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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20211J1611999-08-17017 August 1999 Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210Q1941999-08-11011 August 1999 Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N1291999-08-0505 August 1999 Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20211B5381999-07-30030 July 1999 Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC ML20210J0741999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks ML20211C3251999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210D0911999-07-22022 July 1999 Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20210A5021999-07-20020 July 1999 Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20210B7651999-07-15015 July 1999 Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl ML20209G2081999-07-13013 July 1999 Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted ML20210A6311999-07-0606 July 1999 Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20211H8431999-06-23023 June 1999 Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl ML20196C6831999-06-21021 June 1999 Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701 ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J8271999-06-16016 June 1999 Ack Receipt of to Jackson,Chairman of NRC Re Environ Impacts of Increased Patuxtent River Complex Flight Operations on Ccnpp.Clarification & Correction of Listed Statement Found on Page Two,Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J6591999-06-16016 June 1999 Submits Proposed Alternative to Requirements of 10CFR50.55a(g)(4) (Automatic Compliance with Latest Approved Edition of ASME Code Every 120 Months).Proposal Will Apply Third ten-year ISI Interval,Scheduled to Begin 990701 ML20207F0201999-06-0101 June 1999 Forwards Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2, for NRC Review.Plan Satisfies Commitment Contained in Licensee to NRC 05000317/LER-1999-002, Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b)1999-05-28028 May 1999 Requests That Cover Page for LER 99-002,dtd 990525,be Corrected to Indicate Rept Is Submitted Per Requirements of 10CFR20.2201(b) ML20195B3751999-05-25025 May 1999 Forwards ECCS Codes & Methods Rept, as Required by 10CFR50.46(a)(3)(ii) ML20195B2521999-05-25025 May 1999 Submits Response to RAI Re LAR for Tube Repair Using Leak Limiting Alloy 800 Sleeves for Ccnpp,Units 1 & 2.Test Repts Encl ML20195B2271999-05-24024 May 1999 Forwards Certified Copy of Nuclear Liability Policy NF-216, Endorsement 128 ML20206U3051999-05-19019 May 1999 Submits Written Rept as Required follow-up to Verbal Rept Given to NRC Regional Administrator on 990419 of SG Tube Insps Conducted,Cause of Tube Degradation & Corrective Measures Taken as Result of Insp Findings ML20206U8281999-05-18018 May 1999 Forwards Missing Pages C-30,C-31,C-114 & C-115 from 990319 Response to NRC RAI, Wind Tunnel Modeling of Calvert Cliffs NPP Cpp Project 94-1040. Complete Copy of 1985 Rept, Wind Flows & Dispersion Conditions of Calvert Cliffs, Encl ML20212G9751999-05-12012 May 1999 Forwards Draft write-up Re OI 16 for F Grubelich to Consider ML20206K6921999-05-10010 May 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsements,In Compliance with 10CFR140.15(e).Without Encl ML20206K1711999-05-0707 May 1999 Informs That on 990430 Util Filed Encl Articles of Share Exchange with Maryland Dept of Assessments & Taxation to Form Holding Company,Constellation Energy Group,Inc (Ceg). CEG Is Parent Company of Bg&E ML20206C7521999-04-29029 April 1999 Provides Rept of Number of Tubes Plugged in Calvert Cliffs Unit 2 SGs During Recently Completed Isi,As Required by Calvert Cliffs Unit 1,TS 5.6.9.a ML20212G9891999-04-28028 April 1999 Forwards Current Draft Response to Ci 3.3.2.2-1 to Be Used as Example for OI Vs License Condition Vs Commitment Situation ML20206C7271999-04-28028 April 1999 Forwards Occupational Radiation Exposure Repts for 1998, as Required by Units 