|
---|
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 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 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 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 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) 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 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 ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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 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 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) 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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 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) 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 ML20195B3751999-05-25025 May 1999 Forwards ECCS Codes & Methods Rept, as Required by 10CFR50.46(a)(3)(ii) 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 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 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 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. 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 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 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 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 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 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 ML20012B9121990-03-0909 March 1990 Withdraws 891113 Request for Relief from ASME Code Section XI Requirements 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
._. .. . . .
jp l DAl.TiMORE GAS AND ELECTRIC CH ARLES CENTER . P. O. BOX 1476. BALTIMOR E, M/sRYLAND 21203 Gtonot RitL v,p ,, January 23, 1990 noussa tunuo, ooo .o...s.
U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No.1; Docket Nos. 50-317 Request for Additional Information - Technical Specification Change to Suonort ilPSI Pumo Operability
REFERENCE:
(a) Letter from G. C. Creel to Document Control Desk, dated December 20, 1989, same subject (b) Letter from D. G. Mcdonald (NRC) to G. C. Creel (BG&E), dated January 22, 1990, same subject Gentlemen:
We are providing additional clarifying inforc..ation to support the license amendment request previously submitted (Reference (a)). A request for information was made on January 22,1990 (Reference (b)). The information provided in this response does not change any of the conclusions presented in Reference (a) with respect to the significant har.ards analysis.
Should you hate any further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, d
GCC/ PSF /db ,
Attachment I O
L d 0' lER'48Mesegggc,, e D e
\\ .
\: [ ]
Document Control Desk January 23, 1990 Page 2 cc: D. A. Brune, Esquire J. E. Silberg. Esquire R. A.Caprn.NRC D. G. Mcdonald, Jr., NRC W. T. Russell, NRC J. E. Beall, NRC T. Magette, DNR
A'ITACHMENT (1)
Question:
- 1. In gour LOCA evaluation during Mode 3 with reactor coolant temperature below 350 F, you have assumed that the fission product decay heat is based on i10 percent of 1971 ANS proposed standard. It is the staff's. position that the fission product decay heat following a LOCA shall be based on 120 percent of 1971 ANS proposed standard per the requirements of 10 CFR 50, Appendix K.
Provide the results of your evaluation using this corrected assumption.
Response
- 1. Using a fission product decay heat value of 120% results in greater than 18 minutes available for operator action.
Question:
- 2. Provide a discussion of the consequences of a SBLOCA during Mode 3 with reactor temperature below 350 F and the IIPSI pumps placed in PULL-TO-LOCK. Include the following:
(a) The time available for operator action to initiate liPSI pumps following identification of an SBLOCA. Describe the actions needed to manually initiate 11 PSI pumps.
(b) Describe the procedures available to operators for the above postulated SBLOCA. Discuss the time assumed between the initiation of the event and positive event identification.
Response
- 2. (a) Dased on the analysis performed for Response 1, there are at least 18 minutes available for operator action. To manually initiate a llPSI pump, the handswitch must be turned from its
- pull-to-lock" setting to its normal (auto) position.
The operator would follow his procedure to establish flow by taking the appropriate action at the control panel. This involves:
- verifying the indicated flow path for the selected liPSI pump (including a verification that the loop isolation valves are shut)
- starting the selected liPSI pump (using the pump handswitch; taking it to the ' start" position -- spring return to center)
- throttling open IIPSI header loop isolation MOV's as necessary to control flow to maintain proper pressure, pressurizer level, and subcooling ATTACHMENT (1)
(b) If a SBLOCA were to occur, the operators would use Abnormal Operating Procedure 2-A, " Excessive Reactor Ceolant Leakage" This procedure addresses a Minor Leak, a Major Leak and a Loss of Coolant in Modes 3, 4, 5, 6. The goal of this procedure is to address a loss of coolant and ensure the reactor vessel is not subject to an LTOP event. The procedure cautions the operator to prevent RCS pressure from exceeding 360 psia whenever the RCS temperature is less than 330 F. A copy of the applienble section of the procedure is attached.
