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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 Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements B17901, Submits Statement of Personal Qualification (NRC Form 398)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:OUTGOING CORRESPONDENCE
MONTHYEARDD-99-12, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 9910281999-10-28028 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review DD-99-12 Has Expired.With Certificate of Svc.Served on 991028 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 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 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 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 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 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 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 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 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 ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212J6621999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Units 2 & 3 on 990916.Identified Several Recent Instances in Which Condition Repts Were Not Initiated,Resulting in Untimely or Inadequate C/As.Historical Listing of Plant Issues Encl 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 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 ML20216J1341999-09-28028 September 1999 Ltr Contract:Task Order 49, Millstone Units 2 & 3 Employee Concerns Program Insp, Under Contract NRC-03-98-021 ML20212F4961999-09-20020 September 1999 Forwards Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 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 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 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 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 ML20211K5171999-09-0202 September 1999 Expresses Appreciation for Support Provided for NRC Public Meeting on 990825 ML20211H0741999-08-30030 August 1999 Discusses GL 92-01,Rev 1, Rv Structural Integrity, Issued by NRC on 950519 & NNECO Responses for Millstone Unit 2 & 980715.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 Based on Response Review ML20211H9971999-08-27027 August 1999 Forwards Insp Rept 50-423/99-07 on 990614-0715.Violations of NRC Requirements Occurred Re Adequacy of C/As for Organizational Changes & Being Treated as NCVs DD-99-09, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 9908261999-08-26026 August 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-09) Expired.Commission Declined Any Review & Decision Became Final on 990823.With Certificate of Svc.Served on 990826 ML20211F5841999-08-23023 August 1999 Discusses Proposed Rev 21 to Northeast Utils Quality Assurance Program TR for NRC Review & Approval,Iaw 10CFR50.54 ML20211D5701999-08-20020 August 1999 Informs That in May 1999,Northeast Nuclear Energy Co, Restarted Millstone Nuclear Power Station,Unit 2.Licensee Has Been Tasked Charter with Listed Specific Responsibilities ML20211E8051999-08-20020 August 1999 Forwards Insp Rept 50-213/99-02 on 990420-0719.No Violations Noted.Completion of Corrective Actions for Spent Fuel Bldg Ventilation Issues Adequate ML20211C4621999-08-18018 August 1999 Discusses Rev to TS Bases Sections 3/4.5.2 & 3/4.5.3, Emergency Core Cooling Sys Subsystems ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210N4921999-08-0909 August 1999 Ack Receipt of 990331 Electronic Transfer of $88,000 for Civil Penalty,Proposed on 990309.Corrective Actions Will Be Examined During Future Insp ML20210J6021999-08-0202 August 1999 Informs That Info Re Orise Technical Survey Assistance to NRC at CT Yankee Is to Include Copies of Listed Documents ML20210C0751999-07-21021 July 1999 Forwards 990721 Notice of Public Meeting Re post-shutdown Decommissioning Activities Rept ML20210A9681999-07-14014 July 1999 Responds to Re Changes to Millstone Physical Security Plan Identified as Rev 32,submitted Per Provisions of 10CFR50.54(p).No NRC Approval Is Required,Based on Util Determination That Revs Do Not Decrease Plan Effectiveness ML20209E7341999-07-12012 July 1999 Discusses Util Responses to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. Responses Acceptable.Info Revised in Reactor Vessel Integrity Database (Rvid) & Is Releasing as Rvid Version 2 ML20209G2921999-07-0909 July 1999 Forwards Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210C1491999-07-0101 July 1999 Responds to ,Which Responded to NRC Ltr & NOV & Informs That Engagement in Any Similar Wrongdoing in Future May Result in More Significant Enforcement Action. No Further Action Will Be Taken at This Time DD-96-23, Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 9508211999-07-0101 