Letter Sequence Other |
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MONTHYEARML20134K7911997-02-13013 February 1997 Forwards RAI to Complete Review of Licensee 970131 Submittal Re Proposed TS Changes to RCS Flow Limit at Plant,Units 1 & 2 Project stage: RAI ML20135E1151997-02-28028 February 1997 Forwards Request for Addl Info Re License Amend Request Change to RCS Flow Requirements to Allow Increased Steam Generator Tube Plugging Project stage: Request ML20135E7321997-03-0505 March 1997 Forwards Request for Addl Info Re Proposed TS Changes to Reactor Coolant Sys Flow Limit Project stage: RAI ML20137F2401997-03-25025 March 1997 Forwards Response to RAI Re 970131 Amend Request to Change Reactor Coolant Sys Flow Requirements to Allow Increased Steam Generator Plugging Project stage: Response to RAI ML20137X8791997-04-16016 April 1997 Provides Response to Questions Posed in 970320 Telcon Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging Project stage: Other ML20139A3031997-04-22022 April 1997 Forwards RAI Re Proposed TS Changes to Reactor Coolant Sys Flow Limit Concerning Radiological Controls for Plant Project stage: RAI ML20140E0901997-06-0909 June 1997 Forwards RAI Re Changes to Reactor Sys Flow Limit Amend Related to Reactor Sys.Based on Review,Addl Info Is Required to Complete Review Project stage: RAI ML20149J1841997-07-25025 July 1997 Forwards Request for Addl Info Re 970131 & 0416 Proposed Technical Changes to Reactor Coolant System Flow Limit, Calvert Cliffs Nuclear Power Plant,Units 1 & 2 Project stage: RAI ML20210M6511997-08-19019 August 1997 Forwards Response to 970422 & 0609 RAIs Re License Amend Request Change to RCS Flow Requirements to Allow Increased SG Tube Plugging Project stage: Other ML20217C7311997-09-29029 September 1997 Forwards Response to 970725 RAI Re License Amend Request Revising RCS Flow Requirements to Allow Increased SG Tube Plugging.Ts Page from 970609 License Amend Request to Convert to Improved Ts,Encl Project stage: Other ML20199B6611998-01-22022 January 1998 Provides Supplementary Responses to NRC 970422 & 0725 Requests for Addl Info for LAR Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging Project stage: Supplement ML20217K0961998-03-30030 March 1998 Forwards RAI Re RCS Flow Requirements to Allow Increased SG Tube Plugging.In Order to Expedite Staff Review,Response Requested by 980415 Project stage: Approval ML20216D6321998-04-0808 April 1998 Forwards Response to 980330 RAI Re LAR Change to RCS Flow Requirements to Allow Increased SG Plugging.Response Does Not Change No Significant Hazards Determination Previously Provided Project stage: Other ML20217D2921998-04-21021 April 1998 Responds to Request for Addl Info Re LAR Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging Project stage: Request ML20217D2301998-04-21021 April 1998 Submits Revised TS Pages for 970131 Application for Amends to Licenses DPR-53 & DPR-69 Re RCS Flow Requirements to Allow Increased SG Tube Plugging,As Requested by NRC in 980325 Telcon Project stage: Request ML20247R8811998-05-22022 May 1998 Concurs W/Listed License Condition for RCS Low Flow Amend Request for Units 1 & 2 Project stage: Request 1997-07-25
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20211J1611999-08-17017 August 1999 Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements 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] |
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"
CHART 1R II. CCUSE Ildtimore Gas t.nd Electric Company
? Vice President Calvert Cliffs Nuclear Power Plant Nuclear Energy 1650 Calven Cliffs Parkw ay Lusby, Maryland 20657 410 495-4455 leptember 29,1997 l
l l
U. S. Nuclear Regulatory Commission Washington,DC 20555 A'ITENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Responce to the July 25, 1997, Request for Additional Informaticit: License Amendrnent Request; Change to Reactor Coolant System Flow Requirements to Allow Increased Steam Generator Tube Plugging (TAC Nos. M97855 and M97856)
REFERENCES:
(a) Le;':r fran Mr. C. II. Cruse (DGE) to NRC Document Control Desk, dated January 31, 1997, License Amendment Request; Change to Reactor Coolant System Flow Requirements to Al'ow Increased Steam Generator Tube Plugging (b) Letter from Mr. A. W. Drnmerick (NRC) to Mr. C.11. Cruse (DGE),
dated July 25, 1997, Request for Additional Information - Proposed '
Technical (Specification) Changes to Reactor Coolant System Flow I!mit [], Calvert Cliffs Nuclear Power llaut, Unit Nos. I and 2 (TAC Nos. M97855 and M97856)
(c) Letter from Mr. C 11. Cruse (BGE) to NRC Document Control Desk,
) dated June 9,1997, Revision I to the License Amendment Request to Convert to the Improved Technical Specifications (TAC Nos. M97363 and M97364)
By letter dated January 31,199* l Reference a), Baltimore Gas and Electric Company (BGE) submitted a license amendment request _to the Nuclear Regulatory Commiwlon (NRC) to support operation of 1
Calvert Cliffs Units I and 2 with up to 2500 steam generator tubes plugged in each steam generator. By letter dated July 25,1997 (Reference b), the NRC requested additional information regarding the license amendment request. This letter provides BGE's response to References (b). In addition, this letter im%mits a marked-up page from the recently revised Improved Technical Specification (ITS) license az ..dment request (Reference c), which was not included in Referene: (a) for the easons explained below.
