Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999 Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed ML20209B2951999-06-22022 June 1999 Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226 ML20196E9231999-06-21021 June 1999 Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor ML18040A3651999-06-0707 June 1999 Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission ML18040A3661999-06-0404 June 1999 Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr ML20195C9751999-06-0101 June 1999 Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods ML20195C9601999-05-28028 May 1999 Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr ML20207F1811999-05-24024 May 1999 Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns ML20207D1541999-05-21021 May 1999 Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld ML20207D5331999-05-21021 May 1999 Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790 ML20195B1861999-05-21021 May 1999 Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl ML20206S2621999-05-16016 May 1999 Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date ML20195D5911999-05-13013 May 1999 Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411 ML20206P1981999-05-11011 May 1999 Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2 ML20206R6941999-05-10010 May 1999 Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate ML20206N0291999-05-0707 May 1999 Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28 ML20206G8121999-04-30030 April 1999 Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083 ML20206F7731999-04-22022 April 1999 Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2 1999-09-07
[Table view] Category:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML17261A8541989-01-13013 January 1989 Discusses 890110-11 Meetings Re Nozzle Sizing Study.Most Accurate Sizing Obtained by Collecting Data of Edge Diffracted Waves from Geometric Extremities of Flaw ML19324A1111988-05-19019 May 1988 Forwards Memo Describing Results of Testing of Plant Bolting Matls Under FIN A-3866,Task Assignment 12 ML19324B2701988-03-0202 March 1988 Forwards Rept on Metallurgical Evaluation of Five Bolts Obtained from Farley Plant.Bolts Found Acceptable ML20214R2921987-03-18018 March 1987 Forwards Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Niagara Mohawk Power Corp,Nine Mile Point Nuclear Station Unit 1,Docket Number 50-220, Informal Rept ML20207R7571987-03-10010 March 1987 Forwards Technical Evaluation Rept Input for South Texas Initial Plant Test Program Through FSAR Amend 56,Feb 1987 Sser & & Beaver Valley Unit 2 Initial Plant Test Program Through FSAR Amend 15 & Nov 1986 Sser ML20207S5001987-03-0606 March 1987 Forwards Technical Evaluation Repts for Domestic Mark III Plants (Grand Gulf,Clinton,River Bend & Perry) & Gessar Ii. Inserts to Be Included in Section 6.2.1.8 of Draft Sser 2 for Clinton,River Bend & Perry Plants Also Encl ML20195F8651986-10-31031 October 1986 Forwards Request for Addl Info Re MSIV Operability at Facility,Based on Initial Review of Util Rept Entitled, Final Rept 10CFR50.55(e) MSIV Actuators, Forwarded by Util ML20206H3211986-09-10010 September 1986 Forwards Summary Repts from 860811-14 Visit to Kewaunee Nuclear Station & 851002-03 Visit to Cooper Nuclear Station Re Generic Issue 83 on Control Room Habitability ML20206J6001986-08-0808 August 1986 Advises That NUREG-0956 Support Calculations Using ORNL Trends Code to Evaluate Influence of Containment Chemistry or Retention of Hi Can Also Provide Useful Info for General NUREG-1150 Issue Paper,Per Telcon Discussion ML20206H1131986-06-23023 June 1986 Submits DHEAT2 Parametric Calculations for Plant,Per 860620 Discussions.Calculations Run Assuming Any Steam Spike Would Develop Too Slowly to Contribute to DCH Peak Pressure ML20155B0511986-03-0707 March 1986 Forwards Summary of Resolutions to Unresolved Comments