|
---|
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 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 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 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 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 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 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 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 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 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 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 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 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 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 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 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 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 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 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 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 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 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 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 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:UTILITY TO NRC
MONTHYEARML17056A9771990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revs 4 & 5 to Odcm. ML18038A3231990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM ML18038A3221990-08-24024 August 1990 Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation ML18038A3201990-08-21021 August 1990 Discusses Status of Completion of Generic Safety Issue 75, Item 2.2.2 Re Vendor Interface for safety-related Components ML18038A3251990-08-20020 August 1990 Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed ML20058Q1151990-08-15015 August 1990 Forwards Response to Regulatory Effectiveness Review on 900604-08.Response Withheld (Ref 10CFR73.21) ML20055G5261990-07-18018 July 1990 Forwards Decommissioning Rept Indicating Reasonable Assurance That Funds Available to Decommission Facility. Financial Assurance of Cotenants Also Encl ML17058A5841990-06-27027 June 1990 Forwards Rev 8 to Updated FSAR for Nine Mile Point Unit 1. Changes Re Findings Noted in Insp Rept 50-220/88-201 Included in Rev.Rev Does Not Reflect Changes Re Reg Guide 1.97,Rev 2 ML18038A3051990-06-26026 June 1990 Responds to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issue Requirements.Tabulated Info Re Generic Safety Issue Title,Applicability,Status & Remarks Encl ML20042E3741990-04-11011 April 1990 Lists Info Re Unit Containment Vent & Purge Valves,Per NRC 900315 Request ML20012F6131990-03-30030 March 1990 Forwards Changes to Security Training & Qualification Plan. Plan Rewritten & Revised to Incorporate performance-oriented Training Program.Plan Withheld (Ref 10CFR2.790(d)) ML17056A6721990-03-0202 March 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML18038A7071990-02-0505 February 1990 Forwards Rev 5 to NMPC-QATR-1, QA Topical Rept for Nine Mile Point Nuclear Station Operations. ML18038A7061990-01-10010 January 1990 Forwards Rev 21 to Emergency Plan,Revised Emergency Action Procedures,Including Rev 7 to S-EAP-1,Rev 11 to S-EAP-2,Rev 8 to S-EAP-3 & Epips,Including Rev 13 to S-EPP-4 & Rev 13 to S-EPP-20 ML20042D1981989-12-28028 December 1989 Informs of Delay in Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Until BWR Owner Group Generic Program Completed & NRC Appraisal of Program Reviewed by Util ML18038A7021989-11-28028 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Usi A-5,A-6 & A-7 Inapplicable to Facility ML18038A7711989-11-28028 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Requirements for NUREG-0612 Re Control of Heavy Loads Near Spent Fuel Completed.Usi A-40 Re Seismic Design Criteria Being Resolved as Part of USI A-46 ML18038A7701989-10-25025 October 1989 Forwards Rev 1 to Updated SAR for Nine Mile Point Unit 2. All Errata Items Identified in Attachment 1 to Previous Updated SAR Transmittal Ltr of 890428 Resolved.Programs to Resolve Setpoint Issues Will Be Established by 891130 ML18038A7611989-09-29029 September 1989 Forwards Addl Info Re Simulator Certification for Facility, Per 890803 Request.Schedule Extension Verbally Granted Until 890930 ML18038A6641989-09-0808 September 1989 