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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
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{{#Wiki_filter:REQUL ORY INFOR~)1ATION DISTRIBUTE BYBTEN (RIDB)'CCESSION NBR: 8607070388 DQC.DATE: 86/06/26 NOTARIZED:
YEB DOCKET 0 FACIL: 50-410 Nine Nile Point Nuclear Station>Unit 2>Niagara aloha 05000410 AUTH.NANE AUTHOR AFFILI ATION NANGAN>C.V.Niagav a Nohawl: Power Cov p.RECIP NANE RECIPIENT AFFILIATION ADENSAN>E.Q.BllR Pv object Div ectov ate 3
SUBJECT:
Forwards changes to FBAR Sections 9.5.1 8c 9A.3 v'e f iv e pv otection pv ogv'am cav bon dioxide sos>fov appl oYal.Changes v emove c ommi tment to use CQ2 in nonsa f et'-related av'eas.FBAR will be amended in future.lJ/three oversize encls.DISTRIBUTION CODE: B002D COPIES RECEIVED: LTR ENCL SI ZE: TITLE: I icensing Submittal:
Fire Protection NOTES: REC IP lENT ID CODE/MANE BWR ADTS 0/JR PD3 PD CQP IEB LTTR ENCL 1 1 RECIP I ENT ID CODE/NANE BWR PD3 LA HAUQHEY>N 01 COP IES LTTR ENCL 1 0 1 1 INTERNAL: ACRB ELD/HDB3 10 04 6 6 1 0 1 ADN/LFNB NRR STANQ>J RQNi 1 0 3 3 1 EXTERNAL LPDR NSIC 03 05 1'RC PDR 1 1 02 TOTAL NUNBER OF COPIES REQUIRED: LTTR 20 ENCL 17 0 S f1 il NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE.N,Y.13202/TELEPHONE (315)474-1511 t June 25, 1986 (NMP2L 0758)Ms.Elinor G.Adensam, Director BWR Project Directorate No.3 U.S.Nuclear Regulatory Commission 7920 Norfolk Avenue Washington, DC 20555
Dear Ms.Adensam:
Re: Nine Mile Point Unit 2 Docket No.50-410 The Nine Mile Point Unit 2 Final Safety Analysis Report describes the Fire Protection Program.Carbon dioxide systems are installed in both safety related and nonsafety related areas as described in Sections 9.5.1.and 9A.3.Carbon dioxide systems will comply with NFPA Standard 12 for safety related areas.Preoperational testing of the four C02 systems in safety related switchgear rooms is complete and accepted.The safety related rooms are poured in place concrete structures, while the nonsafety related rooms use masonary walls.During the testing of C02 systems in the safety related areas, as expected, a positive pressure occurred in the rooms in order to meet NFPA 12 concentrations.
These pressures may exceed the design allowable values for the nonsafety related masonary walls.At this time, we are evaluating these designs.The use of the C02 system in these nonsafety related areas will be under strict administrative controls under the direct control of the Station Shift Supervisor.
In the interim, we plan to use backup hose streams and portable extinguishers for protection of these nonsafety related areas.Niagara Mohawk is continuing to pursue a resolution; however, we anticipate that the design solution could go beyond fuel load.Based upon this schedule, a Final Safety Analysis change to Sections 9.5.1 and 9A.3 is provided in Attachment 1 for Nuclear Regulatory Commission review and approval.The change removes the commitment to use C02 in the nonsafety related areas, which is still consistent with the Standard Review Plan.Further, this change does not affect the Technical Specifications.
8b07070388 860Ei261 PDR ADOCK 05000410 F PDR
~~r 4 ,~*I II I, tl 4~~~I~~4 4 4 4, I 4 4 I r C II C~'4 I Ms.Elinor G.Adensam Page 2 As soon as the design solution is implemented and testing complete, the Final Safety Analysis Report will be amended to reflect the installation of the C02 protection for nonsafety related areas.Very truly yours, C.V.Manga Senior Vice President NLR:ja 1737G Attachment xc: R.A.Gramm, NRC Resident Inspector Project File (2) m II k f'I (f C 1 L~~
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation
)(Nine Mile Point Unit 2)Docket No.50-410 AFFIDAVIT C.V.Man an , being duly sworn, states that he is Senior Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto;and that all such documents are true and correct to the best of his knowledge, information and belief.Subscribed and sworn'o before me, a Notary Pgblic in and for the State of New York and County of a., this g5'ay of C 1986.Qlz5is Notary Public in and for a County, New York y Co"'iIiSlNfkMIIip-'" Hohe Public in the State of Hew Yorfr alified in Onondaga Co.No.47876&g.y Commission Extnrea March 30, 1R!c VdTZN 3H)YEN'kg AaY e:H lo ei:Q oQ ni aiHrQ gdcH VNT8'CD ail.o3 agabnaa0 nl b~l>>lcvg Ml,06 dowU touqQ o."~u;m:no3 yM ATTACHMENT 1 9.5.1.2.9 Carbon dioxide systems are provided for Category I equipment rooms and will comply with NFPA Standard 12.The low pressure carbon dioxide system consists of two 13-ton storage tanks (300 psig O'), refrigeration unit, valves, and piping that conveys C02 to fixed nozzles at individual hazards.Total flooding carbon dioxide systems are automatically actuated by cross-zoned smoke detectors.
