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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
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,y f B&W NUCLEAR TECHNOLOGIES 3HT/89-235 November 7, 1989 3315 Old Forest Road m Boxfosas I ynchbury VA 24506-0935 Telephone:804 385-2000 Telecopy: 804-3BS-3663 o
U. S. Nuclear Regulatory Commission [t?- 3/7 Washington, D.C. 20555 Attention: Document Control Desk
Subject:
B&W Proposal of Alternative to ASME Boiler and Pressure Vessel Code Section III Requirements
Reference:
- 1) Letter from Mr. G. C. Creel (Baltimore Gas &
Electric) to U. S. NRC Document Control Desk, dated October 27, 1989, " Revision of Proposal of Alternative to ASME Boiler and Pressure Vessel Code Section III Requirements" (copy attached).
Gentlemen:
The purpose of this letter is to request approval for the use of SB-166, UNS N06690 (Alloy 690) material in fabricating steam generator plugs. As noted in the referenced letter, this material possesses superior corrosion resistance to primary water stress corrosion cracking over Alloy 600, the current material that is used for steam generator plugs. The design values that will be used for code calculations will be based on those given in Code Case N-474, approved for SB-163 material, and Code Main Committee Item 88-360, approved December 9, 1988 for all forms of Alloy 690. The information from 88-360 will ha included in the Winter 1989 Addenda of the Section III Appendices.
As material requirements for Alloy 690 are contained within SB-166, this specification, and B&W manufacturing roquirements that are more restrictive, will be adhered to for chemical and mechanical properties.
B&W has requested ASME approval for the application of Alloy 690, Specification SB-166, SB-167, SB-168, and SB-564 material for
- l. Section III repairs, and the ASME B&PV Code Committee will be i reviewing this request.
Your approval of this proposal is requested by December 15, 1989 l to allow the use of Alloy 690. The need for this material is
' based on the recent problems that have been associated with Alloy 600 when used as mechanical steam generator plugs. Therefore, the use of Alloy 690 is the correct choice of material for steam generator plugging applications to avert potential plug cracking concerns.
1 .
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b L-i r .. l NRC Document Control Desk 1 JHT/89-235 November 7, 1989 Page 2 l
l Should you have any further questionc regarding this matter, we will be' pleased to discuss them with you.
By copy of this letter to Mr. J. E. Richardson, he is requested ,
to advise me promptly as to whether a December 15, 1989 approval is feasible. B&W plans to begin installing 690' plugs in January 1990.
Very truly yours,
- s. '
gf -
. Y. Ta or, Manager '
Licensing Services JHT/bcc Attachment cc: L. B. Engle/NRC K. R. Wichman/NRC J. E. Richardson /NRC S. P. Hellman J. R. Bohart R. B. Borsum 1
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Washington. DC 3p398 .
l ATTSim0N: Document control Desk SUBJECTt Calvert Cliffs Nuolear Power Flaat Unit Nee. ! 4 2; Declost Nos. 50-317 4 30-818 ;
L l Revleien of Proposal of Altern4tive to ASMB 5eller and Pressese l
y ca. *- - m n = t 4
l Gentisment j The purpose of this letter k to ausend Referesse (a) with the following proposal. la -
assordamos with 10 CFR 80J8e(s)(3), we are propeelas an alternative to the l requhement of 10 CFR 50J8e(s). The oristaal proposal arreeseuely ented that it wee is subseisted la eseosdanse whh Referesse {D), ,
1 l We have determlaed that Alley 690 is esperior to Alley 600 for 'ues se repineament i pressuriser ;ne'er. material due to la prhnary waser stress soriosion creeklas (SCC) feelemass. The ASME Beller and Pressure Vessel (B&PV) Code approves the use of Alloy 090 under Speelfloation 53-163 for Seedon M (Code Casse N-20-3 and N-4?d), J but Spesifisesione $5-166 and 85-107 are not curready leoluded. .We are psopeeles to use, at our opiloa, ' Alloy 690 mesdag Spectriostloa 5B-166 or 88-167 lastead of Alley ,
600 for penseurier penetrettes soplacemean. i 1
i, c o - = = i. N w w.k an A e = r!v. As r_ ,
L The seinshed drawing Identifies all pressoriser penetrations, We plea to use f Ainoy 890 unear spostfloation $5-146 or SB-167 fbr say penetratloa that requlrse replacement. These penetrations were orislaally desisned to ASME BAFV Code secties M. Class 3,1965 Edition through Winter 1967 Addenda.
gg, AaME Rman! : far WMeh an Airr M!= 1. Prema**d .
