Letter Sequence Request |
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TAC:M97363, TSTF-19, TSTF-88, TSTF-64 (Approved, Closed) TAC:M97364, TSTF-19, TSTF-88, TSTF-64 (Approved, Closed) |
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MONTHYEARML20137G7751997-03-27027 March 1997 Forwards Response to RAI Re Section 1.0 of TS Change Request to Convert to Improved TSs Project stage: Response to RAI ML20140H5451997-05-0707 May 1997 Requests Addl Info Re 961204 TS Change Request to Convert to Improved TS for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 Project stage: Other ML20141H4791997-05-16016 May 1997 Forwards RAI Re TSs Change Request to Convert to Improved TSs for Plant,Units 1 & 2 Project stage: RAI ML20140B0491997-05-29029 May 1997 Forwards RAI Re License 961204 Request to Convert Plant, Units 1 & 2 Current TS to Improve Ts.Response Requested within 15 Days of Receipt of Ltr Project stage: RAI ML20140G4361997-06-0606 June 1997 Forwards Request for Addl Info Re License Amend Request to Convert Plant Current TS to Its.Request Seeks to Clarify ITS Sections 3.3.3 Through 3.3.12 Project stage: RAI ML20140J0271997-06-0909 June 1997 Forwards Rev 1 to License Amend Request to Convert to Improved TSs as Discussed in 970204 Meeting W/Nrc.Changes Result from Industry or NRC Action on Generic Changes & Issues Identified by Plant Personnel Project stage: Meeting ML20141A0731997-06-11011 June 1997 Forwards RAI Re TSs Change Request to Convert to Improved TSs for Plant,Units 1 & 2.Response Requested to RAI That Seeks to Clarify Improved TSs Section 3.7 & 3.8.Section 3.8 Does Not Include 3.8.4,3.8.5 & 3.8.6 Project stage: RAI ML20141B9441997-06-18018 June 1997 Forwards Response to 970507 RAI Re LAR to Convert to Improved TS Section 5.0 for Administrative Controls Project stage: Other ML20149H5781997-07-21021 July 1997 Forwards Rev 2 to Bge'S Original Application to Convert to Improved Sts,Per NUREG-1432.Changes Result from Responses Provided in to NRC 970507 Rai.Tables in Attachment 1 Describes Each of Changes Encl Project stage: Request ML20210K9531997-08-14014 August 1997 Forwards Rev 3 to LAR Re Conversion to Improved Ts.Changes Reflect Removal of TSTF-113,as Well as Other Changes Identified by Plant Personnel Project stage: Other ML20210T8631997-09-10010 September 1997 Forwards Response to 970529 RAI Re Section 3.4 of Application to Convert to Improved TS & Rev 5 to Original License Amend Application Project stage: Request ML20217G3701997-10-0606 October 1997 Forwards Response to 970611 RAI Re License Amend Request to Convert to Improved Sts.Responses for Section 3.7,list Describing Each of Changes & Revs to Improved TS Section Also Encl Project stage: Other ML20217G3381997-10-0606 October 1997 Forwards Response to NRC 970529 RAI Re TS Change Request to Convert to Improved Sts.Responses for Section 3.6 Provided in Attachment 1.Rev 7 to Original License Amend Application Also Encl Project stage: Other ML20198K3261997-10-20020 October 1997 Forwards Response to 970529 & 0606 RAI Re License Amend Request to Convert to Improved Sts.Response to Section 303 Provided in Attachment 1.Rev 8 to Original License Amend Also Encl Project stage: Other ML20212F3951997-10-22022 October 1997 Forwards Request for Addl Info Re TS Change Request to Convert to Improved TS for Units 1 & 2 Project stage: RAI ML20217K6051997-10-23023 October 1997 Forwards Response to 970611 RAI Re License Amend Request to Convert to Improved Std Tss.Response to Section 3.8 Provided in Attachment 1.Rev 8 to Original License Amend,Encl Project stage: Other ML20198R7181997-11-0505 November 1997 Forwards Responses to 970611 RAI Re Rev 10 to LAR to Convert to Improved TS & Rev 10 to Original License Amend Application Project stage: Other ML20199C0501997-11-0707 November 1997 Requests Addl Info Re TSs Change Request to Convert to Improved STS for Plant.Licensee Should Prepare Similar Tables for Plant Conversion as NRC Writes Safety Evaluation Project stage: Approval ML20198K9591998-01-12012 January 1998 Rev 11 to 961204 Application for Amends to Licenses DPR-53 & DPR-69,converting to Improved Sts,Per NUREG-1432 Project stage: Request ML20199G9451998-01-28028 January 1998 Submits Rev 12 to Util 961204 Application for Amends to Licenses DPR-53 & DPR-69 to Convert to Improved Tss,As Result of Discussion W/Nrc.Revised Pages for Tables,Min Rev to Summary of Changes & Rev 12 to Improved TS Encl Project stage: Request ML20216D0051998-03-0505 March 1998 Refers to License Amend Request Submitted by Bg&E on 961204 to Convert Calvert Cliffs Current TS to Improved Ts.Drfat SE W/Ogc Comments Encl.Nrc & Bg&E Will Meet on 980319 to Review Status of Draft SE Comments Project stage: Draft Approval 1997-05-07