This procedure is a symptom based procedure, that is, it addresses the symptoms of an event and does not follow a strict time line. There are so many variables in dealing with a SBLOCA, that the time available between the initiation of the event and its identification varies with each scenario. The minimum time available for operator action calculated above (18 minutes) assumes a large pipe break and is the minimum time for all scenarios. For smaller pipe breaks, the time available for operator action becomes longer. With a SBLOCA, the llPSI pump is throttled to prevent exceeding the 360 psia pressure limit and, if proper subevoling can be maintained, the system pressure will be reduced to allow use of other. injection sources that would not challenge LTOP (containment spray pumps and/or low pressure safety injection).
Question:
3: Discuss the consequences of manual startup of 11 PSI pumps during Mode 3 relativt to LTOP concerns.
Response
- 3. A Technical Specification change will be submitted by January 31, 1990 to address the use of a llPSI pump when in LTOP conditions. The Technical Specification will require that a HPSI pump be throttled in order to preclude an overpressurization event whenever used while in LTOP conditions or alternatively that an adequate vent be available. The Technical Specification will also describe the condition of the HPSI pumps whenever the Unit is in an LTOP condition, i.e., two pumps with their breakers racked out and the remaining pump in pull-to-lock. The consequence of violating these proposed Technical Specification provisions is' negligible as long as the remaining LTOP controls are in place, (two PORVs or an adequate vent).
i
. /
( .. l
. CCI-10lM ATTACHMENT (2), Page 1 of 4 PROCEDURE CHANGE REPORT
- 1. Date 1-18 90- l
- 2. Procedure Number /Name AOP-2A Rev. # 9
- 3. Change Log Sequence f 90-1028
- 1) Solit Response for major leaks into 2 j
- 4. Description of Change sections: Major leak in Modes 1 and 2. and Major Leak in Modes 3.4.5. l and 6. 2) Added oaraoraoh to Discussion about the LTOP concerns. i
- 5. Reason for Change 11213) Add accrooriate resoonses for LOCAs into l the procedure. and ensure the operators are aware of and have the procedures for LTOP concerns.
7
- 6. Originated By Wilson Date 12-y-89
- 7. Approvals Required:
(1 Plant Management 1 or 2) _L., (one SS/SRO ?) Yes _L No j Assistant General (Supervisor - QC Yes No X Pre Implementation review by POSRC Yes JL. No Field Change (14 day review) Yes No X ]
- 5) Manager - CCNPPD Yes X No
- 6) General Supervisor (or alternate) Yes No X '
- 8. REVIEWS AND APPROVALS (1) Plant Management Staff D Date e- <e- 9o (2) Plant Management Staff b_.,a fhNJ" Date 8 9a NSS/SROifrequkred)
AGS-QC (or alternate) Date l
(Hold Point Changes Only)
POSRC Meeting Number 90 - O lt Date l-2o -90 Manager - CCNPPD [MD lbM Date 1 4t-60 (FOR PROCEDURE DEVELOPMENT USE ONLY) ,
- 9. Recommended Action .
No change to master ( ) Required reading (OPS Only) ,
X Enter in the master copy Other LExplain in(Remarks)
- 10. Evaluated By % wt 10ld Date I-19 -9 0
- 11. EnteredintomasYercopy,by Date ,
- 12. Remarks:
THIS FORM 5 $1 BE DELIVERED TO THE RESPONSIBLE PROCEDURES GROUP / PERSON WITHIN QE WORKING DAY.
9 es
- CCI-10lM _
ATTACHMENT (2), Page 1 of 4 PROCEDURE CHANGE REPORT Proc # A0P-PA Revision # 9 Date: 1-18-90 Change Log Seq.90-1028 ,
4a. (Cont.) Description of Change: 3) Divided the Response for a Maior Leak in Modes 3.4.5. and 6 into 2 sections: RCS temperature areater 0
than 3500F. and RCS temoerature less than 350 F. .
l 1
i I
1 I
I 1
Sa, (Cont.) Reason for Change s
)
e
~
. A0P-2A Rev. 9 Page 2 LIST OF EFFECTIVE PAGES PAGE NUMBER _ REVISION 1-30 9 ATTACHMENT BEylS1QN <
1, Page 1 9 2, Pages 1-2 9 3, Pages 1-2 9 4, Pages 1-2 9 1
4
A0P-1A !