1 & 2 Tech Specs 5.6.1 & 6.1 of Isfsi. Repts Contain Tabulation of Number of Station,Util & Other Personnel Receiving Exposures Greater than 100 Mrem ML20206C7211999-04-27027 April 1999 Forwards Addl Info Which Is Being Made Available in Encl Licensed Operators Fitness for Duty Questionnaire.Encl Specifics of Personal Info Are Withheld,Per 10CFR2.790 ML20212G9851999-04-26026 April 1999 Provides Proposed Response to OI 4.1.3-1 for B Elliott to Consider ML20206U6691999-04-26026 April 1999 Advises That Documents Re Operation of Calvert Cliffs Nuclear Power Plant Should Be Addressed to Listed Natl Marine Fisheries Svc Office ML20205F8851999-04-0202 April 1999 Provides First Annual Amend to Bg&E License Renewal Application for Ccnpp,Units 1 & 2,as Required by 10CFR54 ML20205J0691999-04-0202 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20205G2971999-04-0101 April 1999 Requests That NRC Complete Review of Rev 0 to CENPD-396-P, Common Qualified Platform TR & Rev 0 to CE-CES-195-P, Software Program Manual for 'Common Q' Sys, by 990930 ML20205D7471999-03-30030 March 1999 Forwards Biennial Rept on Status of Decommissioning Funding, IAW 10CFR50.75(f)(1) ML20207G4391999-03-30030 March 1999 Responds to from Cl Miller,Requesting Assistance of FEMA in Addressing Concerns Received by NRC Involving Offsite Emergency Preparedness at Plant NPP ML20205C4091999-03-26026 March 1999 Submits Info Related to Scope,Risk Mgt & Summary of Risk for Performing Preventive Maintenance on P-13000-2 Unit Transformer Re License Amend 205 1999-09-28
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7471990-09-18018 September 1990 Discusses Response to Generic Ltr 88-17, Loss of Dhr. Development of Appropriate Tech Spec Changes for Reducing Cooling Flow Rate in Process.Changes Will Provide Increased Margin to Vortexing Conditions ML20059K1951990-09-18018 September 1990 Clarifies Auxiliary Feedwater Sys Commitments Concerning Ability of Sys to Prevent Total Loss of Feedwater Following Various Pipe Breaks & Component Failures ML20059H2811990-09-0707 September 1990 Forwards Rev 4 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program. Rev Creates Std Format for Action Plans Which States Scope, Deliverables & Overall Objectives of Action Plan ML20059F4761990-09-0707 September 1990 Forwards Rev 5 to Security Training & Qualification Plan.Rev Withheld ML20059H4241990-09-0707 September 1990 Forwards Performance Improvement Plan Implementation Program Schedule Status as of 900905 05000317/LER-1989-023, Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture1990-08-24024 August 1990 Advises That Licensee Plans to Complete Detailed Design for Automatic Isolation Sys Upgrade by 910401,per NRC Request for Schedule for Enhancement Implementation as Discussed in LER 89-23 Re Postulated Pipe Rupture ML20059B7481990-08-21021 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990 ML20058Q2211990-08-14014 August 1990 Forwards Performance Improvement Plan Implementation Program Schedule Status as of 900807.Synopsis of Activities Since Last Update & Updated List of Key Action Plan Info Also Encl ML20058L8811990-08-0101 August 1990 Withdraws License Amend Request Changing Tech Spec Pages 3/4 25a & 25b, RCS Pressure-Temp Limitations. Change Would Have Revised Min Reactor Vessel Flange bolt-up Temp from 70 F to 90 F ML20058L7271990-08-0101 August 1990 Forwards Plant Performance Improvement Plan Implementation Program Schedule Status as of 900724 ML20058L2151990-07-27027 July 1990 Responds to NRC Re Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80.Corrective Action: Evaluation of Battery Charger Determined That Provisions Adequately Verify Requirements of Tech Spec 4.8.2.3.2 ML20055H9241990-07-26026 July 1990 Forwards Decommissioning Plan for Calvert Cliffs Isfsi ML20055G9981990-07-20020 July 1990 Responds to NRC Re Generic Implications & Resolution of Control Element Assembly Failure at Plant on 900607.New Control Element Assemblies Ordered.Addl