Forwards Restart Readiness Rept. Rept Submitted in Fulfillment of Util Third Action Required by Confirmatory Action Ltr CAL-88-17,dtd 880724 ML17056A2701989-08-30030 August 1989 Forwards Nine Mile Point Nuclear Station - Unit 2 Semiannual Radioactive Effluent Release Rept Jan-June 1989 & Rev 1 to Administrative Procedure AP-3.7.1 Process Control Program. ML20245E8451989-08-0707 August 1989 Forwards Rev 6 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21 & 10CFR2.790(d)) ML20247M2771989-07-25025 July 1989 Forwards Issue 2,Rev 0 to Physical Security Plan.Specific Changes Set Forth in Attachment A.Supporting Info Set Forth in Attachment B.Master Acronym & Abbreviation List Also Encl.Encls Withheld (Ref 10CFR73.21) ML20246N9041989-07-13013 July 1989 Forwards Vital Area Evaluation for Plant Screenhouse.Encl Withheld (Ref 10CFR73.21(b)) ML18038A6611989-07-11011 July 1989 Provides Response to Generic Ltr 89-06, Task Action Plan Item I.D.2 - Spds. Certification Stating Plant Unit 1 SPDS Sys Meets Requirements of NUREG-0737,Suppl 1 & Plant Unit 2 SPDS Sys Will Be Modified to Meet NUREG-0737,Suppl 1 Encl ML18038A6591989-06-23023 June 1989 Forwards Util Response to 890522 Salp.Util Agrees W/Need to Improve Surveillance Testing Data & Upgrading Design Basis for Core Spray & HPCI Sys ML20244E3631989-06-15015 June 1989 Forwards Revised Application for Amend to License DPR-63, Incorporating Request to Limit Reactor Power Level at Which Blocking Valve in Feedwater May Be Closed ML18038A4731989-05-31031 May 1989 Forwards Emergency Preparedness Exercise/Drill Scenario 12 1989 Annual Exercise, Vols 1 & 2 ML18038A4581989-04-28028 April 1989 Forwards Rev 0 to Updated SAR for Nine Mile Point Unit 2. Emergency Plan,Formerly Included in Fsar,Not Included in Updated Sar.Portions of Util Responses to NRC FSAR Questions Incorporated Into Body of Initial Updated SAR ML20246Q0071989-04-28028 April 1989 Forwards Proprietary Section 6A of Updated FSAR for Nine Mile Point Unit 2.Section 6A Withheld (Ref 10CFR2.790) ML20246B5451989-04-28028 April 1989 Advises That Util Will Submit Rev to Restart Action Plan After Receipt of Repts from NRC Special Team Insp & INPO Reassessment of Facility ML18038A4561989-03-23023 March 1989 Forwards Addl Info Supporting Application to Use Alternative to 10CFR50.55a Requirements.W/Two Oversize Drawings ML18038A4551989-03-21021 March 1989 Provides Util Plans for Future Exam & Evaluation of Four Feedwater Nozzles Per NUREG-0619.Indications Conservatively Evaluated as Cracks Not Scratch Marks.During 1993 Refueling Outage,Sparger from Nozzle a Will Be Removed 05000410/LER-1989-003, Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected1989-03-21021 March 1989 Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected ML18038A4521989-03-0202 March 1989 Forwards Responses to NRC Questions Re Licensee Restart Action Plan & Nuclear Improvement Program.Replacement Pages for Action Plan Encl ML20245J5521989-03-0202 March 1989 Forwards Rept of Physical Security Event,Reported Via Emergency Notification Sys on 890203 ML18038A4511989-02-22022 February 1989 Forwards Rev 4 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting & Responsibility Changes as Well as Descriptions for Organizations Not Previously Identified ML18038A4501989-02-14014 February 1989 Forwards Rev 1 to TR-6801-2, Mark I Torus Shell & Vent Sys Thickness Requirements Nine Mile Point Unit 1 Nuclear Station. Requests Approval to Use Certified Matl Test Repts for Most of Torus Matls ML18038A4341989-01-18018 January 1989 Forwards Revised,Second 10-yr Interval Inservice Testing Program Plan for Plant & Supporting Documentation,Per 881220 Commitment.Interim Approval of Program as Submitted to Spent Fuel Loading Scheduled for Apr 1989 Requested ML18038A4201988-09-29029 September 1988 Advises That No Unresolved Safety Issues Re Flow Fluctuations & Neutron Flux Noise Exist,Per NRC 880527 Ltr Requesting Summary of Plans to Mitigate Oscillations in APRM Signals & Total Core Flow ML20154C4221988-09-0909 September 1988 Informs That Contracted Vendor to Present Courses Will Not Be Able to Commence Training Until Later in Month of Oct or Early Nov 1988.Schedule Revised to Have Instrumentation & Control Initial Training Implemented by Nov 1988 ML20154B4301988-09-0808 September 1988 Forwards Security & Safeguards Contingency