One of the proposed changes in Reference (aT is a revision to the current Technical Specification Table 4.7-1 to change the maximum allowable lift settings for Main Steam Safety Valves RV-3996/4004, RV-3997/4005, RV-399814]6, and RV-3999/4007 from 1065 psig to 1050 psig. This change is 9710020046 970929 ADOCK 0500 7 DR l
3,; /, :..
=.7 . Document Control Desk' 1 September 29,19972 -
- Page 2 j 4 necessary to support the seanalysis~of the Loss of Load and Loss of Feedwater Events, which' credit a =
more restrictive lift setting range for the highest set valves, in Reference (a), it w.:s noted that this
- change would not affect ITS, as the.lTS submittal proposed relocating this information from the Technical Specifications to the Inservice Testing Program. By Reference (c), BGE revised the ITS submittal. 'Ihe revised submittal proposes retaining the main steam safety valve lift settings in the ITS as
- indicated in Table 3.7.1-2. To accommodate this change, ITS Table 3.7.12 is marked up indicating the revised lift settings for the four highest set valves. This change is consistent with those proposed for the current Technical Specifications in Reference (a).
l Attachment (1) t; this letter provides BGE's response to_ the questions posed in References (b).
Attachment (2) is marked-up ITS Teble 3.7.12. The information contained in Attachments (1) and (2) -
does not change the No Significant llazards Determination presented in Reference (a). Should you have further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours,-
/
- STATE OF MARYLAND ~
- TO WIT:
L COUNTY OF CAlVERT -:
h -
- 1, Charles H. Cruse, being duly sworn, state that I am Vice President, Nuclear Energy Division, Baltimore Gas and Electric Compary (BGE), and that I am duly authorized to execute and file this L cense Amendment Request on behalf of BGE. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my -
personal knowledge, they are based.upon information provided by other BGE employees and/or consultants. Such information has been reviewed in accordance with company pmetice and I believe it to be reliable.
/ne & -Lv
/
J is A 11 of 9 WITNESS my Hand and Notarial Scal: A b 7 Lib
- Notary Public
. My Commission Expires: b k Date CHC/GT/dtm Attachments . _ (1) Response to NRC Request for AdditionalInformation dated July 25,1997
.(2) Marked-up Improved Technical Specificatica Page cc: R. S. Fleichman, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident inspector, NRC Director, Project Directorate 1-1, URC R.1. McLean, DNR A. W. Dromerick, NRC J. II. Walter, PSC r
ATTACIIMENT (1) 9 BALTIMORE GAS AND ELECTRIC COMPANY'S RESPONSE TO NRC REQUEST FOR ADDITIONAL INF01GIATION DATED JULY 25,1997 r- ___
Calvert CliJs Nuclear Power Plant Units 1 & 2 September 29,1997
,. ,s. .
ATTACllMENT (1) I IIALTIMOIG GAS AND ELECTRIC COMPANY
, RESPONSE TO NRC REQUEST FOR- ADDITIONAL INFORMATION DATED JULY 25,1997 NRC Ouestion Address concerns associated with reactor coolant pump loop-seal clearing and break orientation, and compliance with the requirements of 10 CFR $0.46(b), including concerns regarding metaVwater reaction, and long-term cooling. A non-proprietary submittal by Framatome Technologies incorporated (FTI) provided additional information to describe the concern and associatedphenomena.
The small-break loss-of-coolant accident (SBLOCA) scenario involving the principal safety concern involves long term cooling conditions in which the brevk si:e and orientation would be such that the primary system would not depressuri:e, limiting the emergency core cooling system injectionflow rate to that only capable ofmatching the core bolloffrate due to decay heat. Also in this scenario a column of water in the reactor coolant system pump suction loop seal would inhibit the vent path to the break and exert enough additionalpressure to the steam space above the core that the level in the core would be depressed below the top of the core. Should this condition exist as an equilibrium condition, core uncovery would be indefinite, since the attendant s'ecay heat rate would be small and virtually constant.
Under these ci?cimtstances, the cladding oxidation criteria of10 CFR $0.46 could be violated.