Response Will Be Submitted at Least 60 Days Prior to Restart ML20044B0401990-07-13013 July 1990 Forwards Rev 3 to Calvert Cliffs Nuclear Power Plant Performance Improvement Plan Implementation Program. Brief Summary of Changes Listed ML20055E0801990-07-0303 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-317/90-08 & 50-318/90-08.Corrective Actions:Instruction CCI-309B Re Control of Locked Valve Revised to Clarify Required Documentation and Verification of Locked Valves ML19298E2271990-06-29029 June 1990 Confirms That Work Intended to Resolve Unresolved Items & Incorporate Improvement Suggestions Completed,Per Insp Repts 50-317/90-04 & 50-318/90-04 ML20055D0311990-06-25025 June 1990 Submits Corrections to Commitments Re Hydrogen Analyzer Sys. Under Worst Case Condition,Hydrogen Recombiners Would Be Started Prior to Hydrogen Concentration Inside Containment Reaching 3.0% Hydrogen ML20043G1771990-06-12012 June 1990 Forwards Monthly Operating Repts for May 1990 for Calvert Cliffs Nuclear Power Plant Units 1 & 2 & Revised Operating Rept for Apr 1990 for Calvert Cliffs Unit 1 ML20043G5931990-06-0808 June 1990 Requests one-time Exemption from Requirement of 10CFR50.71(e) to Allow 3-month Extension to Schedule for Submitting 1990 Rev to Updated Fsar,Per NRC 1989 QA Audit & Insp Repts 50-317/89-27 & 50-318/89-28 Noting Weaknesses ML20043F7101990-06-0606 June 1990 Suppls 900330 Response to Station Blackout Rule (10CFR50.63).Two Addl Class 1E Diesel Generators Added to Reduce Required Coping Duration.Required Coping Duration Is 4 H for One Unit ML20043D7281990-06-0404 June 1990 Responds to NRC 900404 Ltr Re Weaknessess Noted in Maint Team Insp Repts 50-317/90-80 & 50-318/90-80.Efforts to Clean,Insulate & Paint Plant Areas to Improve Cleanliness Being Undertaken ML20043C9051990-05-31031 May 1990 Notifies of Relocation of Ofcs,Effective 900604.New Addresses & Telephone Numbers Listed ML20043C5971990-05-29029 May 1990 Forwards Startup Review Board Self-Assessment Rept:Apr 1990 Unit 1 Startup. Based on Assessment,Mgt Efforts Taken Through Performance Improvement Plan Appears Substantially on Track ML20043B9341990-05-25025 May 1990 Advises of Licensee Progress to Date Re Unresolved Item Noted in Inps Repts 50-317/90-04 & 50-318/90-04 & Identify Slippage Past 900601 Target Date.Completion Date Extended to 900701 ML20043B4691990-05-21021 May 1990 Reaffirms Licensee Intention to Submit Rept Re Deletion of Tech Spec 3/4.6.1.8, Containment Sys - Containment Vent Sys, Upon Receiving Notification That Vent Valves 1(2)-MOV-6900 & 1(2)-MOV-6901 Established ML20043A3381990-05-15015 May 1990 Responds to NRC 900409 Ltr Re Violations Noted in Insp Repts 50-317/90-01 & 50-318/90-01.Corrective Actions:Detailed & Specific Directions for Radiography Will Be Incorporated in Radiography Procedures within NDE Program ML20043A3321990-05-14014 May 1990 Responds to SALP Rept Dtd 900404 Covering Util Performance During 1989.Feedback Mechanisms Established to Improve Training & 10CFR50.59 Screening Procedure & Training Revised ML20042G3751990-05-10010 May 1990 Forwards Changes 1-3 to Rev 0 to Program Plan for Second Insp Interval for Calvert Cliffs Nuclear Plant,Units 1 & 2. Plan Revised to Include Volumetric & Surface Exams of Class 2 Piping Welds in Containment Spray & Shutdown Cooling Sys ML20042G6141990-05-0505 May 1990 Requests Regional Temporary Waiver of Compliance to Provide Relief from Provision of Limiting Condition for Operation of Tech Spec 3.4.10.1, Structural Integrity of ASME Code Class 1,2 & 3 Sys. ML20042G4581990-05-0404 May 1990 Responds to Request for Addl Info Concerning Tech Spec Amend Re Emergency Diesel Generators.Preventive Maint Procedures Prepared on 900411 & Final Approval Will Be Completed After Issuance of Amend ML20042F5771990-05-0404 May 1990 Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-317/90-80 & 50-318/90-80.Corrective Actions:Surveillance Test Procedure M-538-1 Revised to Include Verification of