We have adopted the alternative allowed by ASME B&PV Code Seetion XI.1986 Edition, paragraph IWA-7210(c). The alternative allows that 'repkan. ente sesy
- most all or portions of the niquiremens of later editions of the Constructica Code . . .
- We have reviewed the ASME B&FY Code Section W and noted that the use of Alloy 690 meeting .*peelflaations $3-166 and 53-167 la not 3aalad*d Reguintory Guide 1.85 list Cooe Case N-20-1 as approved; however, this 0446 h lI'lO I
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w( ,-
, vv T) . iF3 rnoM CCNP M END NEF-lF U. mM N Deemment Control Desk '1
. Celeber 87.1989 pese heat esp!!ss only to Spesificaden 59163 esamless tablas for eendenser or enchanger appilettless with e 40 kai etaisus yloid stroasth. Additionally, we sets est Code Case N to 1 has emphed and has been renewed as N 20-3. Also, :
Code Case N-47d has recently been approved by the ASME Code Committee (which includes approval by the NRC repressatative Mr. R. J. Bossak) darias its l l
Pobruary 1949 nimestias.. and will appear la the neat ASME B&PV Code Case ;
publicatloa. Agala, this Code Case applim only to Spesifloation 53-163, but '
)
allows the use of a 35 kel minhausa yield strength masselst. l l
i M. Enala rhe pmanamina na Alespinalwa t
During the surrent Unit 2 refuelles estage, na laservios inspectiam of the Unit 2 pressuriser elseovered evidemos of remotor coolant .from a . somber '
pesotrations and one pressuriser pressure penettstion.
of bester Butesquent lavestigations have revealed that a number of those penetrations must be either pepelped or repleted.
The orislani penetrosions are made of Alloy 600 'While tide material is seceptable as repleosment maserial, the current body ' of den ladleness that Alloy 690 pensemos superior SCC resistanos. The laeressed ehromium content i
i of Alloy 490 produces a material that has been demeestrated to be Isanname or at '
i least realetant to degrudation mechannama that are active with Alley 400. For osaapie, om page 2-9, Reference (c) states, ' ell avellable dem for Alley 490 ,
i sagssets this material (' microstructure') is not sueseptible to primary water strose corrorton orookins (PWSCC).. Therefore, even though the other fheters are presset (ettoes and temperature), PWSCC has not been observed la this alloy.' Page 8-1 of Referosse (d) ooncludes, ' Alley 490 was lamene to SCC la pure water under all conditions evaluated' tad "Reaking of the alleys la lerms letruslea environment of their SCC resismase la the simulated resia indicated that . . . Alloy 600 . . . had latertmedisse resistnace, and Alloy 400
. . . had the highest resistemos.* Page y of Reference (e) states, 'ABoy 400 was much more resistaat to stress sorrosien than Alloy 600 and was hamass to Also, cracking la most of the - acidic sul' ate solutions enesdeed.'
- Referentes (f) and (3) eeestado that ersck initiation times for Alley 600 are reduced as the room temperesure yield stroasth and reeldual , streses are lagressed. This same reistleaship would be expected for Alloy 690 material.
Based on the superior stres corrosloa oraeklas reelseaseo properties of Alley 690, we prefer to use It as the rapinoament material for our pressuriner penetradons. The A5MB 34PV Code Section M n!!ews the use of Alloy 690 under Speelfloatlos 88-163: Seamlem Nickel and Nichel Alley Condenser and Heat Bashaager Tubes (up to 7/8-inch 00) whh a 40 kel mishaua yield strenesh per ASME Code Case N-20-3. ASME B&pY Code Case N-474 allows the use c,f 35 ksi niinimum yield strength as speelflod la Speelfloatles52-153 for all i
applicable tubing thlokaanses determlaed la socordamos with N3 3133 using
.- Figure VII-1101 1 la Appendis YH of Sostica III (Refwences h and 1). The ASME B&PY Code, however, does not laolude use of Specifloation 85-146:
i Nickel-Chromium-tron Alloy Red, Bar and Wike or Specifiestlos 88-167:
Nickel-Chromium-tres Alloys amanniana Pipe and Tube.
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Seemment Centrol Desk 1 Ostebet 87,'1909 !
l 7000 $
1 Use of Spoolfloations 88 144 sad 85-14f wiu allow us to repinse the pressurieer penetrations with Auey 690.
!Y. Addistanal mannimmaats .
