .. ..... ........... ...... 3 CONNECTICUT YANKEE REGULATORY COMPLIANCE.... .... . ... ... ... .. . .. ........... ......... .. .. ..... .. .. ........ ... .......... .... 3 CLINICAL STANDARDS OF CARE AT CONNECTICUT YANKEE...... . .......... .............. ....... . .......... ...... ... ......... ..... .. ..... .... 3
SUMMARY
. .............................................................. ... . ..... ...... ....... .... .. .. .... .. .. .... ..... . ....... ....... 4 MILLSTONE.. ..
.. . ..... .. ... .. ......... .... .................. .... .. ... ..... .. ... .. ........ ........ ....... .. ... .. ........ . . . .. ...... ... 4 CONNECTICUT YANKEE.. .. . .... . ............ ......
...... . ... . ......... ... ..... ... ... .... .............. .. ..... .... ... . . .. . .. .... .. .. ... 4 ADDENDUM A: AUDIT TEAM PERSONNEL ADDENDUM B: REVIEW INSTRUMENT ADDENDUM C: ALL FINDINGS
INTRODUCTION PURPOSE An independent audit team conducted an investigation at Millstone and Connecticut Yankee to determine the extent to which
. operator licenses submitted to the NRC have been based on correct and complete medicalinformation, j
. changes in medical status for licensed operators have been submitted as required by 10CFR55, and
. the process for licensed operator physicals has been defined and documented in accordance with standard 9 industrial medical practice.
Mr. Carl Clement, Manager, General Services, commissioned this study.
PROCEDURE From March 24 to March 28,1997, a team of occupational health professionals (see Addendum A) went on-site at t Millstone and Connecticut Yankee to perform a 100% review oflicensed nuclear plant operators' medical records i and related medical applications (NRC 396 Forms).
The review encompassed January 1,1993, through March 1,1997. An audit checklist and evaluation instrument was developed prior to the audit using an Excel spreadsheet (see Addendum B).
This review instrument was developed to assess compliance with ANSI 3.4 (Medical Certification and Monitoring .
of Personnel Requiring Operator Licenses for Nuclear Power Plants,1983) and compliance with proper filing of the NCR 396 Form.
The review was performed in the following sequence:
LevelI All medical charts were initially assessed to determined if they contained all the necessary ;
documents for review. If these were not available, Millstone or Connecticut Yankee medical staff were asked to obtain the missing documents.
LevelII All charts were reviewed by two physician's assistants and one physician (Dr. Schmitz).
Level 111 Any chart having an incompletely documented physical examination or inadequately filed NRC 1 396 Form was further reviewed by Dr. Hoffman. q
. See Addendum C for all findings. To maintain confidentiality, operators' names have been indicated by numbers.
April 2,1997 Executive Summary Independent Investigation of Operator License Medical Reports Page1 of4 :
prepared for Northeast Utilities System by Business Heahh Managem nt. Occupational Heahh + Rehabilitation Inc
5555566666666666 Ettttt4555&&&4%%%Etttt%%M FINDINGS Overall, the NRC 396 Forms were properly completed and fded on an every six-year basis, except as noted, as MILLSTONE requd by tk E.
REGULATORY W ypes oMngs were nd on se au&
CO31PLIANCE Finding 1 -ANSI 3.4 requires vision assessment biennially. Changes in vision that require corrective lenses must be noted on the 396 even in non-licensing years. The documentation provided with the medical charts indicated that the NRC was not notified of an indeterminate number (approximately 10) oflicensed operators who had a change in vision that required corrective lenses in a non-licensing year. For each of these operators, an NRC 396 Form should have been submitted with the appropriate annotation of" corrective lenses required for licensed duties."
One operator's visual acuity did not meet required standards in a non-licensing year. No disqualification or changes in the NRC 396 Form were fded, and the chart contains no documentation regarding assessment of this issue. Once this fmding was brought to the attention of the medical department (April 1997, one month after the exam), the medical department contacted the licensed operator who informed them he had been to an eye specialist for refraction since the time of the exam. His repert vision exam at the Millstone Medical Department revealed adequate visual acuity with corrective lenses, consistent with ANSI 3.4 vision standards. The NRC 396 Form is currently being amended for filing.
Finding 2 -ANSI 3.4 requires that "a history or other indication of any disqualifying condition shall be disqualifying unless adequate supplemental findings demonstrate that no disqualifying condition exists. Such a demonstration shallinclude at least the specific narrative entries by the designated medical examiner and relevant aspects of medical history and examination." In addition, 10CFR55 reinforces this requirement.
It is the opinion of this audit team, based on 10CFR55 and ANSI 3.4, that any potentially disqualifying condition that is adequately compensated should be noted on the NRC 396 Form and adequate demonstration of compensation, including supporting documents from the operator's personal physician, should be attached. The NRC's medical consultant reviews the licensee's medical examiner's opinion and documentation and makes the fmal determination.