Rev. 9 -
Page 3 i LIST OF EFFECTIVE _ CHANGES i
i PAGE NUMBER CHANGE RLE0RT NUMBER 4 90 1028 5 88-1241, 90 1028 i 6 88-1241 !
7 89-1330, 90-1028 I
8 89-1330 9 88 1241, 89-1330 !
10 28 90-1028 .,
ATTACHMENT
- 1. Page 1 68-1241 '
2, Page 1 86-159 2, Page 2 86-159 ,
3 Page 1 88-1105, 88-1241 3, Page 2 88-1241 !
4, Page 1 SS-1241 -
4, Page 2 86-159 i
i r
i 6
6 f
P 4
i i
I j
~
I
. A0P 2A l Rev. 9 Page 4 !
l TABLE OF CONTENTS l 1
l IITLE EAE l i
J. DISCUSSIDW ... . . . . . . . . . . . . . . . . . . . . . . . . . 5 !
- 11. INDICAT10NS . . . . . . . . . . . . . . . . . . . . . . . . . .. 5 j
III. RESPONSE FOR A MAJOR LEAK IN MODES 1 AND 2 . . . . . . . . . . . 7 i oo IV. RESPONSE FOR A MAJOR LEAK IN MODES 3,4,5,6 . . . . . . . . . . . . 10 l BJ. ,
53 l RESPONSE IN MODE 3 W!TH RCS TEMPERATURE GREATER THAN 350'F . 10 .
Ek i RESPONSE WITit RCS TEMPEkATURE LESS THAN 350'F ........ 13 ;
V. RESPONSE FOR A MINOR LEAK ................... 28 j 1
i 1
1 i
I l
i I
)
1 I
1 i
l I
l I
i
. _. _ _ . _-__ _ _ ~ - . . _ . _ _ _ _ _ _ _ _
l
~
, A0P-2A Rev. 9 !
Page 10 ;
- 3. Implement ERPIP 3.0.
- 4. Enter loss of letdown and/or charging in the plant transient log as applicable. j l
IV. ELSPONSE FOR A MAJOR LEAK IN MODES 3.4.5.6 f
(One charging pump unable to maintain Pressurizer Level with minimum letdown flow.)
A. Response in Mode 3 with RCS Temoerature areater than 350 0F1
- 1. JE RCS heatup/cooldown in progress, 110 stop the heatup/cooldown and maintain RCS temperature. l
- 2. Verify charging pumps are maintaining Pressurizer Level: i
- a. Start available charging pump (s), as necessary, to maintain or attempt to maintain Pressurizer Level.
- b. Initiate makeup to the VCT as required.
- 3. Attempt to isolate the leak:
- a. Shut Letdown Isolation Valves:
CVC-515-CV CVC-516 CV
- b. Shut RCS Sample Isolation, PS-5464-CV.
- c. Shut Reactor Vessel Vent Valves: ,
RC-103-SV RC-104-SV
- d. Shut Pressurizer Vent Valves:
RC-105-SV RC-106-SV v., . - - , .- wr-e - a=~- -- ,- ------- --- --- -
- 3. -
. A0P-2A 1 Rev. 9 !
Page 11 I
- e. If PORV leakage is indicated by:
o High Quench Tank parameters. 1 e !
"a o High PORV discharge piping temperature, computer l points T107 and T108.
o Abnormal Acoustic Monitor indication.
1 HEN shut the appropriate PORV Block Valve: )1 RC-403 MOV RC-405 MOV ;
- f. Determine if leak is on the Charging Header, as ;
indicated by Charging Header Pressure being less than RCS Pressure.
- g. IE leak is on the Charging Header, ;
IHIH:
- 1) Secure the Charging Pumps.
