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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: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 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 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) 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 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 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 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 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) 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 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 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 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 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 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 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 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 B17801, Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept1999-06-30030 June 1999 Forwards 10CFR50.59 Annual Rept for Period Jan-Dec 1998. Various Changes That Were Initiated in Previous Yrs & Completed in 1998,also Incorporated Into Annual Rept B17819, Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in1999-06-30030 June 1999 Forwards Rev 17 to FSAR & Addendum 6 to Annual Rept.Nneco Recently Completed Review of Unit 2 Design & Licensing Bases Which Resulted in Changes to FSAR Provided in Encl 1.Encl 2 Includes Info Covering Changes Not Included in B17780, Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics1999-06-30030 June 1999 Forwards Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) TR, IAW 10CFR50.54(a)(3).Changes to TR Are Shown as Text in Bold Italics B17723, Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl1999-06-29029 June 1999 Responds to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for Units 2 & 3 Encl.Without Encl B17767, Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr1999-06-29029 June 1999 Forwards Rev 12 to FSAR & Addendum 3 to Annual Rept, for Millstone Unit 3,per 10CFR50.71(e) & 10CFR50.4(b)(6). No New Regulatory Commitments Contained in Ltr 1999-09-03
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" 107 Selden Street, Berlin, CT 06037 ggg Utilities System .wtheot utaitie, se,*e coing.ny P.o Box 270 Ilartford, CT 06141-0270 (203) 665-5000 September 21, 1995 Docket No. 50-336 B15372 Re: IR 50-336/95-21 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Reply to a Request for Submittal of Plans and Schedule for Emergency Operating Procedures Upgrade Program Insoection Reoort 50-336/95-21 In a letter dated August 10, 1995,(" the NRC Staff transmitted the results of a safety inspection of the Millstone Unit No. 2 revised Emergency Operating Procedures (EOPs) and the ability of the control room operators to use them to safely operate the unit.
During the EOP inspection, Northcast Nuclear Energy Company (NNECO) noted that a second revision of the EOP Upgrade Program is planned to address human factors and other concerns. Subsequently, in the report dated August 10, 1995, the Staff requested that we submit a listing of those additional items which Millstone Unit No. 2 plans to address in the continuing EOP upgrade program, along with an estimated timetable for completion. Attachment 1 to this letter provides the EOP Upgrade Program Plan Summary, Attachment 2 provides the Program Task Summary and Attachment 3 provides the Program Timeline.
The following NNECO commitment is made within the attachments to this letter. Other statements within this letter and the attachments are provided as information only. ,
B15372-1 The upgraded EOPs are scheduled to be implemented by July 1, 1997.
e (1) G. W. Meyer letter to J. F. Opeka, " Millstone, Unit 2, EOP Inspection - Report No. 50-336/95-21," dated August 10, 1995.
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'U.S.-Nuclear: Regulatory Commission B15372/Page: 2 September 21, 1995
'.If there are any questions regarding the information'provided in this. submittal, please contact Mr. Philip J._Lutzi at (203) 440-2072.-
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: -J . F. Opeka Executive Vice President BY: m E. A. DeBarba Vice President Attachments cc: T. T. Martin, Region I Administrator G. S.-Vissing, NRC Project Manager, Millstone Unit No. 2 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3
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l Docket No. 50-336
- B15372 J
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Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Reply to a Request for Submittal of Plans and Schedule for Emergency Operating Procedures Upgrade Program Program Plan Summary l
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September 1995
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1995 - 1997 EOP UPGRADE PROGRAM PLAN
SUMMARY
I. FORMATION AND TRAINING OF THE EOP UPGRADE TEAM EOP Unorade Team Formation The-Emergency Operations Procedure (EOP) upgrade team will consist of program administrator (s), EOP writers, and support department '
points of contact. In addition, the team will enlist the aid of other independent organizations (e.g., technical reviewers, human
' factors reviewers, peer reviewers, etc.) as appropriate.
EOP Uoorade Team Trainino The EOP writers and support department-points of contact will be requested to attend . training on the Combustion Engineering Emergency Procedures Guidelines (CEN-152). This will ensure that
.the entire. team starts out with the same basic understanding of CEN-152. _The support department supervisors and managers will also be invited to attend.