To address this concern in the near term, the licensee shouldprovide information to assure that the Calvert Chfs , bnts, in their present configurations (including plant design, technical specifications, procedures, analyses) will operate such that the criteria of10 CFR $0.46 will not be violatedfor it:
SDLOCA analyses in consideranan of the scenario (s) of concern. To confirm its near term assessment and address longer term concerns associated with this SBLOCA scenario, and the capability of this model to quantify the scenarlofs) of concern for ongoing operation andfuture con]Igurations, the licensee should describe its action plan to update its licensing basis SBLOCA model with 'toding and correlations to explicitly simulate the phenomenafor the scenarios) andplant configurations ofconcern as required by 10 CFR $0.46.
Information supplied by ABB/CE in support ofitsforthcoming updated SBLOCA evaluation model (S2M) confirons the potentialfor the scenario (s) ofconcernfor some plant designs, and addresses, both near term and long term, the associated concernsfor all des'gns licensed with the model. This model awaits NRC apt oval; however, vendor assistance may be available to respond to this questionfor the model used in the Calve-t Chffs SBLOCA analyses.
BGE Iksponic Asea Brown Boveri - Combustion Engineering (ABB-CE) is the Nuclear Steam Supply System vendor for Calvert Cliffs. ABB-CE also currently manufactures the fuel for Calvert Cliffs and provides our Emergency Core Cooling System performance evaluation. Reference (1) is the recent ABB CE response ta NRC concerning the Small Dreak Loss-oLCcvant Accident (SB LOCA) scenario discussed above for all ABB-CE plantr.
As discussed in Reference (1), Calvert Cliffs is a " Class A" ABB-CE plant. This is a plant for which the Reactor Coolant System (RCS) loop seal elevation is higher than the top of the active core. Also as discussed in Reference (l), since the Calvert Cliffs loop seal elevation is above the top of the core, Calvert Cliffs will not experience hydrostatically-induced core uncovery due to loop seal clearing and/or refilling behavior. The RCS hydrostatic pressure balance during the SB LOCA scenario of concern is a function of the loop seal elevation. This pressure balance controls the potential for core uncovery. A 1
ATTACllMENT (1)
HALTIMORE GAS AND ELECTRIC COMPANY
- . RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION DATED JULY 25,1997 plant with a loop seal elevation higher than the top of the core is not susceptible to loop seal clearing induced core uncovery during a SB LOCA. Therefore, the core collapsed liquid level during the time of highest differential pressure will be abave the top of the core. As a result, the current Emergency Core Cooling System performance evaluation for Calvert Cliffs is not affected by the above loop seal clearing -
concern, and the criteria of 10 CFR 50.46 will not be violated.
11.e Calvert Cliffs Emergency Opuating Procedures are based on ABB CE guidance provided in CEN 152," Combustion Engineering Emergency Procedure Guidelines." This guidance, with respect to operator response to the SB LOCA scenario of concern, is described in more detail in Reference (1). The Calvert Cliffs optimal procedure for LOCA directs RCS cooldown and depressurization, based on a reasonable time frame for operator actions, within 20 minutes of implementing the LOCA procedure.
This rapid, controlled RCS depressurization will significantly increase the liigh Pressure Safety injection delivery to the RCS and reduce the inventory loss through the break. Although, as discussed above, the loop seal elevation at Calvert Cliffs will prevent the core collapsed liquid level from falling below the top of the core (aner the initial blowdown and recovery) without credit for operator action, the forced cooldown implemented by the operators will avert the conditions that could lead to sustained core uncovery.
As discussed in Reference (1), the ABB-CE SB LOCA evaluation model (the model currently used for Calvert Cliffs) conservatively simulates the phenomena for this scenario and plant configurations of concern as required by 10 CFR 50.46. Under conservative analysis conditions, tha calculations presented in Section 5 of Enclosure (1) to Reference (l' demonstrate that the ABB-CE SB LOCA evaluation model adequately calculates loop seal clearing and the hydrostatic pressure distributions that may act to uncover the core during the clearing process including the SB LOCA scenarios of concern. Furthermore, the results of these (Section 5) calculations show that the SB LOCA evaluation model adequately evaluates the impact of break orientation by virtue ofits elevation dependent modeling capabilities and separated tiow methodologies. Therefore, the current Calvert Cliffs SB LOCA evaluation model uses the noding and correlations that are able to quantify the scenario (s) of concern for ongoing operation and futurr configurations. As a result, an updating of the Calvert C!iffs licensing basis SB LOCA movcl is not required to address this concern.
REFERENCE (1): ABB-CE letter to NRC, LD-97-010, " Additional Response to NRC Request for Additional Information Regarding CENPD-137, Supplement 2 P," dated April 3,1997 2