Plan.Definition of Security Force Member Discussed.Plan Withheld ML17055E2471988-08-30030 August 1988 Forwards Semiannual Radioactive Effluent Release Rept, Jan-Jun 1988, & Revs 4 & 6 to Offsite Dose Calculation Manual. ML18038A4121988-07-28028 July 1988 Forwards Info Re Implementation of NUREG-0131,Rev 2, Technical Rept on Matl Selection & Process Guidelines for BWR Coolant Pressure Boundary Piping. ML18038A4101988-07-28028 July 1988 Forwards Comments,Clarifications & Agreements Re Implementation Re 880506 SER Concerning 10CFR50,App J.Info Submitted Per Commitment Resulting from 880609 Meeting W/ NRC.W/15 Oversize Drawings ML18038A4111988-07-28028 July 1988 Forwards Licensee Response to Generic Ltr 88-01 Re Austenitic Stainless Steel Piping at Facility.Application for Amend to Incorporate Requirements of Generic Ltr Will Be Submitted Later ML20151A2971988-07-15015 July 1988 Forwards Changes to Physical Security Plan.Supporting Info Also Encl.Encls Withheld (Ref 10CFR73.21) ML20151A2751988-07-15015 July 1988 Forwards Changes to Security Training & Qualification Plan. Changes Withheld (Ref 10CFR2.790) ML18038A4081988-07-0707 July 1988 Submits Listed Changes to Util 880609 Comments on SALP, Including Advisal That Review of Nonradiological Chemistry Program Revised to More Accurately Describe How Review Performed ML18038A4061988-07-0606 July 1988 Responds to Request for Addl Info on ATWS Review Re Alternate Rod Injection & Recirculation Pump Trip Sys.W/ Seven Oversize Drawings 1990-08-30
[Table view] |
Text
I REGULATORY x.. ORMATION DISTRIBUTION SYS 8 (RIDS)
ACCESSION NOR'8402150345 DOC ~ DATE: 84/02/10 NOTARIZED'ES DOCKET FACIL:50-410 Nine Mile Point Nuclear Stationi Unit 2i Niagara Moha 05000410 AUTH INANE AUTHOR AFFILIATION LEMPGESiT.E, Niagara Mohawk Power Corp.
RECIP ~ blAME RECIPIENT AFFILIATION SCHNKNCERgA ~ Licensing Branch '2
SUBJECT:
For wards proprietary nonproprietary structural audit open issue close out info,Affidayit requesting proprietary status for info encl. Proprietary info withheld.
DISTRIBUTION CODE: 8001S COPIKS RECEIVED:LTR ( ENCL, 3 gP SIZE:. '2,'7++~~
TITLE: LicenSing Submittal: PSAR/FSAR Anldts 8 Related Correspondence NOTES:PNL 1cy FSAR'S 8 AMDTS ONLY, 0500041.0 RECIPIENT 'COPIES RECIPIENT COPIES ID CODE/NAME LTTR EbICL IO CODE/NAME LTTR ENCL NRR/DL/ADL 1 0 NRR L82 BC 1 0 NRR LB2 LA 1 0 HAUGHEYiM 1 1 INTERNAL: ELO/HDS3 1 0 IE FII E -
P3 1 -1 IE/DEPER/EP8 Qi5(6)7 5 3 IE/DEPER/IRB ftfif. 1 1 IE/DQASIP/GABE]g 1 1 NRR/DK/AEAB 1 0 NRR/DE/CKB Q'iq 1 1 NRR/DF/EHEB 1 1 NRR/DE/EQB ~yogi 2 "2 NRR/DE/GB 2 2 NRR/DE/MKB Qx~ 1 1 NRR/DE/MTEB 1 1 NRR/DE/SAB @fZ+ 1 1 NRR/DE/SGEB 1 1 NRR/DHFS/HFEB+@$ 1 1 NRR/DHFS/LQB 1 .1 NRR/DHFS/PSRB~~ 1 1 NRR/DL/SSPB 1 0 NRR/DS I/AKB @Q4 1 NRR/DS I/ASB >I 1 1 NRR/DSI/CPB AZa 1 1 NRR/DSI/CSB Q 1 1 NRR/DSI/ICSB NRR/DS I/METB l3 1, NRR/DS I/PSB ~X/ 1 1
1 NR lf 1 1
1 NRR/DSI/RSB +35 1 1 G FILE t 1 1 RGN1 P3>sf' I/MIB 1 0 EXTERNAL: ACRS esw"1'> 6 BNL(AMOTS ONLY) @&0 NPa, DMB/DSS (AMDTS) QPg f400 FEMA "REP DIV 39 NPo NOa' LPOR 03 gpO @Pa NRC PDR 02 1 NSIC 05 HPO HAP NTIS N$'o ppo NOTES-' 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 54 ENCL 47
ql 'f'( ~ IN fj I/.j f, l,',l) j,)I'>I, ~g),fr t>> h
)) J, fit ll>> II) II I) I)) f! 't)I pl ,g q>>ef.~,rj,f'j f j f<<f<<jt ',
zj, lf > fffsl)f' "5 jr f
- 7) r 'j fj, '>> 'jjA I I )f) ~ ~ t g, >>) tl f)'jg 'I ). jf '.<<f <<>j ll j tlt l g)!)' f')3>> If 9 It"Ij )l I
' ~
f!f!, ft f I!jr,fg 1 lt jli, g I
,11 ",Ir I! I fly I'jf t I
I' ft)
I I
t I
I'I P'j,f P QC I',I),ttf I), 'I II', t f I g I) 'l')
y<,)t~ge frt)~ j,g jf l I I 0f rr )a,
>>W P.+;",l>> e~>>>>>>>>tet>>>>>>>> +
lrh! tIhft ff)'h t <<
jj t!j I! II p jrf > g fr )gt'<<f f )gh,'r.'ft>>,) fj ~
I ' ' >> "II jtf f
f'I il l I
~
'h r 'ht)
)g
'h
) t v I
~ ~ << I 0't w$ gggtI 4 hj) "'
.~ )l ~
'>> l ggf )I
,K C~ "t r$ Cist 5-J H~ 49M g)I)~O) jf " ht l" ll <<
NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST. SYRACUSE, N,Y, 13202/TELEPHONE (315) 474-1511 February 10, 1984 (8037)
A. Schwencer, Chief Licensing Branch No. 2 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Schwencer:
RE: Nine Mile Point Unit 2 Docket No. 50-410 Enclosed for your review are eight copies of information to close out certain open issues of the NRC Structural Audit. During the Structural Audit of December 12 through 16, 1983 we committed to provide this information.