The EOP writers will also be required to attend training on the Unit 2 EOP Upgrade Writer.'s Guide. All other EOP upgrade team members will be invited to attend this training.
II. EOP ADMINISTRATIVE CONTROLS NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures", recommends an EOP development and verification and validation (V&V) process which will result in technically accurate and usable EOPs. The V&V process is addressed by this program
-plan. The following administrative control procedures will be specifically designed for the Millstone Unit No. 2 EOP Upgrade Program:
MP2 EOP Upgrade Writer's Guide (OP-2259-U)
MP2 EOP Upgrade User's Guide (OP-22 60-U)
MP2 EOP Upgrade Program Administration (OP-2261-U)
MP2 EOP Upgrade Verification Program (OP-2262-U)
MP2 EOP Upgrade -
Validation Program (OP-2263-U)
MP2 EOP Upgrade Procedures Generation Package OP 2259-U. "MP2 EOP Uoorade Writer's Guide" - This document will provide the guidance for the' composition, layout, formatting and writing style used in.the EOPs. It will also provide a listing of approved. verbs, with their meanings defined for EOP purposes, along with acronyms and system names which may be used within the EOPs.
OP 2260-U. "MP2 - EOP Uoorade User's Guide" - This document will provide guidance to the operator for'EOP usage, and will delineate the responsibilities of the EOP users. This document will reflect the method by which the upgraded EOPs are intended to be used.
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l OP 2261-U. "MP2 EOP Uoorade Procram Administration" - This document
- will. describe the' specific process used to upgrade the Millstone Unit No. 2 EOPs.and their supporting documentation ~. It will be.the core procedure for establishing the structure of the EOP program. ,
OP-2262-U. "MP2 EOP Ucarade Verification Procram" - This document will describe the program used to verify that the EOPs are technically correct, that there is consistency between the EOPs and the plant hardware, and that the EOPs adhere to the-guidance in OP 2259-U.
OP-2263-U. "MP2 EOP Uoorade Validation Procram" - This document will describe the process used to ensure that each EOP is usable, that the language is appropriate for the personnel using the EOP, and that the procedure functions as intended.
MP2 EOP Unarade Procedures Generation Packace - NUREG-0899 requires that each licensee submit a procedures generation package (PGP) to the NRC staff at least three months prior to initial operator
' training on new or upgraded EOPs. This document will describe the way in which the plant's EOPs are developed and implemented. r III. INITIAL EOP. DEVELOPMENT AND DEVELOPMENTAL VERIFICATION CEN-152' Mark-Uo The first step in the EOP Upgrade process will determine the degree to which the CEN-152 mitigative strategies can be implemented at Millstone Unit No. 2. A copy of CEN-152 will be entered into Microsoft Word format, and will contain appropriate Millstone Unit No. 2 plant-specific setpoints and system characteristics. It will serve as a mark-up of CEN-152. This " mark-up" will be specified as draft 1.0, and will contain both the procedure title and the EOP number.
4 After the mark-up of each EOP has been completed, it will be ;
t exercised on the Millstone Unit No. 2 simulator to determine if any I step, strategy, or flow path changes are necessary to accommodate l Millstone Unit No. 2 plant specific differences. If any modifications to the steps, mitigative strategy, or flow of CEN-152 are determined to be necessary, this will be documented, along with an explanation of the reasons the modification is necessary.
Develoo Plant-Soecific Guidelines
- After each of the CEN-152 mark-ups has been exercised, the plant-specific EOP guidelines will be developed. These guidelines will be based on the simulator runs of the marked-up CEN-152 procedures and the current EOPs. These guidelines will be developed in procedure format similar to CEN-152, and will be specified as draft ,
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Develcomental EOP Draft Once the plant-specific guidelines have been developed, an initial developmental draft of each of the EOPs will be produced. This draft will be specified as draf t 3.0. It will be based on the plant-specific guidelines and the current EOP steps, and will be written to comply with the Unit 2 EOP Writer's Guide.