Re Reactor Operator & Senior Reactor Operator Exam Given on 851217.All Comments Incorporated in Master Exam Keys ML20214E1721986-02-25025 February 1986 Ack Receipt of 860210 & 21 Ltrs Accepting Task Orders 3 & 4 Under FIN A-3552 & Task Order 5,respectively.Orders Include Work at Palisades & LaSalle Stations & Mod Review at Davis-Besse.Modified Task Order 4 Under FIN A-3550 Encl ML20141N5321986-02-14014 February 1986 Summarizes 860124 Meeting W/Nrc & EC Rodabaugh Re Structural Integrity of Facility Downcomer Design.Design Meets Licensing Requirements for Upset & Emergency Conditions ML20206J2521986-01-24024 January 1986 Forwards Early Draft of Executive Summary from Analysis of Station Blackout Accidents for Bellefonte PWR, Per Request. Initial Draft of Rept Scheduled to Be Completed by 860315 ML20206J3681986-01-15015 January 1986 Discusses Latest Calculations of Molecular Iodine (I2) & Organic Iodide (CH3I) Scrubbing During TC1 Sequence from Draft Plant Rept ML20136F4771985-12-31031 December 1985 Forwards PNL-5718, Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20206J4031985-12-13013 December 1985 Summarizes Preliminary Scoping Calculations for Molecular Iodine (I2) Scrubbing in BWR Pressure Suppression Pools. Calculations Made for Most Recent TC1 Sequence in Draft Plant Rept ML20133A3141985-09-27027 September 1985 Forwards Review of Section 4.7 of Technical Evaluation Rept PNL-5600, Review of Resolution of Known Problems in Engine Components for Tdi Emergency Diesel Generators, Reflecting Views Re Crankshafts for 16-cylinder Engines ML20128H7371985-06-27027 June 1985 Forwards Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept ML20141N2981985-05-29029 May 1985 Requests Listed Addl Info Re S&W 1982 Rept, Ultimate Pressure Capacity of Shoreham Primary Containment ML20126E8721985-05-24024 May 1985 Forwards PNL-5200-3, Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Dtd May 1985 ML20133N7721985-03-27027 March 1985 Forwards Info Telecopied on 850325 Re Locational Distribution of Three Fission Product Species for Surry V Sequence & Time Dependent Release for Fission Product Groups for Peach Bottom ML20214F5101985-03-13013 March 1985 Forwards List of Questions Re Plant Pra,Per 850512 Telcon. Statement of Work, Review of PRA for Seabrook Nuclear Power Plant, Encl ML20133N3461985-02-20020 February 1985 Discusses Review of March Results for Surry & Peach Bottom Sequences,In Order to Quantify Expected Noble Gas Releases. March Model Appropriate for Behavior of Noble Gases ML20134A1011985-02-20020 February 1985 Submits Results of Noble Gas Release Sequences Using March Code for Facilities ML20128P3401984-12-0505 December 1984 Submits Rept for Task 1 Per M Silberberg 841116 Memo Re Concerns Re Lanthanum Releases in BMI-2104.Discusses Discrepancies in Corcon Calculations,Presents Revised Tables 6.14 & 7.16 & Recommends Reanalyses ML20138N6971984-09-18018 September 1984 Forwards Repts Re Irradiation,Decontamination & DBA Testing, Per Request of Y Korobov of Carboline Co ML20134E1591984-08-0202 August 1984 Forwards Brief Summary Rept on Leakage Characteristics of Nuclear Containment Hatches During Severe Accident. Draft of Complete Rept Will Be Mailed Later in Aug ML20127B9221984-07-20020 July 1984 Forwards PNL-5201, Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Grand Gulf Nuclear Station, Unit 1 ML20127B8881984-05-21021 May 1984 Comments on May 1984 Draft Tdi Diesel Generator Owners Group Program Plan.Full Insp of One Engine to Owners Group Spec Recommended ML20093G4821984-05-0202 May 1984 Provides Summary of Battelle Subcontract W/Tdi to Evaluate Special Silicon carbide-impregnated Cylinder Liners & Piston Rings.Task Does Not Involve Dependability Tests of Tdi Engines.No Apparent Conflict Found ML20113A0201984-04-0404 April 1984 Forwards Requests for Addl Info Developed During Review of FSAR Chapter 14 