July 1999 Informs That on 961226,NRC Issued Partial Director'S Decision DD-96-23,in Response to Petition Submitted,Per 10CFR2.206,on 950821 ML20196J2111999-06-30030 June 1999 Forwards SE Concluding Licensee USI A-46 Implementation Program Meets Purpose & Intent of Criteria in Generic Implementation Procedure for Seismic Verification of NPP Equipment, Rev 2 ML20196J5031999-06-30030 June 1999 Responds to 990414 Petition,Submitted Per 10CFR2.206 to Nrc. NRC Solicited Support from FEMA to Ensure That Appropriate Response to Enhancements Identified to Offsite EP in Event of Radiological Emergency at Millstone,Developed ML20196J1131999-06-29029 June 1999 Forwards Notice of Receipt & Availability for Comment of Post-Shutdown Decommissioning Activities Rept, Re .Notice Provided for Public Comments to Be Submitted within 30 Days of Notice Date ML20196G9531999-06-24024 June 1999 Discusses Changes Provided by NNECO on 990504 to TS Bases Sections 3/4.7.7 & 3/4.7.8.Returns TS Bases to NNECO to Be Inserted in TS to Ensure That NRC Staff & NNECO Have Identical TS Bases Pages ML20212H9661999-06-21021 June 1999 Confirms 990611 & 14 Telcons with M Selden,In Which Beckman & Assocs,Inc Was Advised to Stop Work Under Mod 4 to Task Order 005,under Contract NRC-03-98-021 ML20212J0751999-06-15015 June 1999 Forwards Notice of Withdrawal of Amend Request for Allowed Outage Time Extensions for Emergency Diesel Generators & Low Pressure Safety Injection Trains of Emergency Core Cooling Sys ML20212H6661999-06-15015 June 1999 Forwards RAI Re 990315 Application Request for Approval of Proposed Indirect Transfer of Seabrook Station,Unit 1 License & Proposed Indirect Transfer of Millstone,Unit 3 License to Extent Held by Nepco 1999-09-30
[Table view] |
Text
t UNITED STATES g ) j NUCLEAR RE'JULATORY C3MMISSION l
. % t CASHIN2TCN, O.C. 20555 4001
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July 21, 1997 g - m /jqd s / W 3 1
Deborah Katz, President l Citizens Awareness Network l P.O. Box 83 l Shelburne Falls, MA 03170 Paul Gunter, Reactor Watchdog Project l Nuclear Information and Resource Service l 1424 16th Street, NW., 4th Floor Washington, DC 20036 l
Dear Ms. Katz and Mr. Gunter:
1 1
The surpose of this letter is to provide an update on the 2.206 Petition that l you 1 ave submitted. The initial update was provided by letter dated April 10, 1997. The Petition was filed pursuant to Title 10 of the Code of Federal Reaulations (10 CFR) Section 2.206 on November 25, 1996, and amended on December 23, 1996. The Petition requested that the U.S. Nuclear Regulatory Commission (NRC) take actions regarding the nuclear facilities that Northeast ;
Utilities (NU or Licensee) operates in Connecticut. l The Petition was submitted by you on behalf o.f the Citizens Awareness Network ,
(CAN) and the Nuclear Information and Resource Service (NIRS) (Petitioners).
In your December 23, 1996, amendment to the Petition, you requested that the NRC provide copies of calculations to the Petitioners that were referred to by the Licensee at the November 1996, enforcement conference. The calculations were performed by the Licensee to determine the reactor vessel water level as the result of nitrogen inadvertently entering the reactor coolant system.
Actually, the presentation you refer to was a public predecisional enforcement conference held on Decmber 4,1996, at the Hillstone training building in Waterford, Connecticut. Ms. Katz confirmed, during a telephone conversation on July 17, 1997, that the calculations requested were the ones referred to by !
the Licensee at the December 4, 1996, cor.ference.
By letter dated July 3,1997, the Licensee provided information, including the requested calculations, relating to the different methods used for determining the reactor vessel water level resulting from the nitrogen intrusion event.
This information has been placed in the NRC's Public Document Room and the ,
Local Public Document Ronm. l We are providing the enclosed calculations to you as a courtesy since the calculations are relevent to your concern, are not proprietary, and are in the public domain.
C
'00043 i DFO\ i I NBC FRE CEMER W 9707280172 970721 PDR ADOCK 05000213 G PDR _
t Deborah Katz and Paul Gunter We are continuing our review of your Petition and expect to issue a Director's Decisi on shortly.
If you have any questions,-please contact me at (301) 415-1408. ;
Sincerely, -
n
.. 0..JA 04%
Daniel G. Mcdonald Jr., Senior Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enc 1: Rosemary Bassilakis, Researcher Citizens Awareness Network 54 Old Turnpike Road Haddam, Connecticut 06438 t
r
Deborah Katz and Paul Gunter -2 July 21, 1997 We are continuing our review of your Petition and expect to issue a Director's Decision shortly.
