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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 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 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 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 ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl 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 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 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 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 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 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 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 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 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 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 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 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 ML20196K5721999-03-25025 March 1999 Forwards 1998 Annual Rept of Individual Monitoring, Using Form NRC-5 Format,Per Requirements of Reg Guide 8.7,App a, Format for Electronic Transmission of Exposure Data. Without Electronic Media 1999-09-28
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML19324C4571989-11-0707 November 1989 Requests Approval for Use of SB-166,UNS N06690 (Alloy 690) Matl in Fabricating Steam Generator Plugs,As Alternative to ASME Boiler & Pressure Vessel Code Section III Requirements, by 891215 LD-89-099, Forwards Proprietary CEN-373-P,Vol 2,Suppl 1-P, Realistic Small Break LOCA Evaluation Model,Application of Evaluation Model to Calvert Cliffs Units 1 & 2. Rept Withheld (Ref 10CFR2.790)1989-08-28028 August 1989 Forwards Proprietary CEN-373-P,Vol 2,Suppl 1-P, Realistic Small Break LOCA Evaluation Model,Application of Evaluation Model to Calvert Cliffs Units 1 & 2. Rept Withheld (Ref 10CFR2.790) NRC-87-3278, Forwards Gc Steinel & ED Goslin,Of Westinghouse, to Jp Mcvicker of Bg&E Re Broken Weld on Pole Shaft Assembly of Westinghouse Circuit Breaker Ds 206,per 871021 Telcon Request1987-10-22022 October 1987 Forwards Gc Steinel & ED Goslin,Of Westinghouse, to Jp Mcvicker of Bg&E Re Broken Weld on Pole Shaft Assembly of Westinghouse Circuit Breaker Ds 206,per 871021 Telcon Request LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987 Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request ML20215M1201987-06-17017 June 1987 Requests Reinstatement of Author Name on Distribution List for All NRC Correspondence Addressed to Bg&E Re Plant.Author Address Listed LD-86-034, Forwards Performance Info for C-E Supplied Nuclear Fuel for CY85 on plant-by-plant Basis,Per NRC 860618 Request.Info Includes Number of Fuel Assemblies & Fuel Rods Irradiated &/Or Discharged & Batch Average Burnups1986-08-0101 August 1986 Forwards Performance Info for C-E Supplied Nuclear Fuel for CY85 on plant-by-plant Basis,Per NRC 860618 Request.Info Includes Number of Fuel Assemblies & Fuel Rods Irradiated &/Or Discharged & Batch Average Burnups LD-84-039, Informs of Planned Mod to C-E Control Element Assembly Guide Tube Wear Sleeve.Mod Includes Relocation of Sleeve Flare,Sleeve Expansion Over Full Length of Sleeve & Relocation of Crimp,Providing Resistance to Axial Motion1984-07-27027 July 1984 Informs of Planned Mod to C-E Control Element Assembly Guide Tube Wear Sleeve.Mod Includes Relocation of Sleeve Flare,Sleeve Expansion Over Full Length of Sleeve & Relocation of Crimp,Providing Resistance to Axial Motion LD-81-060, Informs That Topical Rept Re Extended Burnup Fuel Cycles Similar to Info Described in NRC 810602 Request,Will Be Submitted in Early 1982.Document Will Minimize Unit & cycle- Specific Analyses for Extended Burnup Targets1981-09-18018 September 1981 Informs That Topical Rept Re Extended Burnup Fuel Cycles Similar to Info Described in NRC 810602 Request,Will Be Submitted in Early 1982.Document Will Minimize Unit & cycle- Specific Analyses for Extended Burnup Targets LD-80-053, Forwards Affidavit Supporting Proprietary Designation,Per 10CFR2.790,for Apps D & E of Cycle 5 Reload License Submittal1980-09-22022 September 1980 Forwards Affidavit Supporting Proprietary Designation,Per 10CFR2.790,for Apps D & E of Cycle 5 Reload License Submittal ML19323A1611979-12-26026 December 1979 Forwards Articles Re Methane Detection Using Lasers. Recommends Laser Fence Idea.Sys Would Act as Continuous Fence Under All Conditions Except Heavy Fog.W/O Encl ML17207A3471979-08-29029 August 1979 Forwards Proprietary Version of CEN-115-P,in Response to IE Bulletin 79-06C Items 2 & 3.Response Withheld (Ref 10CFR2.790) ML20023E0651973-08-0101 August 1973 Forwards Section of Idaho Nuclear Corp Rept Ny-123-69 Re Statistical Verification of Macbeth Correlation 1989-08-28
[Table view] |
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mm 5J COMBUSTION DIVISION August 1, 1973 Dr. S. Salah United States Atomic Energy Cor: mission Rocm 511 7920 Norfolk Avenue Bethesda, MD 20014
Dear Dr. Salah:
~
Enclosed is a Xerox r.opy of the section of the Idaho Nuclear Corporation Report,Ny-123-69, concerning the statistical verification of the Macbeth correlatien. The pages of specific interest to you are II-3 and 11-4.