[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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l CHARES H. CROSE Baltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410 495-4455 July 21,1997 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 Revision 2 to the License Amendment Request to Convert to the Improved Technical Snecifications (TAC Nos. M97363 and M97364)
REFERENCES:
(a) Letter from A. W. Dromerick (NRC) to C. H. Cruse (DGE), dated May 7,1997, Request for Additional Information Regarding the License Amendment Request to Convert to the Improved Technical Specifications (TAC Nos. M97363 and M97364)
(b) Letter from C. H. Cruse (BGE) to Document Control Desk (NRC), dated June 18, 1997, Response to Request for Additional Information Regarding the License Amendment Request to Convett to the Improved Technical Specifications (TAC Nos. M97363 and M97364)
Reference (a) transmitted questions regarding Sections 4.0 and 5.0 of Baltimore Gas and Electric
/
Company's application to convert to the Improved Standard Technical Specifications. The responses I were provided in Reference (b).
Attached to this letter is Revision 2 to the original license amendment application. These changes result 6/
from the responses provided in Reference (b), as well as other changes identified by plant personnel.
Changes to the No Significant Hazards Considerations discussions are included where appropriate.
To assist in reviewing this revision, a table describing each of the changes is attached (Attachment 1).
All of the material for each change is grouped by change in Attachment (2). Attachment (3) provides the revision by Improved Technical Specification Section for ease of replacing pages in the original amendment request. Page replacement instructions are provided. All changes are marked with revision bars and are labeled Revision 2.
j 9707250052 970721 PDR ADOCK 05000317 b
P PDR DdO900 . . . . .
l Document Control Desk July 21,1997 Page 2 l
The Plant Operations and Safety Review Committee and the Offsite Safety Review Committee have reviewed revisions resulting in changes to the No Significant Hazards Considerations and concur that operation with the proposed revisions will not result in an undue risk to the health and safety of the public. Should you have questions regarding this matter, we will be pleased to discuss them with you.
l Very truly yours, l .
d]// sf k#
STATE OF MARYLAND :
- TO WIT:
COUNTY OF CALVERT :
I, Charles H. Cruse, being duly sworn, state that I am Vice President, Nuclear Energy Division, Baltimore Gas and Electric Company (BGE), and that I am duly authorized to execute and file this License 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 pr< 'ce and I believe it to be reliable, w JA &&
/
S se ibed and sworn before me, a Notary Public in and for the State of Maryland and County of
, this fl4Eday of Omfu idn1J ,1997.
WITNESS my Hand and Notarial Seal: bfM1AiJb MILb ;
Notary Public My Commission Expires: b h Date CHC/ PSF / dim Attachments: (1) Summary of Changes (2) Amendment Revision by Change (3) Amendment Revision by ITS Section cc: (With Attachment 1 only)
R. S. Fleishman, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC A. W. Dromerick, NRC R.1. McLean, DNR Director, Project Directorate 1-1, NRC J. H. Walter, PSC 1
i ATTACHMENT (1) 1 1
l
]
4 4 IMPROVED TECHNICAL SPECIFICATIONS, REVISION 2 )
i i
SUMMARY
OF CHANGES
\
l l
l 1
Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant July 21,1997
ATTACHMENT (1) l IMPROVED TECIINICAL SPECIFICATIONS, REVISION 2
SUMMARY
OF CHANGES
- 1. A new Discussion of Deviation has been provided (Discussion of Deviation 27 to Section 5.0) to describe the ' current Calvert Cliffs requirement that the operations manager hold or have held a senior reactor operator license. This Discussion of Deviation justifies the change to NUREG-1432 Specification 5.2.2.f [ Improved Technical Specification (ITS) 5.2.2.f] as -
requested by the Nuclear Regulatory Commission (NRC) in their comments to Section 5.0 (comment 3).