If you have any questions, please contact me at (301) 415-1408.
Sincerely, Original signed by:
Daniel G. Mcdonald Jr., Senior Project ~ Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-245, 50-336, 50-423 and 50-213
Enclosure:
As stated cc w/ encl: Rosemary Bassilakis, Researcher Citizens Awareness Network 54 Old Turnpike Road Haddam, Connecticut 06438 DISTRIBUTION:
Docket File" PUBLIC SP0-L Reading SP0 Reading WTravers PMcKee LBerry DMcDonald SDembek JAndersen MFairtile EHylton OCA RHoefling, OGC Licensee and Service List .
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DATE 07/ Y7/97N'7' 07/n/97 \ 07/ 2[/97 07/4V97 07/ /97 0FFICIAL RECORD COPY
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Northeast Nuclear Energy Company Millstone Nuclear Power Station Units 1, 2, and 3 cc:
Lillian M. Cuoco, Esquire Mr. Wayne D. Lanning Senior Nuclear Counsel Deputy Director of Inspections Northeast Utilities Service Company Special Projects 0ffice P. O. Box 270 475 Allendale Road Hartford, CT 06141-0270 King of Prussia, PA 19406-1415 Mr. Kevin T. A. McCarthy, Director Mr. F. C. Rothen Monitoring and Radiation Division Vice President - Work Services Department of Environmental Northeast Nuclear Energy Company Protection . P.O. Box-128 79 Elm Street Waterford, CT 06385 Hartford, CT 06106-5127 Charles Brinkman, Manager Mr. Allan Johanson, Assistant Washington Nuclear Operations j Director .
ABB Combustion Engineering <
Office of Policy and Management 12300 Twinbrook Pkwy, Suite 330 i Policy Development and Planning Rockville, MD 20852 Division 450 Capitol Avenue - MS 52ERN Mr. D.-M. Goebel P. O. Box 341441. Vice President - Nuclear Oversight l Hartford, CT 06134-1441 Northeast Nuclear Energy Company l P. O. Box 128 Regional Administrator, Region I Waterford, CT 06385 U.S.~ Nuclear Regulatory Commission 475 Allendale Road Mr. M. L. Bowling, Jr.
King of Prussia, PA 19406 Recovery Officer - Millstone Unit 2 Northeast Nuclear Energy Company First Selectmen P. O. Box 128 Town of Waterford Waterford, CT 06385 Hall of Records 200 Boston Post Road Senior Resident Inspector Waterford, CT 06385 Millstone Nuclear Power Station c/o U.S. Nuclear Regulatory Commission i
- Mr. J. P. McElwain P. O. Box 513 Recovery Officer - Millstone Unit 1 Nia:.ic, CT 06357
, Northeast Nuclear Energy Company P. O. Box 128 Mr. J. K. Thayer Waterford, CT 06385 Recovery Officer - Nuclear Engineering and Support Neil S. Carns Northeast Nuclear Energy Company Senior Vice President P. O. Box 128 and Chief Nucleaar Officer Waterford, CT 06385 NortNeast Nuclear Energy Company
, c/o Ms.. Patricia A. Loftus Director - Nuclear Licensing Services P.O. Box 128 Waterford, CT 06385
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4 Northeast Nuclear Energy Company Millstone Nutlear Power Station Units 1, 2, and 3 cc:
Mr. M. H. Brothers Little Harbor Consultants, Inc.
Vice President - Millstone Unit 3 Millstone - ITPOP Project Office Northeast Nuclear Energy Company P. O. Box 0630 P. O. Box 128 Niantic, Connecticut 06375-0630 Waterford, CT 06385 Mr. Evan W. Woollacott Mr. M. R. Scully, Executive Director Co-Chair Connecticut Municipal Electric Nuclear Energy Advisory Council Energy Cooperative 128 Terry's Plain Road 30 Stott Avenue Simsbury, Connecticut 06070 Norwich, CT 06360 Mr. Daniel L. Curry Mr. William D. Meinert Project Director l Nuclear Engineer .