Timough this proposal, speeltications 85166 and 55.idt will be used tesother with tim applisabes additiesel reduireeman lesend on sowification as. ids la the A8ME B&PY Code Cases N-20 3 and )(.494. Specifissuy, we wiu Whose to the Intent of the A8MB B4FY Code Case N-474 (for 88 ka! minhasa yield ,
strength' sasterial) ftr mechanlaan properties. That lo, we will nuet the minimum yleid OWeagth requirements for Alley 690 as given la 8positleasises l SB-lM or S 167 for Alloy 600, la addiales, we wul establish the sepasste ,
weldlag precedegee sad performance goalifications required for Alloy 690 by the AEME 34pv Cees Cases.
r Your approval of this proposal is scenested by December IS,1949, to nuew the use of ADoy #0 Use of this material wu! provide an aseepteblo level of genuty and safety es described la paragraph m above and further described la Refereness (b), (e) and ,
(d). The esed for thh ' request seuld act reasonably have been entielpand slase ,
f>om peessuriser sleeves or aosales is a rare escursenes. Comp!!sase with the s requiremeses of ASME Code seetloa m wul not result la heniship or unusual dimounty la effeedas repairs. However, the ass of Alloy 600 may be related to the root osuse of the leeksee at the pressuriser poseerations. Thotsfore, the use of Alloy 690 is the oorrest sholes of saaterial for the pressortser sleeve and acule ,
application. Its use wul avert the potential future eensequences (i.e., hardship) -
associated with not uslag the best avelleble material.
Should you have say further questions regardlag this metter, we will be pleased to discuss them with yes.
Very truly yours, V .
OCC/JM0/dian List of Refertases es: D. A. Stuas. Beesiro J. 3. Subers, Esquire ,
L A. Capes.NRC
- 8. A.McMou,NRC .
W. T. Russou, NRC -
J. R. Strosakler, NRC -
D. F. Lharoth/J. A. Colla, Jr., NRC T. Maestes, DNR l
1
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,47, 8FTV9M
- Desseost Control Dee'.
i
. . Osteber 87,1989 Sees d ,
IST OF MPERENCES ,
asittmore Oes and Electrie Revisiet of Proposal of Alterestive to ASMB 9ellet and .
Pressure Vessel Code Section m Requirossents l
(a)
Letter from Mr. O. C. Casel (BO&E) to NRC Desumset Control Desk ,
13,19e9, Propetal of Alternatives te ASME Code Seelies M Requirements !
NAC Staff Onidasse Letter on A$ME Rollef Regesets, dated Jessary 1978 (b)
April 1989, Westisshouse Sesam Generator Tube Plus latesrity Suminary Report.
(o) Electrie C&g:l=, WCAP-12344 Revision 1 .'
L Stress Cemelos Creeking Resistemos of Aueys 600 and 690 and Com
( (d) Metals la BWRs, July 1988. Electric Power Research Instiente, NP-5 rep 8ft (e)
Stress corrosien Crasklas Resisensse ofElectrie AlloysPower 600 Resterth and 690 in Asid Solutions at Blevated Tesapeestur:s, ossober 1983 ,
lastitute, NP 3048 Fleel Report Generseer Tullas. Testing of (f) Intergranular Stress Cerrosion Cracklas la steamAlloy GPO an Materials in Nuclear Power Systems- Water Reactors, TMS.1988 AYT Water, B. F. Mistia and C. E. Shoemaker, C (3) 30,1988 Cases of A5ME Boiler and Pressure Yessel Code Case N 20 3, November -
I (b)
Cases of A8ME Boller and Proesure Vessel code, Case N-474, to be pob!
(1) .
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Please be seus to seats C. M. Cruse /P. 3. Ram as year h ,
- 1. E..Donaea/R. P. IIslbel L C. DeVoues R. M. Douglass/R. F. Ash IR/M. 3. Mlersised C. C. Lawsonne,Oswilas F. J. Muses /M.
L 5. Pend /8. R. Busham n - .
L. 3. RusesR/J. R. Leeses J. M. 1lspbe, Jr.
W. J. L opeM/3. 8. Meatsomery ..
J. E Whilse R.C.DeYomas C. M. Rise -
- k. O.Senker J. J. Connolly O.J.PaHteen D. L. Shaw, Jr.
M. L. Seoes D. Y. Gast B. C. Rudell T.M.Kham -
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