2)' Realign charging to the Auxiliary HPSI Header per Attachment (1) of this procedure,
- 4. Determine if leak has been isolated: ,
t
- HQIE - t If Pressurizer Pressure is Blocked, during heatup or cooldown, SIAS will only actuate via Cntmt Pressure or Manual Pushbutton. ;
- a. IE leak has not been isolated alg) Pressurizer Pressure is decreasing rapidly, IllEH verify SIAS actuation.
P i
-d
AOP-2A Rev. 9 Page 12
. ggg -
If E0P-5 or E0P-6 is entered due to the conditions h
$ in step 4.b or c below E0P-0 need not be implemented.
- b. If leak has not been isolated AM) is not within the capacity of the Charging Pumps
- 85) S/G tube leakage is not indicated, IEH:
- 1) Start 11(21) and 13(23) HPSI Pumps.
- 2) Open Main and Aux HPSI Header Isolation MOVs:-
SI-616-MOV SI-617-MOV SI-626 MOV SI-627 MOV SI 636 MOV SI-637-MOV SI-646-MOV SI-647-MOV
- 3) Implement E0P-5.
- c. IE leak has not been isolated 85) S/G tube leakt.ge is indicated, by increasing radiation levels on either of the following:
o Condenser Off-Gas RMS, RI-1752, o S/G B/D RMS, RI-4014 and/or RI-4095, i IMH:
- 1) Start 11(21) and 13(23) HPSI Pumps, i
~
AOP-2A Rev. 9 Page 13
, 2) Open Main and Aux HPSI Header Isolation MOVs:
E y SI-616-MOV SI-617-MOV e
SI-626-MOV SI-627-MOV SI-636-MOV SI-637-MOV r
SI-646-MOV SI 647 MOV !
- 3) Implement E0P-6.
- d. IE leak has been isolated DB is within the capacity of the operable Charging Pumps, as indicated by increasing Pretturizer level and CET subcooled margin greater than 300 F, 1113 establish Pressurizer Level at approximately 160 inches and determine if operation may continue or if raoldown is necessary for repairs. Implement OP 5, as applicable.
B. Response with RCS lemoerature less than 350 0F.
- 1. IE RCS heatup or cooldown is in progress, 11101 stop the heatup/cooldown and maintain RCS temperature.
- 2. Start available Charging, Pumps, as necessary, to maintain Pressurizer Level.
- 3. Makeup to the VCT, maintaining required blend, per 01-2B.
- 4. Attempt to isolate the leak,as follows:
- a. Shut Letdown Isolation Valves:
CVC-515 CV CVC-516-CV
__________________j
AOP-2A 1 Rev. 9 Page 14 l l
- b. Shut RCS Sample Isolation, PS-5464-CV. l 7 c. Shut Reactor Vessel Vent Valves:
g RC-103-SV )
RC-104-SV l
- d. Shut Pressurizer Vent Valves:
RC-105-SV i RC-106-SV .
- e. 1E PORV leakage is indicated by:
o High Quench Tank parameters. 1 o High PORV discharge piping temperature, computer 1
points T107 and T108. !
c' Abnormal Acoustic Monitor indication. l IdB shut the appropriate PORY Block Valve:
RC-403-MOV :
RC-405-MOV I
- f. Determine if leak is on- the Charging Header, as indicated by Charging Header Pressure being less than i
RCS Pressure. *
- g. If leak is on the Charging Header, 1 DH: 1
- 1) Secure the Charging Pumps.
- 2) Realign charging to the Auxiliary HPSI Header per ! 1
. Attachment (1) of this procedure.
i J
l i
I j
. AOP-2A :
Rev. 9 ;
Page 15 i y 5. IE leak has ben isolated QB is within the capacity of the l operable Charging Pumps, as indicated by increasing i Pressurizer Level, ;
1113 establish Pressurizer Level at approximately 160 inches and implement the appropriate Operating Procedure for the desired plant conditions. ;
- 6. IE leak has not been isolated, It!G monitor for S/G tube leakage: !