- 2. Discussion of Deviation 5 to Section 5.0 has been revised to provide the Current Technical Specification (CTS) Amendment number that added the Shift Technical Advisor requirements to the Calvert Cliffs CTS. This revised Discussion of Deviation justifies the change to NUREG-1432 Specification 5.2.2.g (ITS 5.2.2.g) based on current licensing basis. This was requested by the NRC in their comments to Section 5.0 (comment 4).
- 3. Discussion of Change LA.3 to Section 5.0 has been revised to state that the relocated details will be moved to the Quality Assurance Policy, which is controlled by the provisions of 10 CFR 50.54(a). The change control process was requested to be provided by the NRC in their comments to Section 5.0 (comment 5).
- 4. A new Discussion of Change has been provided (Discussion of Change M.6 to Section 5.0) to discuss the addition of the prefilters to the pressure drop tests of CTS 4.6.3.1.d.1,4.6.6.1.d.1, 4.7.6.1.e.1,4.7.7.1.d, and 4.9.1.2.d.1 (ITS 5.5.11.d). This change was requested by the NRC in their comments to Section 5.0 (comment 13).
- 5. A new Discussion of Deviation has been provided (Discussion of Deviation 28 to Section 5.0) to describe the current Calvert Cliffs requirement for the testing of the Iodine Removal System ;
filter trains. This Discussion of Deviation justifies the change to NUREG-1432 l Specification 5.5.11.c (ITS 5.5.11.c) as requested b / the NRC in their comments to Section 5.0 (comment 14).
- 6. Discussion of Deviation 11 to Section 5.0 has been revised to clearly state that the outdoor liquid storage tank requirements of Section 5.5.12 are being deleted. The NUREG markup of this l Section has also been annotated with this Discussion of Deviation number. This change was requested by the NRC in their comments to Section 5.0 (comment 15) in order to more clearly justify the change to NUREG-1432.
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- 7. A new Discussion of Deviation has been provided (Discussion of Deviation 29 to Section 5.0) to .
describe the current Calvert Cliffs gas storage tank radioactivity limit. The Discussion of I Deviation justifies the change to NUREG-1432 Specification 5.5.12.b (ITS 5.5.12.b) as requested by the NRC in their comments to Section 5.0 (comment 16).
- 8. Discussion of Changes M.4 and M.5 to Section 5.0 have been combined into Discussion of Change M.4, and Discussion of Change A.26 to Section 5.0 has been replaced with Discussion of l Change L.3. These Discussions relate to the changes to the current Calvert Cliffs diesel i
generator stored fuel oil testing requirements. Discussion of Change M.4 now describes the addition of the new fuel oil testing requirements and Discussion of Change L.3 describes the i change in the stored fuel oil testing requirements. An associated No Significant Hazards 1
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OF CHANGES Consideration has also been provided. These changes were requested by the NRC in their comments to Section 5.0 (comments 17.a,17.b, and 17.c).
- 9. Discussion of Deviation 25 to Section 5.0 has been revised to clearly state the reason for substituting a gravimetric analysis requirement for total particulates in ITS 5.5.13.c instead of the ;
u ASTM D-2276-89, Method A-2 or A-3 requirements provided in NUREG-1432 Specification 5.5.13.c. This change was requested by the NRC in their comments to Section 5.0 I (comment 18).
- 10. Discussion of Deviation 12 to Section 5.0 has been revised to clearly state the reason for changing the total particulate test frequency from 31 days in NUREG-1432 to 92 days in the ITS. j This was requested by the NRC in their comment to Section 5.0 (comment 19). l
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- 11. Discussion of Change LA.6 to Section 5.0, which discusses the relocation of details on ,
components that require Type B testing, has been replaced with Discussion of Change L.4. The l
new Discussion of Change justifies the deletion of the specific testing requirements, since they l are duplicative of requirements that are maintained in the ITS. An associated No Significant Hazards Consideration has also been provided. This change responds to the NRC comments to Section 5.0 (comments 20 and 30).