Alarm Function & Alarm Testing Reviewed ML20042F0101990-04-30030 April 1990 Forwards Update of Tables 1C,2A,2B,3A & Page 7 of Semiannual Effluent Release Rept for Second Half of 1989 & Table 3A for Second Half of 1988 & First Half of 1989.Update Includes Strontium Results for Fourth Quarter for Gaseous Releases ML20042E8271990-04-30030 April 1990 Forwards Rev 2 to Calvert Cliffs Performance Improvement Plan Implementation Program. Accountability Improvements, Engineering Planning & Sys Circles Action Plans Completed. New Sections to Rev Listed ML20042F0391990-04-19019 April 1990 Submits Initial Response to SALP Rept Dtd 900404.Licensee Devoted Substantial Senior Mgt Attention & Resources to Improving Facility Performance & Committed to Continue Efforts to Attain High Stds of Safety & Quality ML20012F5511990-04-0606 April 1990 Responds to NRC 900306 Ltr Re Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Corrective Actions:Operating Procedures Changed to Prohibit Testing of ECCS When in Solid Water Condition ML20012F2991990-04-0404 April 1990 Revises Scheduled Completion Date for Implementation of Computerized Trending of Surveillance Test Data,In Response to Special Team Insp Repts 50-317/89-200 & 50-318/89-200 from 900601 to 901228 ML20042D8101990-03-30030 March 1990 Forwards Supplemental Info,Clarifying Util 890414 Response to Station Blackout Rule Noting That Util Followed NUMAR-87-00 Methodology ML20012F0211990-03-29029 March 1990 Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-317/89-25.Corrective Actions:Plugging Error Identified & Correct Tube Plugged & Corrective Action Procedures Revised ML20012D3111990-03-19019 March 1990 Provides Followup Response to Violation Noted in Insp Repts 50-317/89-24 & 50-318/89-24.Corrective Actions:Radiation Safety Technicians Responsible for Safety Procedures Trained in Jan 1990 & Radwaste Scaling Factors Approved on 900201 ML20012D1871990-03-16016 March 1990 Discusses Readiness for Restart of Facility ML20012B9121990-03-0909 March 1990 Withdraws 891113 Request for Relief from ASME Code Section XI Requirements ML20012B9221990-03-0909 March 1990 Responds to NRC 900207 Ltr Re Violations Noted in Insp Repts 50-317/89-27 & 50-318/89-28.Corrective Actions:Demineralized Water & Chemicals Added to Steam Generators to Restore Chemical Concentrations to Required Specs ML20012B6111990-03-0707 March 1990 Responds to NRC 900229 Ltr Re Violations Noted in Readiness Assessment Team Insp Rept 50-317/89-81.Corrective Actions: Memo Issued re-emphasizing Importance of Mgt Controls & General Supervisor Counselled ML20012D7271990-03-0505 March 1990 Responds to Violations Noted in Insp Repts 50-317/90-03 & 50-318/90-03 on 900108-12.Corrective Actions:Medical Svcs Tested All Members of Nuclear Security Force for Glaucoma & field-of-vision Requirements ML20011F4251990-03-0101 March 1990 Forwards Page 4-9 of Rev 25 to Security Plan,Originally Submitted on 900228.Encl Withheld (Ref 10CFR73.21) ML20011F4491990-02-28028 February 1990 Forwards 1989 Steam Generator Insp Results Rept.Rept Includes Number & Extent of Tubes Examined,Imperfections Noted & Identity of Tubes Plugged.No Steam Generator Tube Exams Conducted on Unit 1 During 1989 ML20012A1481990-02-28028 February 1990 Forwards Rev 25 to Security Plan & Details of Changes Made by Rev.Encls Withheld (Ref 10CFR73.21) ML20012A1531990-02-28028 February 1990 Forwards Rev 11 to Safeguards Contingency Plan & Details of Changes Made by Rev.Encls Withheld (Ref 10CFR73.21) ML20011F4141990-02-27027 February 1990 Forwards Rev 2 to, Evacuation Time Estimates within Plume Exposure Pathway EPZ for Calvert Cliffs Nuclear Power Plant. Evacuation Time Estimates Updated to Reflect Population & Road Network Changes Since 1981 ML20012A2331990-02-26026 February 1990 Advises That Erosion/Corrosion Program Controlling Implementing Procedure 5.05, Secondary Sys Piping Erosion/ Corrosion Insp Program, Fully Implemented on 891229 1990-09-07
[Table view] |
Text
.