If I can be of any further assistance, please don't hesitate to contact me.
Sincerely yours:
g.I w
Dr. Charles L. a ing ~
Supervisor, Nuclear Safety Dept.
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Gentlemen:
Inclosed please find your copies of the October Monthly Report of the ::uelcar Safety Prcgram Divisien of Idaho ::uclear Corporation.
Very truly yours, WE:::be
- a. :.. i.y er,..r..ager
- uclear Esfety Pr:gran Division
Enclosure:
Nuclear Safety Program Report - October 1969 Addressees:
C. ::. Kelber - A1L H. A. Sindt. nAPD L. Earer - A::L - L:72RPO D. F. Ju dd - 3 & '4 J. A. Redfield - BAPL R. E. 'das cher - 3 & W D. L. *torrison. 3:'.I M. F. Valerino - CE T. A. "aker - IITRI L. E. *!innick - CYAPC T. W. Trout - KAPL A. P. Bray - GE
'4. 3. Cottrell - OR: L (5)
D. O. Fischer - GE L. C. Oakes - OR:!L G. E. Wade - GE G. J. Rogers - P:lL D. Free an - GE. Sunnyvale G. M. Brown - S:!E T. P.ockwell. III - lGR
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, R. G. Bock - GE - San Jose R. A. Wicsemann - WCAP W. K. Dodson - KE J. F. Palmer - AECL J. D. O'Toole - U::C
.'. 3:ur6ecis - CFA F. R. Fc.rner - U:'AEA
?. Tagani - HCRL H. G. Ru rf - TUV
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_ Assistant Director for Nuclear Safety, DRDT cc:
Assistant Dire:ter fer Project :.!anagement, DRDT Assistant Dire:ter for Plant Engineering, DRDT Assistant Dire:::r fer Reicter Engineering, DROT r.._,
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Chief, Research ar.d Develc; ment Ernnch, DRDT Chief, Engineerir.g and Test 3 ranch, DRDT Chief Environmental and Sanitary Engineering 3 ranch, DRDT Chief, Fuel Engine ring 3 ranch, DRDT Chief, Contr:1 l*echanic: 3 ranch, DRDT Chief, k*ater Systens 3 ranch, DRDT Division of Naval Reactors, D::R (R. S. 3rodsky)
Director, Division of Reacter Standards Deputy Director, REG Assistant Director for Reacters, REG Assistant Directer for Special Projects, REG Director, Division of Reactcr Licensing, REG Chief, nuclear and Systems Tc:hnolcgy 3 ranch, DRL (2) '
Direct:r, ::u: lear Technolegy Divisien, ID (3)
Director, 'Euclear Safety Division, ID
. Directer, LCFT Project Divisien, ID (3)
Directer, Hu:1 car Engineering and Cenetruction Division, ID Chief, Technical Services 3 ranch, CSTS Division, ID Chief, Budget Branch, ID g*
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The inferna_ior. cer.';cir.d in this rep:rt ic' prelini:...ry a r.i : ':j e:t to further eV31MatiOh.