I '
Attachment A provides the non-proprietary information. Attachment B provides an affidavit requesting proprietary status for information in Attachment C which is considered proprietary by Stone and Webster Engineering Corporation.
)~
Sincerely, Vice President of Nuclear Generation TEL/NLR'lf Attachment cc: A. F. Zallnick, Jr.
C. V. Mangan M. Haughey W. Morrison S. Z. Doyle (File)
R. Pinney (CHOC)
. @pe quoit
~-.-'u>~
<O~ qO<V',"
egg,. b>,
ego>pgyo p98 '9490500.
i 7 pI~~
Nfl<
IroP
LLL' 4 4
~ 4 ~
ATTACHMENT A j . ~ i NINE MILE POINT UNIT 2 NRC REQUEST NO. 1 Verify and confirm the design of all structures affected by SRV and hy-drodynamic loading.
RESPONSE
The design of structures within the reactor building will be verified for the SRV and hydrodynamic loading during the load verification stage.
Structures within the reactor building either are designed for conceptual (i.e., preliminary) SRV and hydrodynamic loading or are provided with an adequate design margin, which should account for future load verifica-tion.
Based on current schedule, the load verification for the reactor pedestal is planned to be completed by June 1984. The load verification for other structures will be completed by September 1985. The NRC will be notified of the results of this verification upon completion.
a402150345 C2/12177/7/2RH
0 NINE NILE POINT UNIT 2 NRC REQUEST NO. 2 Provide an assessment of the significant differences between the require-ments of ACI 349, as augmented by the NRC Regulatory Guide 1.142 and the requirements of ACI 318-77. (Reference NRC Q Nos. 220.31 and 220.33).
RESPONSE
Results of an assessment of the significant differences between the codes used in NMP2 design versus those referenced in NRC Regulatory Guide 1.142, Revision 1, will be submitted by June 1984.
C2/12177/7/2RH
NINE 11ILE POINT UNIT 2 NRC REQUEST NO. 3 Review the effect of vertical floor flexibility in the analysis of equip-ment and floor designs.
RESPONSE
of the effect of vertical floor flexibility in the analysis An assessment of equipment and floor designs will be performed and submitted 'y June 1984.
C2/12177/7/2RH
NINE MILE POINT UNIT 2 NRC REQUEST NO. 4 Provide a summary of cable tray support calculation methodology for the supports attached to floor and ceiling.
RESPONSE
ELECTRICAL TUNNEL CABLE TRAY SUPPORTS ATTACHING FIOOR TO CEILING
~Summar The most critical cable tray support type FP87 was reanalyzed to include differential movement of the top (roof) slab relative to the base. The support at the top of the slab was modeled first as pinned, which was the condition used in the original design calculation. all stresses were found to be acceptable. The second case assumed the support to be fixed and stresses were still found to be acceptable.
A~nal sis Static Anal sis - Dead loads from the members and cable tray-loadings were included. Differential slab movement of the top slab relative to the base was also statically analyzed by treating the OBE profile (maximum) displacements as support displacements. This is a conservative approach, since the profile displacements are the maximum values of the actual displacements.
- 2. D namic Anal sis " A lump mass model was used to perform the dynamic analysis. The response spectra of the roof slab were input into the analysis. OBE being the most critical seismic case (after consid-ering load factors), was used. Member forces and moments were determined by using modal superposition and SRSS of the responses.