- a. Increasing radiation levels on either of the following: -
o Condenser Off-Gas RMS, RI-1752. !
r o S/G B/D RMS, RI-4014 and/or RI-4095,
- b. Unexplained increase in S/G 1evel.
- 7. IE S/G tube leakage is indicated, M proceed to step 11,
- 8. 1E the leak was not isolated, jglI diagnosed as S/G tube leakage, ;
alg} SDC is in operation l M stop the running LPSI pump (s), placing their H/S's in PTL, A!g) shut SDC Return, Isolation Valves, SI-651-MOV and-SI-652-MOV.
- 9. lE securing SDC isolates the leak, j IllG implement LOSS OF SHUTDOWN COOLING CAPABILITY, A0P-38.
- 10. IE securing SDC does not isolate the leak ;
At(Q RCS Level is maintained above the middle of the Hot Leg, ItiG re-initiate SDC, as follows:
- a. Shut SDC temperature control valve SI-657-CV.
AOP-2A :
Rev. 9 Page 16 e l E Place SDC flow control valve, SI-306-CV, in manual with I 7 b.
1 g
95% output signal (5% open position),
- c. Open SDC Return Isolation Valves, SI-651-MOV and l I
SI-652 MOV.
e
- d. Check open LPS! Loop Isolation Valves:
SI-615 MOV 4 i
SI-625 MOV SI 635 MOV SI-645 MOV .
- e. Start LPSI pump. Very slowly increase open signal on f FIC-306 until 3000 GPM is achieved and place FIC-306 in l automatic.
- f. Adjust SDC temperature control valve SI-657-CV as ,
necessary to maintain RCS temperature. .
- 11. E Fressurizer level cannot be controlled using the Charging '
I Pumps, QB the REACTOR VESSEL WATER LEVEL LOW alarm annunciates, ,
E initiate Safety Injection flow and refer to the ERPIP:
- a. E RCS pressure less than 225 PSIA, 1
1 M proceed to step ll.c.
I'
- b. H RCS Pressure is greater than 225 PSIA, E initiate High Pressure Safety Injection:
- 1) Stop any running RCPs.
- 2) Open or check open RWT Outlet Valve for the operable HPSI Pump, SI-4142-MOV or SI-4143-MOV.
l
- 3) Establish HPSI flowpath through the Main or Aux '
HPSI Header:
---eut e - - _a__-_ . - _ _ _ .--m_ _u__-+_______
~
. A0P-2A Rev. 9 Page 17 a) Open the HPSI Hdr Valve for the desired flowpath:
[R Main HPSI Hdr SI-654-MOV Aux HPSI Hdr SI 656 MOV b) Align HPSI Hdr Crossconnect Valves for selected HPSI PP:
Pf lip _SJ_tidt SI-653-MOV SI 65S-MOV 11(21) Main 0)en 0)en 11(21) Aux Slut Slut 12(22 Main 0)en Shut 12(22) Aux Slut Open 13(23) Main Shut Shut 13(23) Aux Open Open c) Verify Loop Isolation Valves, for the desired HPSI Hdr flowpath, are Shut:
tiain aux SI-616-MOV SI-617-MOV SI-626-MOV SI-627-MOV SI 636-MOV- SI-637-MOV SI-646 MOV SI-647-MOV
- 4) Open or check open the Mini-flow return to RWT:
SI-659-MOV SI-660-MOV
- 5) Start the selected HPSI PP.
- l
. A0P 2A l Rev. 9 i Page 18 a, -CMLLGll-When RCS temperature is less than 330'F, RCS Pressure I shall not exceed 360 PSIA, due to LTOP considerations.
-CAUTION-If Shutdown Cooling is on service, do not allow RCS j I
Pressure to exceed 270 PSIA to ensure the SDC Return Isolation Valves do not shut. ,
- 5) Throttle open the HPSI Hdr Loop Isolation MOVs to maintain all of the following: ;
o Pressurizer pressure less than 360 PSIA, )
(270 PSIA if Shutdown Cooling is on service). l o Pressurizer Level greater than 155 inches.
o At least 30 0F subcooling, as indicated by i . CETs.