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- r ng-TA3LE OF CO :TE;;TS Page I.
Sr o..a I-1 II.
KUCLEAR S/JETY DEVELOPM2HT.
........ II-1 II-1 A.
Analytical Developent II-10 B.
Separate Effects Tests II-11 C.
Power Reactor Safety Analysis.
II-12 D.
Fission Prcduct Tests.
E.
In-Plant Testing of Reactor Engineered Safety Syste=s II-1k F.
Reliability Monitoring Prc6 ras II-15 G.
E=erGency Core Coeling Heat Transfer Tests II-16 H.
Acoustic Flav Detection and !{onitoring System II-25 Developent.....................
49
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4 s
8 ii 9
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.Detober 19c9 y
II. 1:UCLEAR SATE T DEVELGII'E"T BRA"CH A.
Analytical Development 1.
Highlights None 2.
Technical Activities Core Heat Transfer Anelyris: A users manual has been ' prepared and distributed within Idanc ::uclear Corporation for the single rod, single channel ecde TI: ITAL.
Ther cphysical properties for UO2 and Zircaloy-h have been inccrpcrated in the code.
Werk is continuing tcvard development of a three-dimensicnal core heatup code for the FEUST 8x3 rod bundle. A subroutine to calculate the fluid energy balance at each axial level is currently being developed.
With the addition of the subroutine the code vill be operational.
Dhe CEF study continued. A total of 729 lea pressure (150 to 725 psia) red bundle CHF data points has been collected and correlated, and a report of this study started. Also, a report describing the ec=parison of selected CHF correlaticns to data previously ecliected was started.
A portion of this report follows.
One major parameter in 1 css-of-coolant accident (LOCA) analysis is the time-to-critical heat flux (a) (CHF), that is, the ti=e frc: initiation of the break to the time critical heat flux occurs in the cere. I: ediately fellouing the occurrence of a break, the pressure differential across the core results in forced convection which begins to transfer the sensible energy stored in the fuel rods and the decay energy scnerated by nuclear fission frc: the rods to the coolant flowing thrcush the core. Eventually the critical heat flux conditien, which is a functicn cf the red anM core geenetry, axial heat flux distributice, and the fl:v and ther:cdyr.anic state of the coolant is reached. At JEF e film of vtp r exists adjacent to the red surface and results in severe reduction in the a cunt of enerEY that can be removed from the core. Tclieving the attainment of the CHF condition, the rod surface ter;crature 'cegins to increase as the energy rc:aining in the rods and the generated decay energy 'cecoces redistributed.
Alth:ngh predic'.icn of th: Oritical heat flux is neces:try fer reactor design purposes, the phenc:enen of :ritical heat flux maintains a unique status in engineering in that no theoretical analysis has been atte=pted
() Critic;; ". cat.1x ic uced in thic reper: *o decerite a large decrease in the lceal hea: tran:fer ccefficient which results in a large increase of the surface temperature.
e e
y x
.,4
- n 6ctober 1969
~
and consequently experimental data are the only cource cf information Therefcre, in crder to obtain design values regarding it s. cccurrence. flux, ex.ccrirents are ucually conducted at steady-of the critical heat
- spacing, state with electrically heated rods of design diameter, pitch, and length and with fluid conditiens at er near the design operating If sufficient data with a systenatic variatien of the core inlet reint.
cendition and c- ' *+ --se flux are taken, a ccrrela ion of the data may be attempted and this correlaticn in turn say be uced as a design equation.
In contrast to the problen of' cbtaining informatien required for denign purpcses, the probler of predicting when CEF vill be reached during a,less-of-ccolant accident requires data over vide ranges of pressure, = ass flux, and inlet conditions and, in addition, the effects cf rapid ch2nges in pressure and cass flux must be taken into account.