BALTIMORE GAS AND ELECTRIC COMPANY GAS AND ELECTRIC BUILDING ,
BALTIMONE, MARYLAND 21203 AnTHun E. LupeovALL.Jn-vice pass.oo ,
J q 11,lg Surate Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Subject:
Calvert Cliffs Nuclear Power Plant Units No. 1 & 2, Docket No. 50-317 & 50-313 Fire Protection Safety Evaluation Report and Amendments to Facility Operating License File: 013-261-0, L-037-F
Reference:
BCCL letter dated December 27, 1979 from Lundvall to Reid, same subject Gentlemen:
In accordan.:9 with my letter of December 27, 1979, enclosed please find forty (40) copies of the " Fire Hazards Analysis" for the Containment Interior. Also enclosed are forty (40) copies of revised pages to our sub-mittal of December 21, 1979.
Very'trul yours,
/
r ?"- _ l /
T_[f m _
f, Enclosure cc: J. A. Diddison, Esquire G. F. Trowbridge, Esquire '
- ,le ssrs. E. L. Conner, Jr. - NHC J. W. Brothers - Bechtel s
1766~29f B 0 0116 0 FC f,
229-1 ROOM NOS. 229 AND 230 - FIGURES 2 TIIROUGli 9 ROOM DESCRIPTION Containment Unit 1 - 230 Unit 2 - 229 The containment contains four divisions.of safety related cable and equipment and the following two divisions of safe shutdown equipment and its associated cabling:
- 1. RCP Seal Leakoff Valve 1-CV-506
- 2. Pressurizer Sample Valves 1-CV-5465, 1-CV-5466 and 1-CV-5467
- 3. Reactor Cold Leg Temperature 1-TE-ll5,1-TE-125,1-TE-lllY and 1-TE-121Y
- 4. Reactor Hot Leg Temperature 1-TE-lllX and 1-TE-121X
- 5. Charging Letdown Valves 1-CV-515 and 1-CV-516
- 6. Shutdown Cooling Return Isolation Valve 1-MOV 652
- 7. Pressurizer Heaters
- 8. Steam Generator Level 1-LT-1105, 1-L7-1111, 1-LT-1106 and 1-LT-ll21
- 9. Reactor Core Temperature
- 10. Pressurizer Level 1-LT-103,1-LT-110X and 1-LT-110Y
- 11. Pressurizer Pressure 1-PT-100X and 1-PT-100Y
- 12. Auxiliary Spray Line Valve 1-CV-517
- 13. Pressurizer Power Operated Release Val /es.1-ERV-402/1-MOV-403 and 1-ERV-404/1-MOV-405 ,
Pfl0POSEDMODIFICATIONS
- 1. A new Reactor Ci elant Pump oil collection system will be installed.
Reference the response to SER question 3.3.4, "RC Pump Lube Oil Collection System."
- 2. Fire detection devices will be installed in the electrical penetration areas and in the containment recirculation HVAC ducts.
- 3. For redundant safe shutdown raceway routed within five feet and not protected by physical barriers, such as concrete walls, one of the two raceways shall be wrapped in a rated fire resistive material.
SER QUESTIONS
- 1. Demonstrate the adequacy of separation between adjacent fire areas that are not separated by fire barriers (with protected openings and penetrations) of appropriate fire resistance.
Hesponse The containments are 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated structures with no possibility of fire spreading into or out of the area. Entry into the area is strictly controlled at all times.
176$ 292
229-2
- 2. Identify the minimum separation between the redundant cables (in trays or in conduits)/ equipment required for safe shutdown in each fire area.
Response
In lieu of separation between redundant safe shutdown cable, one of the two raceways will be wrapped in a rated fire resistive material.
The following lists safe shutdown equipment and their safe shutdown separation relationship:
- 1. RCP seal Leakoff Valve 1-CV-506 and Pressurizer Sample Valves 1-CV-5465, 1-CV-5466 and 1-CV-5467 - Redundant components are located outside the containment.
- 2. Reactor Cold Leg Temperature 1-TE-ll5, 1-TE-125, 1-TE-lllY and 1-TE-121Y and Reactor Hot Leg Temperature 1-TE-lllX and 1-TE-121X -
Redundant instruments are located remotely and separated by con-crete shielding.