- 6) 1E RCPs secured, ;
MlD Shutdown Cooling was 311 in service, IEli confirm Natural Circulation:
0 o Thot minus Tcold between 10 and 50 F.
o Tcold constant or decreasing.
L o Thot constant or decreasing.
o CET temperatures consistent with Tho.t.
o Steaming rate affects primary temperatures.
t'
- A0P-2A Rev. 9 i Page 19
{
$ 7) 1E the following conditions can be maintained:
o At least 30 0f subcooling, as indicated by ;
1 CETs, i o Pressurizer level greater than 155 inches. i o At least one S/G, or Shutdown Cooling available for heat removal. j o RVLMS indicates the core is covered. !
E depressurize the RCS to allow using a LPSI or !
Containment Spray Pump for inventory control: l a) 1E Auxiliary Spray is available AND the Pressurizer is not solid, J l
M initiate Auxiliary Spray:
i) Record temperature differential ]
1 between Pressurizer and Regenerative Heat Exchanger outlet.
ii) Open Auxiliary Spray Valve, CVC-517-CV.
iii) Shut loop Charging Valves: '
CVC-518 CV ,
l CVC-519-CV iv) Maintain Pressurizer cooldown rate 0
less than 200 F/h.
- b) If Auxiliary Spray is not available I
DB the Pressurizer is solid, E slowly throttle shut the HPSI Loop Isolation MOVs to allow the RCS to ,
depressurize.
[
- AOP-2A i Rev. 9 i Page 20 !
e
's M RCS pressure less than 300 PSIA 7 c)
O Alg) temperature is less than 3000F, !
Ill[lf shut SIT Outlet Valves: l SI-614 MOV l I
SI-624-MOV SI-634 MOV ,
SI-644-MOV
- c. If RCS Pressure is less than 225 PSIA, {
&lg) the Safety Injection System has jg)I been aligned for Shutdown Cooling, l i
IllDi initiate'LPSI flow: ,
i 4
- 1) Stop any running RCPs.
- 2) Verify RWT Outlet Valves open:
SI-4142 MOV SI-4143-MOV
- 3) Start the selected LPSI Pump. .
- 4) Open the LPSI Loop Isolation Valves:
f ;
SI-615 MOV a SI-625-MOV , i l
SI-635 MOV SI-645-MOV 'l 1
I 1 d. IE the RCS Pressure is less than 225 PSIA, Alg) Safety Injection has been aligned for Shutdown Cooling, j
'I IllEll initiate Containment Spray flow to the RCS:
~
- 1) Open or check open the RWT Outlet Valve for the h
$ selected Containment Spray Pump:
SI-4142 MOV SI 4143-MOV !
- 2) Open or check open the Containment Spray Pump l
Mint-Flow:
11(21) CS PP SI-333 j 12(22) CS PP SI-343 l
- 3) Open or check open the Mini-flow return to RWT:
SI-659-MOV .
SI-660-MOV j
- 4) Open the selected Containment Spray Pump discharge i
valve: ,
11(21) CS PP SI-314 12(22)CSPP SI-324
- 5) Start the selected Containment Spray Pump.
- 6) Verify SI-657-CV at least 50% open, ,
1
.ggg. !
Due tosthe throttling affect of SI-306-CV it !
is necessary to shut SI-658 MOV to permit ,
injection flow from the Containment Spray. :
Pump. This action will' remove the cooling s
capability of the SDC Hx.
- 7) Shut SI-658-MOV.
J l
i 1
~
. AOP-2A :
e Page 22 i Operate SI-657 CV and SI-658 MOV as necessary to !
8) e i maintain:
a) Pressurizer level greater than 155 inches. ;
b) CET subcooled margin greater than 300F.
0 0 c) CET temperatures less than 300 F (200 F if l inMode5). ,
i
- e. M LPSI or Containment Spray Pump is operating, :
i AND HPSI Pump is operating, ,
i M place the handsvitch for the HPSI Pump in PTL, and j shut the HPSI loop Isolation Valves. ;
- f. E the LPSI or Containment Spray Pump is maintaining RCS ,
inventory, '
M place the Charging Pumps in Pull-To lock,
- g. Start all available Containment Coolers in HIGH, and open their SRW Emergency Discharge Valves. ,
- h. Start all available Containment Filters.