Re Initial Plant Test Program.Review Conducted Through Amend 4.Listing of Items Requiring Resolution Encl ML20117C9421984-04-0303 April 1984 Forwards Proposed Radiological Source Term Input for Facility.Encl Amended to Reflect NRC Suggested Changes ML20093C5281984-03-30030 March 1984 Forwards Audit of Susquehanna Unit 2 Tech Specs, Technical Evaluation Rept ML17320A9711984-03-0606 March 1984 Forwards First Round Questions Following Evaluation of Exxon Rept, Steam Tube Rupture Incident at Prairie Island Unit 1, PTSPWR2 Vs Data,Preliminary Benchmark Analysis. ML17320A9741984-03-0505 March 1984 Forwards First Round Questions on Exxon Methodology Rept for PTSPWR2.Rept Lacks Specific Details Re Biases in Initial Conditions & Boundary Conditions ML20128N6571984-02-22022 February 1984 Comments on Draft Vols IV-VI of BMI-2104,presented at Peer Review 840126 & 27 Meetings.Comments Concern Completed Calculations for Sequoyah Ice Condenser Plant,Recalculated Surry Results & Completed Calculations for Zion Plant ML19306A0151984-02-10010 February 1984 Summarizes 840206-07 Visit to Nevada Test Site Hydrogen Burn Facility to Inspect Condition of Equipment & Cable/Splice Samples After Series of Hydrogen Burn Tests Conducted by Epri.No Indication of External Damage to Equipment Noted ML17320A9731983-11-22022 November 1983 Forwards First Round Questions on Mods to Exxon Draft Repts, PTSPWR2 Mods for St Lucie Unit 1 & Description of Exxon Plant Transient Simulation Model for Pwrs. ML17320A9721983-09-30030 September 1983 Forwards First Round Questions on Exxon Plant Transient Code,Based on Review of Proprietary Rept, Description of Exxon Nuclear Plant Transient Simulation Model for Pwrs. ML20080B5631983-08-12012 August 1983 Forwards Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. Rept Satisfies Milestone for Task 1 of Project 3 Under FIN A-3393 ML20211D5971983-04-11011 April 1983 Forwards Summary of Independent Development of Finite Element Models & Determination of Natural Frequencies for Piping Problems in Containment Spray Discharge Line & Accumulator Loop 4 ML20132B4961983-02-11011 February 1983 Forwards Evaluation of Generic Key Indicators for Project Engineering/Design Activities at Facilities ML20072L7101982-12-20020 December 1982 Forwards BNL 821213 Memeo Re Degraded Core Accidents at Facilities,Per Task III.3 Defined in Design Basis for Hydrogen Control Sys in CP & OL Applications. No-cost Extension to Contract Requested ML20079J5641982-12-16016 December 1982 Summarizes Findings of 821207-08 Plant Tour Re Use of PORVs or Depressurization Scheme for Removing Decay Heat.Addl Info Requested Includes General Arrangement & Isometric Drawings of Piping Near San Onofre Pressurizer ML20027D1751982-10-18018 October 1982 Responds to 820806 Request to Evaluate Rapid Depressurization & DHR Sys for C-E Plants W/O Porvs, Discussing Role of Task Action Plan A-45, Shutdown Heat Removal Requirements, in Supporting Evaluation of Facility ML20126F4791982-10-0101 October 1982 Requests Permission to Observe Upcoming Types A,B & C Tests at Listed Facilities,Per FIN B-0489, Containment Leak Rate Testing ML20072L6851982-09-21021 September 1982 Forwards Analysis of Full Core Meltdown Accidents in Grand Gulf Reactor Plant, Draft Informal Rept.Rept Satisfies Preliminary Rept Milestone for Task I Defined in Safety Evaluation of Core Melt Accidents:Cp,Ml & OL Applicants ML20027A8971982-08-26026 August 1982 Forwards Nonproprietary Vols 1 & 2 of, Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SER (F-11 & B-60, Technical Evaluation Rept ML17276B0731982-02-10010 February 1982 Comments on Const of Two Power Reactors by Skagit/Hanford Nuclear Project at Hanford.Purchasing & Finishing Terminated Wppss Plants at Hanford & Satsop Should Be Considered as One Alternative to Proposed Action 1989-01-13
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