- 3. Charging Letdown Valves 1-CV-515 and 1-rV-;'S - Valves are normally open but will fail safe in event of fire.
- 4. Shutdown Cooling Return Isolation Valve 1-MOV-652 - This valve is normally shut and is not required to change position immediately.
Manual valve operation can be accomplished following fire suppres-sion to reach cold shutdown.
- 5. Pressurizer Heaters and Pressurizer Power Operated Relief Valves 1-ERV-402/1-MOV-403 and 1-ERV-404/1-MOV-405 - These devices are enclosed and isolated from adjacent areas by concrete walls and the area is devoid of co'mbustible materials.
- 6. Steam Generator Level 1-LT-1105, 1-LT-llll, 1-LT-1106 and 1-LT-ll21 -
Redundant instrumentation is separated by 100 feet and concrete walls.
- 7. Reactor Core Temperature - In core instrumentation is run in conduit.
- 8. Pressurizer Level 1-LT-103, 1-LT-110X and 1-LT-110Y and Pressurizer Pressure 1-PT-100X and 1-PT-100Y - Redundant instrumentation is more than 10 feet apart, column / wall mounted, above grated floors and not exposed by combustible materials.
- 9. Auxiliary Spray Line Valve 1-CV-517 - This valve is normally shut and will fail closed.
- 3. Identify the largest fire that can be expected in each fire area based on the fixed combustibles in the area and transient combustibles which may be introduced into or moved through the area.
Response
Per the Fire Protection Program Evaluation, the fixed fire loading in the containment is approximately 16 minutes. Approximately 50% of the fire load is due to electrical cables in tray, the majority of which are located at elevation 45'-0" in the area of the electrical penetra-tions. The only credible fire would be one due to a fire involving the cables in tray. Cable tray initiated fires have been demonstrated by Sandia Laboratories Test Report, " Cable Tray Fire Tests" SAND-77-ll25C dated July,1977 to be slow propagating and are effectively contained within the initiated tray. Should a tray initiated fire occur, damage to only one division of safe shutdown cable is postulated since redundant raceways close enough to be affected by a single fire will be wrapped in a rated fire resistive material.
1766 293
229-3 The RCP lube oil comprises approximately 49% of the fire load with the remaining 17. being scattered miscellaneous material.
As discussed in the response to SER question 3.3.4, the RCP lube oil collection system will prevent a fire resulting from a lube oil release.
Transient combustibles can only be expected during plant shutdown as containment access is severely limited during reactor operation to operational inspections. Transient combustibles introduced during plant shutdown would be removed as a part of the final containment inspection prior to startup. Therefore, safe shutdown could not be jeopardized by transient combustibles.
- 4. Identify the worst damage that could result from such fire.
Response
The following safe shutdown cable / equipment could be damaged: CV-506; C V-54 6 5, CV-5466 and CV-5467; TE-ll5 or TE-125; TE-lllY or TE-121Y; TE-lllX or 121X; CV-515 or CV-516; LT-1105/LT-llll or LT-1106/LT-ll21; Pressurizer lleaters (A or B); LT-103, LT-110X or LT-110Y; PT-100X or PT-100Y; ERV-402/MOV-405 or ERV-404/MOV-403.
- 5. Demonstrate that such damage will not have an adverse effect on safe shutdown or cause excessive radioactive release to the environment.
Response
As identified in the responses to SLR 2 and 4 above, only one division of safe shutdown cable / equipment could be affected; therefore, safe shutdown of the plant is assured.
Since the prime purpose of the containment is to prevent the release of radiation to the environment, there would be no radiological consequences of a fire in these areas.
EVALUATION OF SER SECTION 5 MODIFICATIONS Refer to Section 5.19.6 of the SER.
- 1. Demonstrate the adequacy of cable / equipment separation in preserving safe shutdown.
Response
Refer to the response to SER question 2.
- 2. Install fire detection devices in areas which contain safety-related cables and/or equipment.
Response
Fire detection devices will be installed in the containment rceircula-tion HVAC ducts to provide whole area detection. Also in the vicinity-of the electrical penetration arcas which constitutes the only credible major fire load.
17166 294
229-4
- 3. Perform hose reach tests to ensure that all fire hazards can be reached by at least one effective hose stream.