D~esi n All members were checked and found to be within allowable stress limits for both cases (top support, fixed, and pinned). Results of the computer run for static were added by absolute sum method to the SRSS of dynamic stresses.
C2/12177/7/2RH
0 NINE MILE POINT UNIT 2 ELECTRICAL TUNNEL TRAY SUPPORTS WITH DISPLACEMENT Summary of Results Verticals Original W/Differential W/Differential
~Desi n Movement - Pinned Movement - Fixed Axial Load 0.7 K 1.1 K 1.1 K Bending Moment* 10.1 IN-K 9.6 IN-K- 21.9 IN-K Combined Stress 0.3 0.35 0.67 Equation+
'>NOTE: The original design has a higher moment than the pinned, differential movement design because of a conservative, sim-plifying used assumption used during the original analysis ~
Horizontals For all designs, the vertical member stresses govern the shape selection.
Therefore, for horizontal members using the same members as verticals is adequate.
Vertical Connection NOTE: The design of vertical connection governs over Horizontal to connection.
Allowable Loads-Connection Original f W/Dif e rent ia 1
- Pinned W/Differential
- Fixed Ca acit '~Desi n Movement Movement Shear 2.0 K 0.5 K 0.4 K 0.77 K Axial 1.5 K 0.7 K 1.1 K 1.1 K "Combined stress equation Fa + Fb <1.0 Similar to AISC 1.6-la Fa allow Fb allow C2/12177/7/2RH
NINE MILE POINT VNIT 2 NRC REQlJEST NO. 6 Provide data on strength, material type, and mechanical properties of Nelson studs, used in NMP2 polar crane rail support design.
RESPONSE
Nelson studs Type CPL, 7/8-inch diameter threaded studs are used in fastening polar crane rail supports. This method of fastening offers easy installation, reduced maintenance, and added safety during instal,-
lation and operation. The attachment provides the data on material composi,tion, type, strengthi etc, Crom the catalog, Nelson - Construction Applications in Power Generating Plants by (TRW - Nelson Division).
C2/12177/7/2RH
~ (
APPLICATION 10 STEEL MILLS
.Ntt00DIN KIB3 N800WOMR II2lMK I2l60Q iSTANDARD STUD DIMENSIONS CPL PITCH DIAMETER BASE STUDS E F Weld Weld Ttireed Std. INn. fillet fNet f Diameter t. th Dilnetei t i C B J 5/8 /8 /4 rsvp 4Available inreqmrcd tcngtlo above cpcoficdmimmvm, D
c-ELSON PITCH DIAMETER BASE AND FULL BASE HBL FULL BASE THREADED STUDS HREADED STUDS FOR SECURINO OVERHEAD CRANE AILS Used with a variety ol clips designed for par iSTANOARD STUD DIMENSIONS ticular situations. NELSON pitch diameter and lull base threaded studs provide overhead crane rail fastening E I f that offers speed of installation, added safety, and Wold Weld reduced maintenance at lower cost. Tbread Std. Btin. fittet fittct iiaeeter L Dianeter H t 5/B 5/8 3/8 I I/2 3 16 34 3/4 /2 ~ /4 /4 lrc BENEFITS:
~
tcI
~ FASTER RAIL INSTALLATION All installation is
~ .e topside no underneath staging or scaffolding err unnecessary to back up nuts with wrench on under.
<<'y side.
~ QUALITY ASSEMBLY AT LOWEST COST Weak.
nesses in craneway sections caused by drilled or punched holes is eliminated.
~ Rf DUCED MAINTENANCELess corrosion because holes are eliminated.
~ SAFER Drop out of bolts, due to loosening in service or assembly, is eliminated.
Pri<<red ie U.S.A.
GENERAL INFORMATION 1 CPL SPEC 1 THREADED PITCH DIAMETER BASE STUD . "~ 2.3
~,
~ ~ ~ ~
CFP, CFL, FFL SPEC 2 FULL THREADED STUDS. 4,6 NBI. SPEC 3 NO THREAD STUDS .. ~....., ~...,, ~,, ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6
~ ~ ~ ~ ~
84X REFRACTORY "Y"ANCHOR BTUDS .. d RGP SPEC 4 SPEC 6- RECTANGULAR STUDS ...............,.
~.........,.,. .......
~,,.......
~
~ .. 8 R7P SPEC 6 RECTANGULAR STUDS w/HOlE ~...,....'. 7
- ~ ~ ~
L2L SPEC 7 LAGGING STUDS w/HOLE . ~ ~ ~ . ~..... .. ~ 7 SSL SPEC 8 FEMALE SPRINKLER STUDS........ ~... ~.....,...... ~.........,, 8
~ .