An investigation cf all CEF data available in the open literature for axial flux prcfile, red bundles and of several CEF steady-state, unifer:
correlatiens has been undertaken with the cbjective of determining the applicability of the data and ccrrelations to =cdels being developed to predict the core thertal behavior during a loss-of-coolant accident.
The correlaticns censidered in this repcrt are prcbably the costThey have been ci at the tresent tir
, 3,eger(3, Gencral Electric (e). and '..~estinghcuce (Shippinspcrt)(h).
.videlv2[2)vnanduce n-3:rne':t Eenuits obtained by using these ccrrelatiens were ec pared trith 1C96 CEF data points for rod bundles which cover the fc11cving ranges of parameters:
156 to lk00 psia Pressure 6 lbe/hr-ft2 0.02 x 106 to 4,o x 10 Mass flux Fluid inlet ecndition 0to3733tu/lb subecoling 0.250 to 0.625 in.
Roi diameter 30.0 to 178.0 in.
Rod length 0.022 to 0 30T in.
Spacing betwee'n rods Axial heat flu); distribution Unifonn tra'".-i. F r ~* Ey..ir aticn cf Published R. V. :*a cb e th. 5 "r -u'. R :p
\\Lyu~).
(1)
V:r.d ?c a for ?.ci ;z.ur..: u, n za-A Ccrrele-i-- of Furneut Dsta fer Uniferrlr Eeeted (2)
P. G. Barnett, ci rcrri.
...s.e: hed Eunizes, An-uli and Its Us e _for !r,lic:inr ?.. :. is
'i. W-h -03 (19cc).
'<. 2 + e r (3)
K. M. Becker, ' ? : rn c u. O '- "
' - * ' - T ' -"
in Vertical.c4 Sundic e,.2-eTO (1jui).
9 (h)
L. S. Tcng, T.cilinc l'ect Tranrfer an-1 P.re-Fhare Fiev, New York:
Jchn Wiley and Scns, Inc.,1907 II-2 a
U V
.-,j; October 1969
.y For purpeces cf eczpariscn, the percent error between the calculated and experimental values is defined as
~ Q ur o
c"c(100)
(1) cer'a ERROR =
S'CEF,e where qcgy,, = experimental criticc1 ?. eat. flux, cleulate riti al heat flux.
q EF,c
=
C The results of the calcula:1cns are presented in Figures II-1 through II-5 as
- graphs of the frequency that an error is encountered versus the percent error of E u2tien 1.
Whereas these figures do not reveal the cetails of the error distribution with respect to pressure, length, mass flux, inlet subcooling, and bundle internal ccnstructicn, they do give an overall view t'
of the accuracy of the correlation.
Figure II-1 gives the error distrit.'ticn of the Macbeth ec: relation ( ).
The results are goci considering the fact that the correlation is based cn a very lizi ci a: cunt of data (172 points) given in Reference 1.
'Jhen cc pared with CEF values determined fcr ranges of parameters within, as gerrelation predicts well as cutside, the ranges en which it is based, tha 97%cfthedatavithintheerrcrbounds-207,toF255(8
/.
Figure II-2 61ves the error distribution for the Barnett correlation (2).
Again, the data were obtained fren 'cundles uhose sec ctric and operating characteristics were within and outside the range fer which the correlation was based. All of the data are predicted within -32 5% and +27 5% and 97% is predicted within -22 5% ani +17 5%. These results and an examination of Figures II-l thrcugh II-5 indicate that the Barnet correlation is v.
superier to the c hers for predicting steady-state CEF data frca red I
bundles.
Figure II-3 gives the errer distributien for the 3ecker.ccrrelation(3)
Although the ccrrelation is based on data over the pressure ranse 31 < P 5 lh00 psia, and all ef the rod bundle data are within this range, the predictions are not as accurate as these of the Macbeth and 3arnett correla-i tiens. The calculated results for 97% of the data agree with experimental 1.
re.c., a-. a n. a...a-u,,'3.