- 12. E S/G tube leakage is indicated, M:
- a. Have Chemistry sample both S/Gs to determine the i l
affectedS/G. l
- b. E the affected S/G is identified, M isolate the affected S/G:
- 1) Shut the MSIV:
MS-4043-CV MS-4048-CV 2)- Shut the MSIV Bypass Valves:
MS 4045-MOV MS-4052-MOV j A
i
' AOP-2A i Rev. 9 Page 23 l l
- 3) Shut S/G Feedwater Isolation Valve: j g <
11(21) S/G 12(22) S/G 2,
e FW 4516-MOV FW-4517-MOV l
- 4) Shut S/G 8/D valves
. BD 4010-CV BD-4012-CV BD-40ll CV BD 4013 CV ;
- 5) Shut AFW Steam Supply Valve, by placing handswitch ,
in CLOSE:
l 11(21) S/G 12(22) S/G MS 4070 CV MS-4071-CV l
- 6) Shut the AFW Flow Control Valves:
11(21) S/G 12(22) S/G AFW-4511-CV AFW-4512 CV ,
AFW-4525 CV AFW-4535-CV
- 7) Shut the Motor and Steam Driven Train AFW Block Valves:
i 11(21) S/G 12(22) S/G !
i j AFW-4520 CV , AFW-4530 CV l AFW-4521-CV AFW-4531-CV ,
AFW-4522 CV AFW-4532-CV AFW-4523-CV AFW-4533 CV
- 8) Shut the Atmospheric Dump Manual Isolation Valve, 11(21) S/G 12(22) S/G !
-l MS-101 MS-104 1 a
i k
I
AOP-2A Rev. 9 Page 24 h 9) Shut the Upstream Drains by placing handswitch N HS 6622 in CLOSE.
- c. E a S/G is isolated due to tube leakage, E:
- 1) Depressurire and cooldown the RCS to naintain RCS Pressure approximately equal to affected 0/G Pressure.
- 2) If desired, maintain affected S/G Pressure and Level per E0P-6 step I!!.W.
-CAUTION-The possibility of cavitation increases when taking suction from containment sump.
- 13. E RWT Level drops to 2.5 feet, E initiate RAS as follows:
- a. -E LPSI Pp operating for RCS makeup, E place the LPSI Pp RAS Override Switch in OVERRIDE.
- b. Depress Recirculation Manual Actuation Channel A and B pushbuttons to manually initiate an RAS.
- c. Verify Containment, Sump Isolation Valves, SI 4144 MOV and SI 4145 MOV, open,
- d. Shut RWT.0utlet Valves, SI-4142 MOV and SI-4143 MOV.
- 14. E Shutdown Cooling is not on service, E initiate Shutdown Cooling as follows:
- a. E Pressurizer level gre.ater than 101 inches 8llQ RCS subcooling greater than 300F, M:
AOP-2A Rev 9 Page 25
- 1) Initiate Shutdown Cooling per 01-3, with the N following exceptions:
a) IE a Containment Spray Pump is maintaining RCS inventory, IllG do not shut its discharge valve, b) If a LPSI Pump is maintaining RCS inventory, ItiG do not align the suction valve for Shutdown Cooling.
- 2) Operate Charging Pumps and/or LPSI/ Containment Spray Pumps as necessary to maintain RCS Level and Pressure,
- b. IE all of the following conditions exist:
o Pressurizer Level less than 101 inches.
o RCS subcooling less than 300F.
o RCS Pressure minus Containment pressure less than 160 PSID.
1113 commence Shutdown Cooling as follows:
- 1) Shut 11(21) and 12(22) Containment Spray Pump Discharge Valves:
11(21)CSPp SI-314 12(22) CS Pp SI-324
- 2) Shut 11(21) Shutdown Cooling Heat Exchanger Outlet to Spray Header Valve, SI-319.