CKL SPEC 9- THREADED COLLAR STUDS 8 F3L SPEC 10- NO THREAD COLLAR STUDS ~ ~ ~ . ....
~ ~ ~ .. 9 H3P SPEC 11 NAMEPLATE STUDS 9 N3A SPEC 12 ALUMINUMNAVY TYPE ANNULAR RING STUDS . ~ .. ~.... ~,... ~ ~ . ~ .. 10 N3P SPEC 13 NAVY TYPE ANNULAR RING STUDS ....... ~ . ~ ... ~ 10 R9L SPEC 14 ROPE HOOK STUD ~ 11 SL SPEC 16 20- STANDARD CABLE HANGER STUDS 12 SL SPEC 21 PLATE HANGERS 13 SL SPEC 22 TUBULAR HANGERS 13 P2P SPEC 23 DOUBLE POINTED INSULATION PINS . ~ 14 D2L SPE C 24 DEFORMED BAR ANCHOR 16 S3L SPEC 26 SHEAR CONNECTORS ~ . 18 H4L SPEC 26 CONCRETE ANCHORS 17 ATC,ATS,ATA,FTC SPEC 27 THREADED STORED ARC STUDS 18 TPC SPEC 28 STORED ARC PIN l9 CHP SPEC 29- CUPPED HEAD INSULATION PIN 20 S7X SPEC 30 REFRACTORY "STEERHORN" ANCHOR 21 VXCD SPEC 31 ANCHOR ASSEMBLY 21 RWP SPEC 32 WIGGLED RECTANGULAR TWO TINE STUD 22 SPEED CLIPS 23 STUD ACCESSORIES 24 INSULATION FASTENERS QTY'S. PER CARTON . ~ , . 26 STANDARD FERRULES .26, 27 WEIGHT CHART THREADED STUDS, NON THREADED .............. 28 WEIGHT CHART SHEAR CONNECTORS, ANCHOR STUDS ......,..... 29 STUD TENSILE TORQUE STRENGTHS . M,31 STORED ARC STUD TENSIlE TORQUE STRENGTHS ~................. 32
]r, ~
\
~
~
~ ~
~ ~
~ ~ ~
~ ~ ~ ~ ~ .'I 'o
~ ~ ~ ~ ~ ~ ~ ~ ~, ~
~ ~
~ ' ~ ~ ~ ~
o ~ ~
~ ~
~
~
~ I ~ ~
~ ~ ~
~ ~
~ I ~ ~ ~ ~
~ ~ ~ ~ '
~ ~ ~
~
~ '
~ ~
~ ~ ~, ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ o o
~ ~ ~ ~
~;
o ~
~ . ~ ~ ~ ~ ~ ~
~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~
~ ~ ~ ~ ~
~ ~ ~
~ ~ ~ ~ ~ ~ . ~
~ ~ ~ ~
~ ~
~ ~
~ ~ ~ ~ ~ ~ ~ ~
~ ~ ' '. ~ ~ ~ ~
~ ' ', ~ ~ ~ ~ ', ~ ~
~ ' ~ ~ o o ~ .: ~ ~ ~ ~ ~
~ ~ ~ . ~ ~ ~ ~
~ ~ ~ ~ o ~ ~ ~ ~
~ ~
~, ~ ~ . ~ . ~ ~ ~ ~ ~ . ~
~ ~ ~
~ ~ ~
~ ~
~
~ . ~ ~ ~ ~
~
~ ~
~
~
~ ~ ~ ~ . ~ ~ ~ . ~ ~ ~ ~
~ ~
~ ~ ~ ~ ~ ~ ~
~ . ~ ~ ~
~ ~ ~ ~ ~ ~ 'o
~ ~ ~ ~ ~ . ~ ~ ~
~ ~ ~ ~ ~ . ~ . ~
~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~
' ~ ~ ~ ~
~ o ~
~ I ~
~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ I
~ ~ ~ I~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ I ~ ~ ~ ~ ~ ~
II
~ ~ ~ I ~ I II ~ ~ ~ ~
~ ~ ~ II ~ I ~ ~ ~ o ~
I I II o ~ ~ ~ ~ I ~
NINE MILE POINT UNIT 2 NRC REQUEST NO. 7 Provide a summary of how cable (rope) slack is considered in the con-tainment polar. crane design.