Standard Accendices Instead of using support procedures within the EOP space, in most
-cases, Millstone Unit No. 2 will excerpt the appropriate information from the support procedures and assemble an appendix which will be customized for EOP use. These " standard appendices" will' be draf ted during the development 'of the EOP (s) .
Develcomental Verification This developmental verification process consists of two major tasks called " Developmental Verification Walkdown," and " Developmental Simulator Verification."
Developmental ~ Verification Walkdown The purpose of the developmental verification walkdown is to verify, by mock performance, that local plant operations can be successfully performed as written in the standard appendices and any EOP support procedures. In addition, this task provides an estimate of the time required to perform the local operations necessary to support the EOPs. This is necessary to provide input to the developmental simulator verification process, such that the estimated time to complete each supporting local operation can be accounted for during the exercising of the EOPs.
Developmental Simulator Verification Developmental simulator verification will be used to ensure )
that each developmental EOP draft provides adequate mitigative strategies for each event, and that the plant specific steps are accurate and can be performed as presented. A draft of each EOP, specified as draft 4.0, will be prepared from the results of the previous developmental tasks. Each of these drafts will then be brought to the Millstone Unit No. 2 simulator for a developmental simulator verification.
IV. EOP VERIFICATION Once the developmental verification is complete, a draft of each EOP- will be produced accounting for developmental verification findings. This draft will be specified as draft 5.0.
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, 1 Each! of the; procedure drafts _ will undergo a formal verification I
~' process in~.accordance with OP 2262-U. EOP verification will be (
accomplished-through a series of reviews as follows:
multi-discipline review human' factors review
. label consistency review ,
technical review !
Multi-Discioline Review A multi-discipline review (MDR) will be performed on each of the EOPs. This multi-discipline approach is taken to allow the various '
specialty skills of the participants to be utilized in the review of.the EOPs. The MDR will be performed using personnel from.the following organizations:
licensing independent safety engineering group operations engineering safety analysis .
t training Human Factors Review A human factors review of each EOP will be performed to ensure that the EOP conforms to the requirements of the Millstone Unit No. 2 EOP Upgrade Writer's Guide. -This review will also consist of a check that, nomenclature, grammar, structure and style are .
consistent throughout the EOPs.
Label Consistency Review The details regarding label consistency review is provided in section VI.
Technical Review A techn.' review will be performed to verify the technical adequacy the EOPs, and the correspondence between the upgraded EOPs and LEN-152.
V. EOP SUPPORT DOCUMENTATION DEVELOPMENT EOP Technical Basis Documents
'A Technical Basis Document will be developed for each EOP and will explain the reasons for each EOP step, lists the reference ;
- documents used~to support'the basis, and lists any NRC commitment being fulfilled by the step. It is intended to be used as -
reference for training on the EOPs prior to their implementation, i and asia reference for future EOP revisions.
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Steo Deviation Documents Step: Deviation Document will be developed for each EOP that compares each step of the EOP to the CEN-152 steps. In accordance j with NUREG-0800, NUREG-0899, NUREG-1358, and NUREG-1358 Supplement 1, 'all safety significant deviations will be identified and justified.
Trainina Excectations Documents i A Training Expectations Document will be developed for each EOP i that describes how the operations department expects the training t
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_ department to train the operators on the implementation of each EOP. The purpose of this' document will be to describe the unique expectations that will be associated with certain steps.
Therefore, not all steps will have an associated training expectation.
Safety Evaluations The NNECO Safety Analysis Branch will perform an Integrated Safety Evaluation on the EOPs in accordance with department procedures.
EOP Setooint Document This document will provide a basis for all plant specific numerical values listed in the EOPs, including reference to the appropriate supporting calculations. This EOP Setpoint Document will contain values which account for both harsh containment, and non-harsh containment instrument uncertainties in accordance with CE-NPSD-925, and the report which will be generated as a product of current Combustion Engineering Owners Group Task 884.