Total flooding systems are provided for: 1.Standby switchgear rooms A and B and HPCS switchgear room in the control building.2.600V switchgear room in the reactor building.9A.3.6.5 C02 Suppression Systems (NFPA Standard 12)C02 systems are used in all safety related switchgear rooms.C02 systems comply with NFPA Standard 12 and the requirements of BTP CMEB 9.5-1, Section C.G.e.Disarming of C02 suppression systems will comply with the requirements of BTP CMEB 9.5-1, Section C.2.j.
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~~Nine Mile Point Unit 2 FSAR maximum allowable..In any case, cable tray water sprinkler'ystems are provided for these areas.In calculating fire loading for the diesel generator room, a fuel oil pipe rupture has been assumed with the entire contents of the fuel oil day tank spilled on the floor.It was also considered that all of the lube oil contained in the crankcase of the engine would leak out.These assumptions resulted in a fire loading of 2 hr 24 min, which is still less than the 3-hr walls that have been.provided.Automatic pre-action water sprinkler systems have been provided for the diesel generator building.The normal switchgear building also has a high fire loading, but it is J.ess than the 3-br fire walls that have been provide.d.
Fire loading for all other areas is approximately 2 hr or less.In spite of the low fire loading, 3-hr fire walls have been provided wherever separation is required or desirable.
9A.3.1.2.5 Qetailed Fire Hazards Analysis by Building The following sections provide the detailed fire hazards analysis and a summar'y of the effects of fires in fire zones.This summary shows that the fire protection system will provide adequate ability to detect, prevent, and suppress postulated fire outbreaks in and around the plant.9A.3.1.2.5.1 Standby Gas Treatment Building Introduction The standby gas treatment (SGT)building is adjacent to the reactor building.It houses the SGTS units, reactor building ventilation supply unit, and railroad access bay, all of which are separated from each other by 3-hr fire walls and floors.Construction of the SGT building is detailed in Section 3.8.4.1.9.
Safet-Related S stems The SGTS units are the only safety-related equipment in this building.Amendment 9A.3-8
Nine Mile Point Unit 2 FSAR During normal operation, the opening of one heat vent does not result in a release of radioactivity because the exhaust fan maintains the turbine building at a negative pressure.In the event of a fire with multiple operation of the heat vents, the design objectives of 10CFR100 would not be exceeded.Fire Detection and Su ression S stems Each area of the turbine building is protected by a zoned, early warning smoke detection system arranged to alarm locally and in the control room.Automatic wet-pipe sprinkler systems are provided for protection of general areas at el 250 ft 0 in and 277 ft 6 in.A system of six automatically operated foam water sprinkler systems (foam injection is manually controlled) covers the area under the turbine generator below el 306 ft 0 in.These systems would lay a blanket of foam on the floor under the turbine generator at el 277 ft 6 in to cover any accumulation of burning or unburned oil being discharged from a leak on the machine and to flow down the sides of the machine'nd lay a blanket of foam in the condenser pit, at el 239 ft 4 in.The foam water sprinkler systems utilize open foam water sprinkler heads spaced to achieve area coverage, and the water phase is actuated automatically by heat detectors.
The water supply to the systems is controlled by automatic flow control valves.The foam concentrate pump is manually started.Two equal capacity foam pumps are provided for the foam water sprinkler systems.One is on automatic standby.Two foam concentrate tanks are provided for foam water sprinker systems and foam hose reels.To assist manual firefighting around the turbine ge'nerator, the water hose stations in the vicinity of the unit are provided with piped foam concentrate so that either water or foam'streams are available at these stations.CO<hose reels are also provided.Carbon dioxide total-flooding systems are,'provided for the alternator exciter enclosure, and the lube oil reservoir.
Manual local application CO<systems are provided for turbine bearings and turbine lube oil piping.Manual water Amendment 9A.3-15
Nine Mile Point Unit 2 CESAR Manual water and CO~hose reels and portable extinguiehers are provided for backup protection.
Drains are discuss'ed in Section 9A.3.5.1.12.