Parsons Power Group, Inc. l Massachusetts Municipal Wholesale 2675 Morgantown Road Electric Company Reading, Pennsylvania 19607 P. O. Box 426 j Ludlow, MA 01056 Mr. Don Schopfer i Verification Team Manager Ernest C. Hadley, Esq. Sargent & Lundy 1040 B Main Street 55 E. Monroe Street P. 0. Box 549 Chicago, Ilinois 60603 West Wart. ham, MA 02576 Joseph R. Egan, Esq.
Egan & Associates, P.C.
2300 N Street, NW Washington, D.C. 20037 Citizens Regulatory Commission ATTN: Ms. Susan Perry Luxton 180 Great Neck Road Waterford, Connecticut 06385 4 The Honorable Terry Concannon Co-Chair -
Nuclear Energy Advisory Council Room 4035 Legislative Office Building
. Capitol Avenue Hartford, Connecticut 06106
Northeast Utilities Service Company Haddam Neck Plant Docket No. 50-213 cc:
Lillian M. Cuoco, Esq. Resident Inspector Senior Nuclear Counsel Haddam Neck Plant Northeast Utilities Service Company c/o U.S. Nuclear Regulatory Commission P. O. Box 270 361 Injun Hollow Road Hartford, CT 06141-0270 East Hampton, CT 06424-3099 Mr. Kevin T. A. McCarthy, Director Mr. James S. Robinson Monitoring and Radiation Division Manager, Nuclear Investments and Department of Environmental Administration Protection New England Power Company 79 Elm Street 25 Research Drive Hartford, CT 06106-5127 Westborough, MA 01582 Mr. Allan Johanson Mr. G. P. van Noordennen Assistant Director Manager - Nuclear Licensing Office of Policy and Management Northeast Utilities Service Company Policy Development and Planning 362 Injun Hollow Road Division East Hampton, CT 06424-3099 450 Capitol Avenue-MS#52ENR P. O. Box 341441 Hartford, CT 06134-1441
. Mr. F. C. Rothen Vice President - Work Services Northeast Utilities Service Company I
, P. O. Box 128 i Waterford, CT 06385 Mr. D. M. Goebel I
, Vice President - Nuclear Oversight L Northeast Utilities Service Company .
P. O. Box 128 j Waterford, CT 06385 <
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Mr. J. K. Thayer Recovery Officer, Nuclear Engineering and Support Northeast Utilities Service Company P. O. Box 128 Waterford, CT 06385 4
Regional Administrator
. Regioitl
- i. U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
! Board of Selectmen .
Town Office Building Haddam, CT 06438 f
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Docket No. 50-213 .
!- CY-97-041 : ,
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'Haddam Neck Plant j
- Additi onalInformati on For The Nitrogen Intrusion Event Analysis Of The Nitrogen Intrusion Event
. Utilizing RELAPS/ MOD 3 l
- July 1997 1 g ' i )
Enclosure
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U. S. Nucinr Regul: tory Commission
. CY-97-041/ Attachment 3/Page 1 .
Analysis Of The Nitrogen Intrusion Event Utilizing RELAPS/ MOD 3 The inadvertent nitrogen intrusion vent was simulated with the RELAPS/ MOD 3 code in November 1996 to determine the maximum accumulation of nitrogen in the vessel and
'to calculate the resultant displacement of the vessel inventory from the reactor vessel 1 into the pressurizer. Given the rate of the nitrogen inflow to the primary side and the >
vent line resistance to nitrogen outflow from the pressurizer and the reactor, it is q possible to calculate with a system code the minimum level at which the two flows l balance.
The RELAPS/ MOD 3 model of the Haddam Neck Plant (HNP) included the detailed vessel representation, the pressurizer and part of the hot leg. The Icops were not represented since they were isolated during the event. The relative elevations among i the regions have been preserved in the model. The top of the vessel and the pressurizer were connected to a common vent header which provided the release path ,
for the nitrogen and served as the pressure boundary for the system. )
l Nitrogen injection was simulated by a separate junction connected to the top of the downcomer. The junction was supplied by a time-dependent volume representing the i
nitrogen supply tank. The downcomer communicated with the upper head through a small flow path which normally allows some cooling flow into the upper head during power operations. The fuel assemblies in the core were modeled as part of the overall I vessel flow resistance, but the actual decay heat was not simulated. The head vent pipe sizes were based on the 0.5 inch diameter Schedule 80 pipe for the reactor vessel vent, and on 0.75 inch Schedule 80 for the pressurizer vent.