(a) The 975 lev;l of cerrclatien is videly used in the open literature.
f Ecuever, the :hcico cf -he errcr ecunde within whi:h 97,' cf the data is f
pre dicted s quite a #"---
y.
Fcr this repcrt, values were chcsen ~:etween which the errer distributien is sy :ctrical.
I I
l II-3
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i ep 140 U
.c 3
~
g-12 0 C
100 80
~
60 40
-l 1
=
20 n.o l
~
H t
t i
f i
' ' I t
g
-40
-30
-20
-10 0
to 20 30 40
!O IQ
~GCMF c CHFe C M F. e tNC-A-14 240.
I l
Fig. II-l Error Distribution for the Macbeth CHF Correlation II-b e
l
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9
..,p..
zg 180 u
c t,
3a 160 w
=
'14 0
~-
12 0 10 0 BC
^
60
- 40 f
l
- 20 l
1
\\
I t
g i
-40
-30
-20
-to O
to 20 30 (g
-o 1800/o l
CMF.e C MF.4 CMF.e r
Fig. II-2 Error Distributien for the Barnett CIIF Correlation l
l II-5 I
l
%.)
U u0 r.y
- - 10 0 3
.EF C
90 80,
1 70 60 50
- 40
- 30 i
- 20
- iO I
C t
_fo
-4o o
to 20 30 40 l
,, o 3o
( o.,,, - a.... ) ' 0 0 / 8 c
c c.r.
Fig. II-3 Error Distributien for the Seeker CEF Correlation II-6 t
a
~
. e
.+
I 0 s
6 i
0 4
0 I
t 2
no i
t I
a l
l e
0 5
0 8
5 r
3 2
2 g
0 0
r o
C
$:Tr:w 1
F I
I C
t 0
r 1
2 o
p g
I r..
n 4
i c
p I
p I
0 I
i
/
0 h
4 0
S g
e I
i e
F h
I r
t ac ro I 0 -
f 6
r n
e i
o c
i I
t l
u b
I 0
i 8
r ts i
s I
D ro 00 r
1 r
9 E
i 0
f 2 9
I i
0 I 4 t
l I
0 6
9 gH,4 i '
]1i' 1
C s
0 F.. I 7
w i
0 i
6 F_
i 0
t i
5 e
vru i
C ng 1
i 0
s l
4 eD T
i IC y
0 n
i a
3 p
mo C
i c
ir 0
t I
2 c
e l
9 5
E i
F H
I l
C 9
I ar e
0 I
1 g
n i
e F
G I
4 I
c, F
e H
h C
t N
o 0
0 0
0
~
r 0
s 1
3 2
1 0
o 6
e.
f
. jl-F H
n o
C
=0?.'
9 i
l 1
i tu f_
b 0
1 i
I r
ts D
i i
ro r
0 r
I 2
E i
0 i
g 3
1 i
0 1 4 0
mo s-lt i
lt l
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~
h October 1969 ny correlation (IT-h presents thaOnly 33% of the data vere predicted within -160% to Figure arrer distributica fer the Shippingpert k).
45% error. The rc aining 62% of ti.a predictions produced errer larger than -16C% and, therefore, are not tabulated in Figure II-5 As defined thus by Equatica 1, negative errers indicate an over-predicticn of e any correlation that yields negative errers is undesirable fer"gr,bbth design n
and LOCA analyses. The results given in Figure II i clecrly indicate the ne c c a a- * *."so.'.-r.----*-.
"-.-*'.'..*-..'..da.a=.*.>..-a.. u
.4..s-
'.'..a. c-.e'a-S
-: -. - ~
.s tien. Iigure II-l aise in:icates ;ne inaccuracies tha are pcccibic when a correlaticn based on data frc: a given sc etry is applied to c her gecretries.