9A.3.1, 2.5.9 Auxiliary Boiler Building Yntroductian The auxiliary boiler building is a single-story structure with metal siding walls, I.t houses two electric boilers which are utilized during startup and shutdown, It has no interior walls and contains only 5mall amounts of combu s tib le s, The ventilation system consists of outside aix'ntake louvers and power roof exhaust fans.Safet-Related E i ment The auxiliary boiler building does not contain any safety-related equipment.
Post Fire Anal sis There is no equipment in this building required for safe plant shutdown.Radioactive Release Anal sis A fire in the aukiliary boiler building will not result in excessive leakage of airborne radioactivity; t he desf gn objectives of 10CFR100 would not be exceeded.Pire Detection and Su ression The bui lding i s px ot ected by an early wax ning, smoke detection system axxanged to alarm and..annunciate in the control room.Since the fixe hazards analysis indicates a vexy low quantity of combustib'les and since the area is easily accessible for manual firefighting, fixed protection has not been provided.Mater hose xeels and portable extinguishers are provided for complete building coverage.O'A.3 22~Ofgty<igloo 0~~llf)1%'t I V+~~Sl~
'Nine Mile Point Unit 2 FSAR 9A.3.7.4 Plant Computer Room The plant computer is not safety related;it is not required to shut down the reactor or limit the~release of radioactivity to the environment.
The computer room is located within the control room pressure boundary on the relay room elevation.
The computer room walls have glass panels and are not fire rated.The relay room elevation of the control room pressure boundary is separated from all other areas by 3-hr barriers.A smoke detection system that alarms in the control room and an automatic total-flooding Halon suppression system have been provided in the computer room.Manual COz and water hose reels and portable extinguishers are available for backup.9A.3.7.5 Switchgear Rooms Rooms with safety re'lated switchgear are protected with automatic total-flooding-COz extinguishing systems.Manual COz and water hose reels and portable extinguishers are available for backup protection.
Detection systems annunciate in the control room and alarm locally, Three-hour walls separate switchgear rooms from each other and from the remainder of the plant.Manually actuated smoke removal capability is provided for normal switchgear building and the control building switchgear rooms.For further details, refer to Section 9.4.Smoke removal.capability would be provided through the use of portable fans if required for other switchgear rooms.9A.3.7.6 Remote Safety-Related Panels Unit 2 has two remote shutdown rooms separated from each other and other plant areas by 3-hr barriers.An automatic fire detection system annunciates in the control room and alarms locally.;Manual COz and water hose reels and portable extinguishers have been provided outside this room.9A'.3.7.7 Safety-Related Battery Rooms Battery rooms are separated from each other and from the remainder of the plant by 3-hr fire walls, which are in excess of the fire load calculated
=in the fire hazards analysis.All penetrations have a 3-hr rating.Separate ventilation systems have been provided for battery rooms to limit hydrogen buildup to 2 percent maximum.Fan failure is annunciated in the control room.Ross of flow initiates the redundant fan and prints out on the computer.Amendment 9A.3-56 0 4 Nine Nile Point Vnit 2 PSAR TABLE 9A.3-6 THNBINE BBILDING Figure Nom 9A.3-6 FA 84 Pire Area (FA)or Pire Sub Area (FSA)Number 740 XL Pire Zone El 277r-6<<Turbine building normal switchgear room west Area 1, 720 safety-Related Equipment in Area None Name Nisc eguip Cable trays Insul.Insul.706 25,346 Fire Hazard Combus-Quantitv tible Lb Gal Btu/Lb 12,000 12, 000 Total Btu (thousands'I 0, 472 304 152 L=-312, 624 Fire Loading Pire Barrier 8eq u ired 220, 370 2.3 hr Detection Svstem Smoke detection Crer S zoned Extinguishing System 9A.3-6 FA 83 726 XL El 277'-6>>Turbine building