Two operators had medical conditions that were potentially disqualifying, but not noted on the NRC 396 Form. It is the opinion of the audit team that both operators had adequately compensated medical conditions and it was unnecessary to place any restriction on their solo operation. The site physician exercised proper medical judgment and adequately documented the reasons for his decisions in the charts. Nonetheless, the NRC 396 Forms should have been filed with the expectation th^< G NRC Medical Consultant would have approved the license application.
Independent Investigation of Operator License Medical Reports April 2,1997 Executive Summary Page 2 of 4 prepared fer Northeast Utilities System by Business Health Managementoccupational Health + Rehabilitation Inc
b l5 5 5 5 5 5 5 t E E E t & & 5 5R FINDINGS (CONTINUED)
Three findings were noted regarding clinical standards of care:
CLINICAL STANDARDS OF Finding 1 -The ANSI 3.4 requires certain exam and laboratory elements biennially. Occasionally, CARE AT documentation for exam or lab elements were missing from a chart. In particular, in 1993 many of MILLSTONE the operators' exams did not include a urinalysis. This problem was corrected in 1994. Although this test is a routine component of biennial exams, all of these operators underwent a urinalysis in 1992 and 1994. Since Millstone performed annual comprehensive examinations on alllicensed operators, a great deal of redundant and overlapping medical information is documented for each operator. In the opinion of the audit team, none of the findings that may have resulted from missing exam components noted from 1993-1997 likely would have impacted an operator's '
performance or resulted in amended NRC 396 findings. A checklist in the form of a spreadsheet or database computer program should be developed to track all physical examination and laboratory elements on a routine basis (annually is recommended) to ensure that all exams and lab work are completed and documented.
Finding 2 -The audit team noted a general problem with documenting the vision component of the exam.
Various forms associated with assessing vision often were unsigned or incomplete. It is recommended that the forms for documenting the visual exam be simplified and contained on one or two pages.
Finding 3 -The audit team discovered several charts in which the American Thoracic Society Standards for spirometry were not met (e.g., failure to provide three reproducible test curves). It is frequently the case that standards may not be met; however, documentation that explains why the standards are not being met must be provided in the chart.
CONNECTICUT The audit team found no issues with NRC 396 documentation or compliance with standards.
YANKEE REGULATORY CONIPLIANCE CLINICAL Several omissions of examination or laboratory elements were noted, but none were considered significant.
STANDARDS OF CARE AT The overall organization and documentation of the Connecticut Yankee charts were excellent.
CONNECTICUT YANKEE Executive Sununary Independent Investigation of Operator Ucense hiedical Reports Apnl 2,1997 prepared for Northeast Utilities System by Business Health hianagernent/ Occupational Heahh + Rehabilitation Inc Page 3 of 4
SUMMARY
Overall, the Medical Clinic provided an excellent standard of compliance with ANSI 3.4 and NRC 396. On two AIILLSTONE occasions, the on-site physician exercised judgment in not submitting a change in NRC 396. Only one operator license was initially in question, based on inadequate visual acuity. The visual acuity exam was repeated after the audit, and the operator met ANSI 3.4 Standards for visual acuity.
The audit team has three recommendations:
- 1. Develop a comprehensive system using a spreadsheet or database computer program to track
. the scheduling oflicensed operator exams,
. whether all exams and laboratory work are completed, and
. the proper illing of the NRC 396 Form, including revisions that occur in non-licensing years.
- 2. Licensed operators undergo medical evaluations only biennially, as recommended by ANSI 3.4
- 3. An internal quality assurance process should be developed to assess compliance with ANSI 3.4,10CFR55, and clinical standards of care on a routine basis (perhaps annually).
Overall, the Medical Clinic provided an excellent standard of compliance with ANSI 3.4 and NRC 396.
CONNECTICUT YANKEE The audit team has two recommendations:
- 1. Develop a comprehensive system using a spreadsheet or database computer program to track
. the scheduling oflicensed operator exams,
. whether all exams and laboratory work are completed, and
. the proper filing of the NRC 396 Form, including revisions that occur in non-licensing years.
- 2. An internal quality assurance process should be developed to assess compliance with ANSI 3.4,10CFR55, and clinical standards of care on a routine basis (perhaps annually).
April 2.1997 Executive Summary Independent lavestigation of Operator License Medical Reports Page 4 of 4 by Business Health Managementoccupational Health + Rehabilitation Inc prepared for Northeast Utilities System
I_S 4 4 O O O D D E & E B D & 5 & O & O O O O & O & O O O 006 CibbUbbU U U O OY ADDENDUM A: AUDITTEAM PERSONNEL Ben Hoffman, M.D., M.P.H., Project Director Steve Schmitz, M.D., M.P.H.
Tom Clayton, PA/C Wayne Estes, PA/C Jan Schwartz, OHN i Richard Scacheri I
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ADDENDUM C: ALL FINDINGS (See tollowing pages.)
Notes:
Explanation of missing exam data levels:
. MISSING EXAM DATA FOR 396 YEAR means that data is missing for an exam performed to file for the NRC 396 license.
. MISSING EXAM DATA BIENNIAL YEAR means that data is missing for an exam performed to conform with the ANSI 3.4 Standard.
. MISSING EXAM DATA means that data is missing from an exam performed during any year other than a 396 or biennial year.
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