- 3) Shut 12(22) Shutdown Cooling Heat Exchanger Outlet to Spray Header, SI-329.
- 4) Open 11(21) Shutdown Cooling Heat Exchanger Inlet Cross Connect Valve, SI-452.
. . . . .- 1
a a --- . sa- *.-- ~a -,m- - - n ,- a ,,--- - - -
t I, AOP-2A Rev 9 ,
Page 26 l
m 8 5) Open 11(21) Shutdown Cooling Heat Exchanger Outlet i T to RCS Valve, SI 456. j 8 l
- 6) Open 12(22) Shutdown Cooling Heat Exchanger Inlet j Cross Connect Valve, SI 453. l
- 7) Open 12(22) Shutdown Cooling Heat Exchanger Outlet i to RCS Valve, $1-457. ;
- 8) Place second Component Cooling Heat Exchanger in service by opening appropriate Component Cooling Heat Exchanger Outlet Valve: l CC-3824 CV l CC-3826 CV I
- 9) Start a second Component Cooling Pump.
- 10) Open 11(21) Shutdown Cooling Heat Exchanger Component Cooling Outlet Valve, CC-18 CV.
- 11) Open 12(22) Shutdown Cooling Heat Exchanger Component Cooling Outlet Valve, CC-3830 CV. <
- 12) Open Shutdown Cooling Heat Exchanger Inlet Isolation, SI-658-MOV. l t
- 13) Open LPSI Hdr Isolation MOVs: ;
SI-615 MOV l j
I
$1-625 MOV SI-635-MOV i SI-645 MOV
- 14) Place keyswitch for SI-306 CV in AUTO,
- 15) Shift FIC-306 to MANUAL with 5% open signal, q i
l
. l
. AOP-2A l Rev. 9 Page 27 i P
g 16) Open Cntet Sump Discharge Valve:
3 SI-4144 MOV !
- 17) Shut $1 Pump Mini Flow Isolations:
SI-659 MOV ;
4 SI-660 MOV
- 18) Ensure level indication exists on Wide Range Containment level Indicator, LI-4146. j
-CAUTION- i 1
The possibility of cavitation increases when taking -
suction from containment sump, .
- 19) .IE LPSI Pump 1511 operating, l
\
IllW clear RAS from one operable LPSI Pump by l
placing LPSI Pump RAS Override Switch in OVERRIDE, !
and start the selected pump. i 4 ,
-CAUTION- i Cooldown limit changes from 100'F to 20'F at RCS j temperature of 250'F. i
! 20) Adjust the signal on FIC 306 to raise flow to 3000 -
GPM, while maintaining cooldown rate within 4
limits.
- 21) Place keyswitch for SI-657-CV in AUTO. i i
t
I- A0P-2A Rev. 9 Page 28 m
E -CAUTION-Do not-exceed 14'F/m heatup rate or greater.than 5000 GPM through one heut exchanger.
- 22) Adjust Shutdown Cooling Temperature Control Valve, I SI-657-CV, to obtain less than 14 0F/m heatup rate at Shutdown Cooldown Heat Exchanger Outlet (TI-303X and-TI-303Y). ,
- 23) If desired RCS cooldown rate can HQI be maintained with one LPSI Pump operating, ;
Ills start _second LPSI Pump, and adjust FIC-306-to !
6000 GPM. t il 24)- Adjust Shutdown Cooling Temperature Control Valve, SI-657-CV, to obtain desired cooldown rate.; j i
V. RESPONSE FOR A MINOR LEAK !
l (One charging pump is able to maintain pressurizer level with minimum l letdown flow but RCS leakage is greater than allowed by Technical- !
Specification 3.4.6.2.) ;
1 A .- Implement ERPIP 3.0 as applicable. '
i B. Locate and attempt to-isolate the leak
- 1. Verify or determine RCS leak rate per STP-0-27 concurrently. l i
with the following steps.
- 2. Determine if leakage is to the containment atmosphere as l, evidenced by the following conditions: :
- a. Increased frequency of containment sump alarms.
.1 h
' d