RESPONSE
Dynamic analysis of the polar crane considered trolley positions at mid-span (MID), at quarter-span, and at the end of span (END); with the load positioned at maximum lift lift the and with no load.
(UP), i.e., highest elevaiton, at minimum trolley at quarter span analysis was (DOWN) discontinued when it became apparent that stress levels would be lower than other load conditions.
The attached table summarizes the rope accelerations under OBE and SSE seismic loading for the preceding various conditions.
The maximum dynamic acceleration alone had a value 'of 1.01 g, which when considered against 1 g gravity loads results in a stable rope situation, with essentially no differential acceleration and no slack-rope condi-tion.
C2/12177/7/2RH
NINE MILE POINT UNIT 2
SUMMARY
OF POLAR CRANE ROPE LOADS OBE Load Dynamic .Static and Dynamic Position Acceleration (Gs)
MID/UP 0.63 1.63 MID/DOWN 0.48 1.48 END/UP 1.00 2.00 END/DOWN 0,44 1.44 SSE Load Dynamic Static and Dynamic Position Acceleration Gs) Acceleration Gs MID/UP 0.68 1.68 MID/DOWN 0 '1 1.61 END/UP 1.01 2.01 END/DOWN 0.54 1.54 C2/12177/7/2RH
NINE MILE POINT UNIT 2 NRC REQUEST NO. 9 Revise response to NRC Question 220.28 based on reviewing a seismic Category I structure for an additional torsional rqoment resulting from additional eccentricity of 5 percent of the maximum building dimension.
RESPONSE
See revised response to NRC Question 220.28.
C2/12177/7/2%I 14
NINE MILE POINT UNIT 2 QUESTION F220.28 (SRP 3.7.2-II.ll)
To account for accidental torsion, the SRP states that an additional eccentricity of +5 percent of the maximum building dimension at the level under consideration should be assumed in the seismic analysis of Category I structures. For Nine Mile Point 2, however, the accidental torsion effects for the additional +5 percent were not considered in the analysis. Provide an assessment of the adequacy of the analysis con-sidering the effects of accidental torsion.
RESPONSE
As explained in Section 3.7.2.11A, the seismic analyses of Category 1 structures consider the effects of actual eccentricities between the centers of rigidity and centers of mass of structural components (which cause the torsional loading). Therefore, 'since the results of the analyses already account for the torsional effects, it is not necessary to consider an additional eccentricity of 5 percent of the maximum building dimension.
Additionally, the design of the control building, which is considered representative of Category I structures, was reviewed for an additional torsional moment resulting from additional eccentricity of 5 percent of the maximum building dimension. It was shown that the additional shear stresses resulting from this analysis were not significant and were within the design capacities.
C2/12177/7/2RH 15
NINE MILE POINT UNIT 2 NRC REQUEST NO. 10 Provide additional justification for the validity of the use of the 1.3 static coefficient factor in equipment design (Reference NRC Ques-tion 220.9).
RESPONSE
Response to this request is already incorporated in FSAR Amendment 7, December 1983.
C2/12177/7/2M'
NINE MILE POINT UNIT 2 NRC REQUEST NO. 11 Provide a discussion on the primary containment hatch boundary conditions and the correlation of forces/displacements between the two models.
RESPONSE
Response to this request will be provided by March 1984.
C2/12177/7/2RH 17
NINE NILE POINT UNIT 2 NRC RE(UEST NO. 14 Verify all Category I foundations for stability considering upward seismic forces.
RESPONSE
Response to this request will be provided by March, 1984.
1 t
Ir fI t
A
NINE MILE POINT UNIT 2 NRC REQUEST NO. 15 Verify that radwaste and screenwell buildings are analyzed and designed as independent structures.
RESPONSE
The screenwell building design is updated to reflect the results of the revised seismic analysis, which does not include the radwaste building.
The radwaste building is seismically analyzed as an independent struc-ture; therefore, both structures are analyzed and designed independently of each other.
C2/12177/7/2RH 23
NINE NILE POINT UNIT 2 NRC REQUEST NO. 16 For all Category I buildings, verify vermiculite concrete-bearing capacity against sliding resistance.
RESPONSE
Response to this request will be provided by March, 1984.
I C ATTACHMENT B I
FEB v~ )~~~
Commonwealth of Massachusetts)
SS.
County of Suffolk ~V<8cuso
) 9u8rfegs I, Ben Charlson, being duly sworn according to law depose and say I am Vice President of Stone 6 Webster Engineering Corporation (SWEC) and that:
For the reasons listed below the material contained in Attach-ment C of the responses to the U.S. Nuclear Regulatory Commis-sion (NRC) request for information from their structural audit which is being filed with the U.S. Nuclear Regulatory Commis-sion by Niagara Mohawk Power Corporation (NMPC) in connection with its license application for Nine Mile Point Unit 2, Docket No. 50-410, contains information considered by SWEC to be con-fidential information containing trade secrets and should be withheld from public disclosure.