A list of additional parameters is found in Table 1. The noding diagram of the HNP REl.APS/ MOD 3 modelis shown in Figure 1.
RELAP Simulation The simulation was performed in two steps. In the first part, the goal was to achieve a steady-state condition inside the vessel for a given nitrogen injection flow rate. The steady state is defined as the condition characterized by a stable water level inside the vessel, balanced by a column of water inside the pressurizer. Once the levels were stable, the next step was to isolate the N 2. injection and refill the vessel in several steps to match the operator actions over the period of three hours.
U. S. Nucirr R:gulatory Commission CY-97-041/ Attachment 3/Page 2 Before starting the nitrogen injection in the analysis, the initial water levels in the vessel and the pressurizer were allowed to come to a hydrostatic equilibrium with the head vent lines open. With the vessel full, the pressurizer registered the equilibrium levet just above the lower level tap. Once the balance was achieved, the nitrogen injection was initiated into the downcomer. The gas began to flow into the upper head and collected at the highest point, displacing the water from the vessel into the pressurizer. As the level in the pressurizer increased on the way to a new hydrostatic balance, a controller was activated in the code to maintain the level 160 inches above the hot leg by draining off some of the inventory. The code kept track of the discharge volume by integrating the discharged volume. The data shows that the operators drained some 5,000 to 6,000 gallons from the primary side as the level increased in the pressurizer.
In summary, the simulation was tuned to two basic assumptions:
- That the steady-state pressurizer level with nitrogen injection is at 345 inches on the level taps and that the tolerance associated with this readi! g is negligible, and e That the volume of water discharged from the Reactor Coolant System (RCS) is between 5,000 and 6,000 gallons when the steady-state pressurizer level of 345 inches is reached.
The unknown factors in the analysis are:
- The average nitrogen in-leakage rate, and j e The flow resist ~ance of the head vent lines.
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" _ U. S. Nuclecr R:gulatory Commission
. CY-97-041/ Attachment 3/Page 3 :
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1 Results
- A. ' Steady State
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_Two' separate. cases _were analyzed, the first assuming the nitrogen injection rate of
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~4 CFM and the second case, which assumed the increased rate of 7 CFM. The higher flow rate is the maximum possible rate calculated from the_ inventory of the gas used by g the plant;over the ,three-day period (30,000 cubic feet), assuming that all of it was L ilnadvertently injected through the charging system into the primary side. Each case was :
[ run_twice, with a different form loss K-factor to bound the head vent line resistance, F which was not known. The' vent lines typically. hooked up to the vessel and the r pressurizer for refueling. activities are temporary Tygon tubes (see Figure 2 for the diagram of the temporary vent connections). The analysis assumed that the' K-factor
'b equal to 100 would bound the resistance of the vent lines. A lower K-factor, equal to -
ISO was also used The lower number is similar in magnitude to the value calculated for the permanent head _ vent.line, which calculated the frictional losses through the lines. ,
Both vent lines used the same K-factor.
Case 1: 7 CFM N2injection rate and K=50 The results indicate that at this rate the level in the vessel would drop below the hot leg nozzle elevation and the pressurizer would fill up completely. Nitrogen ingestion into the Residual Heat Removal System, which takes suction at the mid-point of the hot leg, would most likely occur. The operators would have.to drain much more than the 5,000 gallons bro the RCS to maintain the level on scale. Since the recorded plant ;
data shows that O was not the case, it can be concluded that the 7 CFM was not a realistic rate t- M late. -
Case 2: -4 CFM N 2injection rate and K=SO The steady state was achieved after approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of transient time simulation.
The RCS pressure stabilized at 19 psia in the upper head. The integrated volume of the water discharged from the primary side to maintain the pressurizer level at 345 inches was approximately 5000 gallons. The level inside the vessel stabilized 62 inches above the top of the hot legs.
Case 3: 4 CFM N2injection rate and K=100 The steady. state was reached after 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of transient time. The pressure in the upper head leveled off at 19.2 psia. The integrated volume of the discharged water
- was 6300 gallons. The water level inside the vessel stabilized at 31 inches above the top of the' hot legs.