Response
Ilose reach tests have been performed and all areas can be reached by at least one hose stream. See the response to SER question 3.1.21, "f.!anual llose Coverage."
l 1
176~6'295
3.1.12 3.1.12 Battery Room Ventilation (4.4.4, 5.11)
Telltales have been installed at the exhaust and supply air grills in each battery room and the air flow is being verified twice each shift.
Response
As indicated above in the SER, this item has been completed and is considered acceptable to the NRC staff as indicated in Section 4.4.4.
3.1.13* Emergency Communication (4.7)
Communication equipment will be provided which is capable of maintain-ing communication between the control room and all areas of the plant, including the interior of containment, considering possible damage due to a single fire.
Response
Existing plant communications systems include a page system and sound powered phone system which are capable of maintaining communications between the control room and all areas of the plant including the interior of the containment. A sound powered phone system will be installed to provide back-up communications from the control room, in the event of loss of normal communication during a fire. This system will consist of 13 remote sound powered phone jacks as shown on the ;
attached draft Riser Diagram. Jacks will be located as follows: j (1) Unit 1 and 2 Containments - 3 jacks each at El. 10'-0", El. 45'-0",
El. 69'-0" in vicinity of east stairway.
._, stairways AU-1 and AB 5 jacks each at El. (-)l5'-0", El. 5'-0",
El. 27'-0", El . 45 '-0", El . 69 '-0" at stairway entrances.
(3) Rooms 603 and 605 (Aux. Feed Pump Hooms - El. 12'-0") 1 jack each.
The system will be installed in such a way as to maintain adequate sepa-ration from existing communications facilities. East Electrical Pene-tration Rooms will be utilized for containment entrances to avoid a com-mon route in the west Penetration Room. No new cable will be routed through the cable spreading room. Five (5) circuits will be installed to minimize impairment of the remainder of the system due to a fire in any one area. New sound powered equipment will be compatible with the existing system. These modifications will be accomplished by June, 1930 subject to timely review approval by the NRC staff.
3.1.14* Hydronen Piping (5.4, 5.3, 5.9)
An excess flow stop valve will be installed in the line to the hydrogen supply to auxiliary building to automatically secure hydrogen to the building in the event of a piping system rupture.
Response
Design drawings and details will be furnished for NRC staff review prior to implementing the modifications described above in the SER.
Revised: 1/11/30 1766 296
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TA11LE l PAGE 1 0F 12 Pit 0 POSED PLANT MODIFICATIONS FOR FIHE PHOTECTION UPGHADE ItOOM NO. FIRE DETECTION FIltE SUPPHESSION OTi!ER MODIFICATIONS 100/103/116 Smoke Detection Sprinklers under 1. Wrap zC and zis conduits.
at Ceiling Trays except Room l i ti 2. Place sprinklers to cover entire floor area.
101/119 Smoke Detection None 1. Wrap ZC conduit.
at Ceiling 2. Add fire damper to ceiling and wall llVAC duet penetration.
- 3. Close blockouts between Itoom 118 and 119 and 101 and 102 with fire rated 3 hour stop.
- 4. Provide interlock to close motor operat.ed IIVAC dampers at ceiling and wal1 on acLuation of smoke detectors.
- 5. Close blockouts between Room lid, 119, 101, and 102 and the Corridors 100 and 103.
102/118 Smoke Detection Nonc 1. Same as 101/119.
at Ceiling I 103/116 See Hoom No. 100 104 Smoke Detection None 1. Wrap ZC conduit. g at Ceiling
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PAGE 2 OF 12 ItOOM NO. fille DETECTION FIIIE SUPPitESSION OTilER MODIFICATIONS 105/115 None Sprinklers at Ceiling 1. Provide curbs at entrance and between compartments.
- 2. Add f' ire damper in llVAC duct communicating with Itoom 106/113.