, VI. CONTROL ROOM AND LOCAL OPERATIONS LABEL PROGRAM
, In conjunction with the development of the upgraded EOPs, the control room labels and the labels on local equipment associated with local EOP operations will be evaluated for clarity, display attributes, conformance to " normal" plant nomenclature, location, and completeness. A human factors expert, a licensed or previously i
licensed operator, and a member of the EOP upgrade development team as a minimum, will comprise the labeling design, evaluation, and
- verification team.
. VII. SPDS UPGRADE i
In conjunction with the development of the upgraded EOPs, the Safety Parameter Display System (SPDS) monitoring and display software will be modified. This modification will be performed by the SPDS computer group working with technical support engineering,
'and the EOP team. This development will commence once the final I EOP verification drafts have been produced and will continue through the end of the program. l j
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. j VIII.- EOP VALIDATION Simulator Val'idation Once the verification process has been completed as specified in section IV-of this Program Plan, each EOP will ~ be validated in accordance'with OP 2263-U. The validation process will commence with the' development of_a draft EOP incorporating all documented
. verification concerns. This draft will be designated as draft 6.0. .
NRC Review NNECO personnel will continue to maintain communication, regarding the' progress of the EOP Upgrade Program, with the NRC through the Region I, Operations Branch. In the course of this communication the Staff has been invited to review the progress of the EOP Upgrade Program at any time. However, we - believe the Staff's review during the simulator validation phase would be beneficial in our. assessment of the initial products of the EOP Upgrade Program.
IX. EOP TBAINING MP2 EOP Trainers Prior to the commencement of operator training on the EOPs, the EOP development team will provide to the training department with (approximately two weeks of) " Upgraded EOP Indoctrination" presentations on the new EOPs. These presentations will take the form of classroom seminars, and simulator sessions, and will allow the EOP Development Team to familiarize the trainers with the upgraded EOPs, and the reasoning behind the EOP strategies.
Millstone Unit No. 2 operators will be trained on the upgraded EOPs following completion of the validation phase of the development program, and the upgraded EOP indoctrination training of the trainers. A draft, designated as draft 7.0, will be produced incorporating all validation and upgraded EOP indoctrination session findings. This draft will be used during the operator training phase of the project. Each crew will be trained on the new EOPs prior r.o their implementation. Comments, concerns and suggestions will be solicited from the operators and will be evaluated and addressed.
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. PROCEDURE FINALIZATION AND APPROVAL Final ~ Reviews A ~. final' ' human factors review of the EOPS will be conducted
- following completion of the EOP validation. This review will be performed using' draft 7 of the: upgraded EOPs. The purpose of this review will be to evaluate how well the earlier comments from the reviews were understood, incorporated and resolved, and to ensure &
that 'the EOPs meet all of the requirements of the EOP Upgrade Writer's~ Guide.
> A final technical review will be conducted following completion of 4 the EOP validation. This review will be performed using Draft 7 of the upgraded ~EOPs. The purpose of this review will be to evaluate-how well the earlier comments from the Technical reviews were '
understood, incorporated and resolved.
1 EOP Finalization Once- the final human factors and technical reviews have been completed, a final draft of the EOPs will be prepared. This draft
- will be designated as draft 8.0. The EOP development team will incorporate the comments from the final human factors review and technical review, and will perform a final consistency check to ensure that the steps are presented consistently throughout the
. EOPs, and that the EOP standard appendices are consistent as appropriate.
PORC Review. Unit Director's Acoroval and Imolementation Each EOP will be reviewed by the Plant Operations Review Committee (PORC) in accordance with Station Procedure OA-3. All comments and concerns will be resolved as appropriate. Following this PORC review and approval, the new EOPs will be presented to the Unit Director for approval prior to implementation.
XI. EOP UPGRADE PROGRAM SCHEDULE I' The EOP upgrade program commenced in August, 1995 and will take approximately two years to complete. It is anticipated that the
- 2. new EOPs will be implemented by July 1, 1997.
XII. EOP UPGRADE PROGRAM RECORD CONTROL All EOP upgrade program supporting documentation will be kept in
- thefEOP upgrade program project-file, by Millstone Unit No. 2 EOP team members. The documentation.will be separated by the EOP it supports, to the extent possible, and will be available for audit purposes. .