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V I U. S. Nucl::ar Regul tory Commission CY-97-041/ Attachment 3/Page 4 B. Refill of the Vessel The second part of the analysis involved refilling the vessel from the Refueling Water Storage Tank. The data shows that the operators cycled the refill valve six times over approximately a three-hour period. The duration of each cycle and the injection flow rates were scaled from the recorded plant data and the scaled data repiotted on Figure 3 (the time scale is not absolute but is referenced to the time the operators begaii the refill process on the morning of September 1,1996). In RELAP, the cycles were approximated by assuming that each refill cycle lasted two minutes and injected 1,200 gallons, for a total of 7,200 gallons. For conservatism, only Case 3 was analyzed, since the results of the steady state showed the largest inventory loss from the vessel.
Some of the pertinent results from this case, combined with the steady state, are plotted in Figures 4,5, and 6. Figure 4 shows the pressure in the upper head. The end of the steady state is at 12,000 seconds (the times are not related to the operator actions) when the nitrogen injection is isolated. immediately the level starts to decrease in the vessel because of the sudden hydrostatic imbalance, and the pressure begins to decrease. The level comes to rest at 316 inches in the calculation (compared to 321 inches in the data). After 20 minutes, there is an additional nitrogen injection because of the valve cycling by the operator. Forty minutes after the N2 isolation, the operators begin the refill process. As can be seen on the plot, the first cycle increases the RCS pressure by 1.5 psi (compared to approximately 2 psi on the data chart). The subsequent refill cycles show comparable pressure spikes.
Figure 5 shows the pressure plot in the pressurizer. There is very little repressurization, beyond temporary spikes," because the vent line on the pressurizer is larger and capable of venting more gas.
Figure 6 is the integrated mass of water drained from the RCS during the code initiation to steady state (to convert to gallons, multiply by 0.12), which on the data chart is 345 inches on the pressurizer level indicator.
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. 1 U. S. Nucimr Regulatory Commission
-CY-97-041/ Attachment 3/Page 5 Summary
. The inadvertent N 2intrusion event was simu!ated with RELAPS/ MOD 3, which has the non-condensable gas modeling capability. Results of the simulation were compared to I the available plant data recorded during the transient. The analysis shows that the most probable nitrogen average in-leakage rate was 4 CFM.
The resistance of the head vent line was bounded by assuming a lower K-factor equal to 50 and an upper K-factor of 100. Using these values, the level inside the vessel was calculated ' be as low as 31 inches above the top of the hot legs and as high as 62 inchc; above the hot legs The level was sufficient to preclude ingestion of nitrogen into the RHR line.
1 Finally, the refill cycles were dynamically simulated. The actual plant response in terms i of the pressure and level was reasonably predicted. Based on the simulation, an l I
estimated 5,000 to 6,300 gallons of water would have to be drained from the RCS to match the recorded data.
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U. S. Nuclear Regulatory Commission
. CY-97-041/ Attachment 3/Page 6 Table 1 Parameters Used in The RELAP/ MOD 3 Analysis Minimum Pressurizer Level in Steady State 345 inches Elevation Of Hot Leg Center Line 185 inches l
Vent Header Pressure 14.3 psia (10" H2O vacuum) i Temperature inside The Vessel 95"F l
' Loops isolated N2Injection Rate 4 CFM and 7 CFM Vent Line Resistance (Form And Friction) 50 and 100 (2 Cases)
Volume Control Tank (VCT) Pressure 30 psig !
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U. S. Nuclear Regulatory Commission
- CY-97-041/ Attachment 3/Page 7 Figure i The HNP RELAPS/ MOD 3 Model Configuration For The N 2 Intrusion Event T
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- U. S. Nuclear Regulatory Commission
. CY-97-041/ Attachment 3/Page 8 Figure 2 Simplified Air Purge Containment Pipmg Diagram Tyson Wnometer Leops Beed Yunt 10 ladas H2O T
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..CY-97-041/ Attachment 3/Page 9 l Figure 3 I
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- CY-97-041/ Attachment 3/Page 11 Figure 5 Pressurizer Pressure O
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- CY-97-041/ Attachment 3/Page 12 Figure 6 Integrated Water Mass Dralned From The RCS o
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