106/113 None Sprinklers at Ceiling None 107/114 Smoke Detection None None at Ceiling 108 Smoke Detection None None at Ceiling lo'J/112 None None None N
- p. llo Smoke Detection None None y at Celling u
O C- 111 Smoke Detection None None at Ceiling 113 See Itoom No. 106 l Itevised: 1/ll/do
PAGE 4 0F 12 H00M No. FIRE DETECTION FIltE SUPPitESSION OTilElt MODIFICATIONS 204/225 Smoke Detection Sprinklers under Trays 1. Wrap ZB and ZC raceway.
at Ceiling 205/226 None Sprinklers at Ceiling None 206/227 Smoke Detection None None l at Ceiling i 207 None None None 203 None None None 209 None None None 210 Smoke Detection None None at Ceiling Q
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PAGE 6 0F 12 It00M NO. FIltE DETECTION FIltE SUPPitESSION OTilEli MODIFICATIONS 223 None Sprinklers at Ceiling None 229/230 Flame Detection Nonc 1. L J rap redundant raceways.
- 2. Provide an itCP oil collection system.
I A/ lu/2A/2il Smoke Detection Automatic Sprinklers None at Ceiling (existing) 301/304/305/307 None None None 302/306/lC/2C Smoke Detection Italon 1301 1. Interlock 11alon with IIVAC.
at Ceiling total flooding 2. Actuation of llalon by detectors.
- 3. Electrically supervise all doors.
308 None None None 309/315 None Sprinklers at Ceiling None
'N Ch Ch itevised: 1/11/80 U
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s PAGE 7 0F 12 itOOM NO. FIltE DETECTION FIltE SUl'l'ItESSit)N OTilEH MODIFICATIONS 310/316 Smoke Detection None
- 1. Wrap ZH conduit.
at Ceiling 311/317 Smoke Detection None 1. Wrap two divisions of shutdown cable. \
at Ceiling 2. Add fire damper in IIVAC duct in the ceiling.
(existing) 3. Upgrade unrated blockouts to 3 hour.
312/318 Smoke Detection None None at Ceiling 313/411/ None None None 314/427 319/325 Smoke Detection None None at Ceiling 320 Smoke Detection None None at Ceiling Smoke Detection None None 322/324 at Ceiling s
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@ Itevised: 1/ll/d0 w
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PAGE 8 0F 12 HOOM NO. FIRE DETECTION . r'tE SUl*PitESSION OTilEH MODIFICATIONS 323 Smoke Detection None None (includes all at Ceiling of filter C ion Passage Area exchanger ros)
None None i
_325 _ Smoke Detection - - l 327/328 None None None (See Itesponse to SER Item 3.1.18.) l 400/401/402/ Smoke Detection None None 403/404/4_05/ (Existing) l 415/432/434/
435/436/437/
438 4 0 t> Smoke lletection IIalon 1301 1. Wrap ZA and ZC conduits.
(Existing) (Existing)
Additional Smoke Detection above Drop Cei1ing 407/430 Smoke Detect. ion Nonc 1. Wrap the redundant division of raceway.
at Ceiling (Existing) 408 Smoke Detection Sprinklers at Ceiling E 1. Wrap redundant conduit between P line and Above Trays in under Trays between P G M line.
Areas Between M lines P Line C M Line nevised: 1/11/d0 Ch CA u
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PAGE 9 OF 12 1100:4 NO. FIltE DETECTION FIltE SUPPitESSION OTilElt flODIFICATIONS 409/429 Smoke Detection Sprinklers under Trays 1. Wrap one division of shutdown cable. l at Ceiling (Existing) 41O None None None 1
412 None None None 414/423 Smoke Detection Sprinklers under Trays 1. Wrap one division of conduit.
at Ceiling (Existing) 416/421/422 Smoke Detection Preaction Sprinklers None at Ceiling at Ceiling (Existing)
(Existing) 417/418 None Sprinklers at Ceiiing None (Existing) 419/425/426 Smoke Detection Sprinklers at Ceiling 1. Wrap twa divisions of shutdown cable.
Above Trays in West of P I.ine and the Areas Adja- below Trays East of cent to the P Line
. Containments N itevised : 1/11/30 y
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l' AGE 11 dF 12 ItOOM NO. FIltE DETECTION FIltE SUI'l*ltESSI ON OTliElf MODIFICATIONS 501/502/503/ None None None 504/505/506/
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534/535 512 Smoke Detection None None at Ceiling 520 None None None 524/ 52ti Smol<c Detection Nonc 1. Class A Fire Doors.
at Ceiling 525/527 Smoke Detection None None at Ceiling 523/530/ None None None 533/536/ l 537 -
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