- 2. In support of its averment that the above-mentioned information is confidential, SWEC provides the following reasons:
a ~ The information sought to be withheld consists of modeling techniques used in seismic analyses of the structures, techniques to analyze column loading of the spent fuel pool, and design basis and details for the polar crane supports.
- b. I am a Vice President for SWEC and have the authority to review and protect the confidential commercial information sought to be withheld.
c ~ SWEC is in the business of designing and constructing nuclear power plants. This business is competitive and firms that engage in it compete on the basis of the nature and quality of the products and services that they offer clients. The above referenced material is one such pro-duct.
- d. The subject material was developed at considerable expense to SWEC and is of substantial value to SWEC in the conduct of its business. A competitor would derive an unfair advantage in obtaining the proprietary information sought to be withheld. Thus the unrestricted disclosure of this material could have an adverse commercial impact on SWEC.
The data is plant specific and the methodology is for Nine Mile Point Unit 2; however, the data could be applied to other situations.
- e. It is, accordingly, the customary practice of SWEC to treat such material as confidential commercial informa-tion.
C3/12177/192/5Y
~
~, ~ F'
- f. To the best of my knowledge and belief, the identified materials are not, available from any public source and have not been made available to third parties, except in confidence.
Ben Charlson, being duly sworn, deposes and says that he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.
Ben Charlson Vice President Stone 8 Webster Engineering Corporation Sworn and su/scribed before me this J day of January 1984 Catherine Trabucco
).y pic (r.NOTARY PUBLIC For the Cofnmopvealth of MassaofIIII)t0 My Co~issi6n Expires ffov, 8, NN C3/12177/192/5Y
4 l
l c wynd y~
k' P
l fl
'1
ATTACHMENT B U
Commonwealth of Massachusetts)
SS.
County of Suffolk ~Ylacro
)
Quarterly I, Ben Charlson, being duly sworn according to law depose and say I am Vice President of Stone 6 Webster -Engineering Corporation (SWEC) and that:
For the reasons listed below the material contained in Attach-
,ment C o'f the responses to the U.S. Nuclear Regulatory Commis-sion (NRC) request for information from their structural audit which is being filed with the U.S. Nuclear Regulatory Commis-sion by Niagara Mohawk Power- Corporation (NMPC) in connection with its license application for Nine Mile Point Unit 2, Docket No. 50-410, contains information considered by SWEC to be con-fidential'nformation containing trade secrets and should be withheld from public disclosure.
In support of its averment that the above-mentioned information is confidential, SWEC provides the following reasons:
a ~ .The information sought to be withheld consists of modeling techniques used in seismic analyses of the structures, techniques to analyze column loading of the spent fuel pool, and design basis and details for the polar crane supports. v \
- b. I am a Vice President for SWEC and have the authority to review and protect the confidential commercial information sought to be withheld.
C. SWEC is in the business of designing and constructing nuclear power plants. This business is competitive and firms that engage in it, compete on the basis of the nature and quality of the products and services that they offer clients. The above referenced material is one such pro-duct.
- d. The subject material was developed at considerable expense to SWEC and is of substantial value to SWEC in the conduct of its business. A competitor would derive an unfair advantage in obtaining the proprietary information sought to be withheld. Thus the unrestricted disclosure of this material could have an adverse commercial impact on SWEC.
The -data is plant specific and the methodology is for Nine Mile Point Unit 2; however, the data could be applied to other situations.
- e. It is, accordingly, the customary practice of SWEC to treat such material as confidential commercial informa-tion.
C3/12177/192/5Y
. ~
To the best of my knowledge and belief, the identified materials are not available from any public source and have, not been made available to third parties, except in confidence.
Ben Charlson, being duly sworn, deposes .and says that he has read the foregoing .affidavit and the matters- stated therein are true and correct to the best of his knowledge, information, .and belief.
Ben Charlson Vice President Stone 8 Webster Engineering Corporation Sworn and su/scribed before me this l day of January 1984 Catherine Trabucco
,< j rr,hlOTARY PUBLIC
,Foi,the~6mrrionwealth of MasNchNON
,> "'y Comrtrission~Expires NoV. 8, NN
~ ~ >
l~
C3/12177/192/5Y
'4 ~
0
ATTACHMENT C