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' B15372 Attachment 2 Millstone Nuclear Power Station, Unit No. 2 Reply to a Request for Submittal of Plans and Schedule for Emergency Operating Procedures Upgrade Program Program Task Summary September 1995 l
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-EOP Unorade Procram Task Su==arv
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. 1. - Assemble EOP Upgrade Team
- 2. Train EOP Upgrade _ Team
- 3. Develop EOP Upgrade Administrative Controls
- MP2 EOP Upgrade Writer's Guide (OP-2259-0).
- MP2 EOP Upgrade User's Guide (OP-22 60-U)
MP2 EOP Upgrade Program Administration '(OP-2261-U)
' - ICP;2 EOP Upgrade Verification Program (OP-2262-U)
- MP2 EOP Upgrade Validation Program (OP-2263-U)
MP2_EOP Upgrade Procedures Generation Package
- 4. Develop CEN-152 Mark-up
_ Develop CEN-152 Mark-up
- Exercise CEN-152 Mark-up on the MP2 Simulator
- 5. Develop Plant-Specific Guidelines
- 6. Develop Initial EOP Drafts Develop Standard Appendices
- Perform Developmental Verification Walkdown Perform Developmental Simulator Verification
- 7. Perform Full EOP Verification Multi-Discipline Review Human Factors Review Label Consistency Review Technical Review .
- 8. Develop EOP Support Documentation EOP Technical Basis Documents Step Deviation Documents Training Expectations Documents Safety Evaluations EOP Setpoint Document p
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- 19. . ; Implement! Control Room and:LocaliOperationsiLabel(Program'
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10.;: Perform SPDS Upgrade-i
- 11. . Validate EOPs: ,
Simulator validations- ~
NRC-review Conduct'EOP! Training
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Indoctrinate MP2 EOP Trainers on the Upgraded EOPs ,
- Train-the MP2 Operators on the Upgraded EOPs
- 13. . Final'izefand: Approve EOPs
' Final HumaniFactors' review'and' Technical review
,.- -- EOP Finalization PORC- Review,' Unit Director!s Approval and-Implementation 1
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- Docket No. 50-336
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Attachment 3 Millstone Nuclear Power Station, Unit No. 2 Reply to a Request for Submittal of Plans and Schedule for Emergency Operating Procedures Upgrade Program Program Timeline September 1995
. . . _ . - _ . - - - .- ~. . . - .. _..__. _.- - . -_ -.
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. 1995 1996 1997 ID Task Nam.) Otr 2 l Otr 3 l Otr 4 Otr 1 l Otr 2 l Otr 3 l Otr4 Otr 1 l Otr 2 l Otr 3 l Otr4 1, , , Assembl3 EOP Upgrade Tocm 7/3 l 9/18 l 5
\
) 6 Train EOP Team 4
7/9 PS 10/6 l 11 4
12 Develop EOP Admin. Procedures 7,3 g i
40 1
- 41 Develop CEN 152 Mark-Up 8/11 M 10/31 49 i
50 Develop Plant-Specific Guidelines 10/2 i M 12/19 54 55 Develop initial Drafts 1 I/28 5/10 65 66 Develop Deviation Documents y 6/18 l 3/1 y )
76 l 1
77 Develop Technical Basis Documents 6/17 3/15 y y 89 90 Develop Training Expectations y 6/17 3/15 y 100 101 Develop EOP Setpoing Document y 5/21 3/15 y
, 112
- 113 Verification !3/20 2/15 126 2
127 Validation 4/5 12/4 i 135 136 EOP Training 3/26 8/8 I !
4 146 i (
l i 147 Finalization and Approvals 12/9 6/23 i
- 161 i l !
162 Perform Label Upgrade 10/2 I 8/9 169 170 Determine EOP instrument Uncertainties 11,1 10/18
- 178 f
179 Support Departments Technical Assistance 1 l/28 y . , y 2/10 I l '
182 ;
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j 183 Upgrade SPDS ! 5/7 y y 6/23 i
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198 EOP Implementation 7/157/1