normal switchgear room east 2, 300 None Nisc equip Notor contcol centers Cable trays Insul.Fiber.Insul.979 402 48,010 12,000 10, 000 12,000 11,740 7,236 576 120 595, 104 258,740 3.2 hr Smoke detection ccoss-zoned 9A 3-6 FA 50 725 NZ El 288'-6>>Ventilation coom 5, 160 None Bise equip Motors l'able l ra y" Insu1.Insul.lnsul..156 36 10,457 12,000 10,000 12, 000 1, 072 360 125 rl04 L.127, 716 24,752 19 min Smoko detectiqn ,9A.3-6 FA 50 9A.3-6 FA 50 9A.3-6 FA 50 722 NZ 721 NZ 723HZ (A)724HZ (8)7 25NZ (C)El 277'-6>>Condensate demin-eralizer El 280'-6<<Off-gas room El 277 r-6>>Heater bay A room (similar for heater hays 8 and C)2,345 None 4,050 4,050 4050 Ncne 4,840 None Notors Cable trays Notors Bise equip Cable trays Notocs Cable trays Insul.Insul.Insul.Insul.Insul.Insul.Insul.72 6,372 3 208 5r062 1 4,152 10,000 12,000 10, 000 12, 000 12,000 10, 000 12,000 30 2,496 60 744 63, 270 10 49 824 49,034 720 76 464 L-77, 104 15, 947 12 min 26,900 20 min 12,3QQ 10 min Smoke detection smoke detoction smoke detection 1 of 5 Nine Nile Point Unit 2 PSAR TABLE 9A.3-9 (Cont)Figure No.Fire Area (Fh)or Fire Sub brea (FSAB)Pire Zone Area Name Safety-Belated Equipment in Area<<v Name Combus-tible Fire Hazard Ouantitv Lb Gal Btu/Lb Total Btus (thousands'I Fire Loading fB~tu ftvL Fire Barrier Bequired Detection System Ertinguj shing Svstem 9A.3-7 PA 59 951 NM El 309'-0" 6, 535 Truck loading 6 MSS storage None Motors Insul.10 10,000 100 15 Negli gi ble Smoke detection Automatic sprinkler system 9A.3-5 PA 70 905 NM El 261'u Decon area 6 dirty vorkshop 4,750 None Motors Insul.10,000 20 4 Negligible Smoke detect io n Automatic sprinkler system 9A.3-6 PA 70 395 XL El 279'-0" Radvaste svitch-gear room 2, 250 None Cables Insul.8436 12,000 101232 44992 34 min Smoke detection 9A.3-6 PA 70 390 XG 8 El 279~-Ou 907 NZ Badvaste control room and 2,500 None Cables Insul.10350 12,000 124200 49680 38 min Smoke Total floodlnn detection Union 9A.3-7 FA 70 903 NZ El 306'Ou Decon bldg HVAC equipment room 4,750 None Misc equip Insul.21 10, 000 210 Negligible Smoke detection 9 A.3-6 PA 58 904 NZ El 287'u LMS evaporators 650 None No combus-tibles Smoke detection)TI 5LPERmaZ ,CABD Amendment 3 of 3 Nine Nile Point Unit 2 FSAR TABLE 9A.3-10 NORNAL SMITCHGEAR BUILDING Figure No.9 A.3-4 FA 51 Pire Area (PA)or Pire Sub Area gFSA)Number Pire Zone Area Name 601 XL El 237',715 General area vest Safety-Belated Equipment in Area None Name N isc.equip.Cable trays Combus-tible Insul.Insul.Fire Hazard Ouantitv Lh Gal 797 24, 281 Btu/Lb 12,000 12, 000 Total Btu tthousandsl 9, 564 291 372 L 300,936 110,842 Fire Loading gBt~uft~z Pire Barrier Required fhrgmin 1.4 hp Detection System Smoke detection cross-zoned Extinguishing S stem I 9A 3-4 PA 52 9 A-3-4 FA 53 603 NZ El 237'-0<<1A battery room 830.None 602 XL El 2371 0<<4,590 None General area east Cable trays Nisc.equip.Notors Batteries Cable trays In sul.Insul.Insul.Styrene Insul.39,838 341 7 1,964 4,773 12,000 12, 000 12, 000 18,000 12,000 478,056 4,092 70 482,218 35,352 57 276 92,628 105,060 111,600 1.3 hr 1.4 hr Smoke detection cross-zoned Smoke detection 9A 3-4 FA 53 603 NZ El 237'-0<<18 battery room 830 None Batteries Cable trays Styren e Insul.1,964 5,867 18,000 12, 000 35,352 70 404-L 105,756 127,420 1.6 hr Smoke detection 9A.3-4 FA 53 603 NZ El 2371 0<<Room 4A 220 None Cable trays Insul.1,736 12,000 20,832 94,695 1.2 hr Smoke detectxon 9A.3-4 FA 53 9A 35 PA 78 9A.3-5 PA 79 603 NZ El 237'-0<<Room 4B 220 None 613 XL El 261'-0<<4, 590 None General area east 612 XL El 261'-0<<4,820 None General area vest Cable trays Bise.equip.Cable trays Notor control centers Bise.equip.Notcr control centers Cable trays Insul.Insul.Insul.Piher.Insul.Fiber.Insul.1,736 6,522 58,870 233 4,315 297 58,053 12,000 12, 000 782,264 706, 440 18,000 194 L 788,898 12, 000 51, 780 18,000 12, 000 5, 346 696 636 753, 762 12,000 20,832 94,695 1.2 hr 163,675 2.1 hr 164,220 2.1 hr Saoke detection Smoke detection cross-zoned Smoke detection cross-zoned Total flooding COz Total flooding~COx Amendment 1 of 2~gg-c33}}