The General Electric Cer;nny design curve correlation was derived by censtructing curves under CEF data ccisidered c c:ver the operating range cf SWR *s (that is, a Iceer envel:pe was determined). That the correlation is ecnservative (pcsitive errcrs) as intenaed is indicated by the results shcun in 71gure I~'-5
.-2nevar, the success of using this cethed of correlation reqaires data fcr the entire range of parameters over which the ccrrelation is to be applied. An e.xamination of the predictions shcvs that the ncncenserva-ive errcrs (negative er*crs) in Figure II-5 were obtained fer lev mass flux data (G < l.0 x lob lbm/hr-ft).
2 The results presented in.this section have shcvn that the method of 7
correlation used by Macbe:hs1 a->
- --att(cl produce accurate CHF correla-
/
tiens that =cy be extrapolated with reasenable certainty cutside the range.
of pcraneters en which they are based.
The develeprent of(nov heat transfer.
Therral-Hvdraulic Anelysis:
The Macbe:h 1) and Earnett(2) todels fer use in RELA?3 has ccntinued.
critical heat. flux correlaticns are being used for calculating the critical heat flux. Currently, the Earnett correlatien is being used for pressures above 1000 psia and the Macbeth correlation for pressures belov 725 psia.
For intermediate pressures an interpclation between -he two correlations is used. The correlations have been ceded and are currently teing checked s.
cut.
An extensive analysis Of the semiscale Test 813-2 (30% double-ended break)isbeingcade". The tes; data are being ec pared with RI'A?3 predictions made prior to running the test. Preliminary cc parisons shev scod agreement between predicted and ceasured prescures.
Cciputer Sciences Support: An explicit technique for solution of th=..""---~....".c.e"-..'..
-. - "....* *.... *.. *. - '.. ~. ~'.~.~. n..= '.s"...~='.'.*~.~~s'.n of a L1.s.-Wendriff technique. O:ic cchnique ;rcvide: a =cre stable and accurate solution cf abrupt chan;23 in bcuniary ecnditiens (that is, the channel inlet enthalpy change that occurs during flev reversals) than the precent explicit er implici: rethods currently in THETA 1.
This new technique vill replace the pretent enplicit technique.
II-9
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au V0ctober 1969 -
B.
Separate Effects Tests l.
Highlights i
A preliminary systen design description document has been prepared for the two-loop Semiscale Blcudewn and ECC System.
A series cf channel bicekage experiments in support of F1ECET has been cenpleted 'en a 9-pin heater asseibly.
t 2.
Technical Ac-i"ities Semiset.1* ?2ev.detn and ECO (Sin le loop): The se:.iscale blevdown assedbly is presen.ly underacing ::ifications in preparation for Test Series II Grcup 2.
- ciifica:icns ecncist of the installation of an electrically heated cere, the addi:icn cf three ganza ray densitometers to cbtain measurements cf aterage fluid density in the enre, a change in the locp ccnfiguraticn frec two rup:ure devices to one rupture device, and the installation of additional instrumentation.
Specifications have been issued to the Procurement Branch for 3-foot heaters for bicudevn heat transfer studies. Request for cuotations
- were issued October 27; tha bid cpening date vill te UcVedber 17, 1969
'A delivery date cf February 27, 1970, hac been c;ecified.
Semiscale Ele.dern ced E00 6.o lect): The t:c-lccp blevdcrn system is in the ccnceptual desi6n siege. A preliminary syste: desi6n descriptien document has been prepared for review and cctments. Work has begun on specificaticns for long lead time components.
t I?ine-pin Ch:nnel Ele:ka e Experic nt: A series of experiments has been ecepleted vi:h a 9,in ecre to s.udy the effect of flev channel blockage on eter ency ccre cooling hea; trancier. The experiments vers condue ei by ficciing the ccre at tenper :ures of 1600 and lg;;c? vith restricted ficv area at. he center of the cere. Restriction in flev l
crea was varied during the test series fre no restriction to 90 percent restriction. Results are being evaluated.
FHUST: The THUST core for Test Series II testing has been assedbled and installed in the FZUST vessel. Tecting is scheduled to begin the seccnd week cf ::cvember after the instruuentation has been connected and the cytten has been checked cut.
II-lO
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