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- 12. The Battery Inspection Program has been deleted from the Cah crt Cliffs ITS submittal. This i change only affects the portion of the program in Section 5.0. The portions of the submittal I affected by the Rattery Inspection Program deletion that are described in Section 3.8 will be deleted from the Calvert Cliffs ITS in a later revision to the subm .ttal. This was requested by the NRC in a phone conversation with BGE while discussing NRC comment 21 to Section 5.0.
- 13. A statement precluding the inclusion of the occupational radiation exposure due to the Independent Spent Fuel Storage Installation in the Units 1 and 2 Occupational Radiation Exposure Report required by ITS 5.6.1 has been added to the Note ofITS 5.6.1. This restriction is consistent with CTS 6.6.1 footnote *. A new Discussion of Deviation has also been provided (Discussion of Deviation 30 to Section 5.0) to describe the addition of this statement to NUREG-1432 Specification 5.6.1 Note, as requested by the NRC in their comments to l Section 5.0 (comment 22). l
- 14. A bracketed sentence in the NUREG markup of NUREG-1432 Specification 5.6.2 has been i retained. The sentence was inadvertently deleted in the original submittal; however, the sentence I was correctly included in the typed Calvert Cliffs ITS and the CTS markup. The Discussion of i Deviation thatjustified deletion of this sentence (Discussion of Deviation 16 to Section 5.0) has i been modified to reflect this change, as requested by the NRC in their comments to Section 5.0 (comment 24).
l 15. Discussion of Change LA.8 to Section 5.0 has been revised to state that the Offsite Dose Calculation Manual (ODCM) will be the location of the relocated details. (One of the details is duplicative of 10 CFR 50.36a and will not be included in the ODCM). This change was requested by the NRC in their comments to Section 5.0 (comments 25 and 30). In addition, the phrase ", as modified by approved exemptions" has been added to the Calvert Cliffs ITS for l
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OF CHANGES clarity, since one of the relocated details is an exemption to 10 CFR 50.36a. A new Discussion of Deviation has also been provided (Discussion of Deviation 31 to Section 5.0) to describe the addition of this phrase.
- 16. Discussion of Change A.17 to Section 5.0 has been revised to clearly state why the addition of the Post Accident Monitoring (PAM) Instrumentation Report to Section 5.0 is administrative. In addition, new Discussion of Changes M.7 and L.5 to Section 5.0 have been provided to justify changes to the PAM Instrumentation Report required by CTS 3/4.3.3.1 Action 30, 3/4.3.3.6 Actions 34 and 35, and 3/4.6.5.1 Action a.l. An associated No Significant Hazards Consideration has also been provided. These changes respond to the NRC comments to Section 5.0 (comment 28).
- 17. Discussion of Change A.22 to Section 5.0 has been revised to clarify why the associated change (the addition of a Safety Function Determination Program) is administrative and to cross-reference the less restrictive Discussion of Change in Section 3.0. This change responds to the NRC comments to Section 5.0 (comment 29).
- 18. Discussion of Change LA.5 to Section 5.0 has been revised to state that the Technical Requirements Manual will be the location of the relocated requirements. This change was requested by the NRC in their comments to Section 5.0 (comment 30).
- 19. Discussion of Change LA.7 to Section 5.0 has been deleted. Most of the CTS details relocated by LA.7 have been incorporated into the ITS. These details affect the frequencies of the tests required by the Ventilation Filter Test Program. In addition, due to maintaining the CTS frequencies, new Discussion of Deviation 32 to Section 5.0 has been provided justifying these changes to NUREG-1432. The remainder of the details are either deleted with new Discussion of Change L.6, or with modified Discussion of Change A.23. An associated No Significant Hazards Consideration has also been provided. This change responds to the NRC comments to Section 5.0 (comment 30). Also, new Discussion of Deviation 33 to Section 5.0 has been provided justifying deleting the phase "at the system flowrate specification below [i 10%]" in NUREG-1432 Specification 5.5.11 since it is redundant to each of the subsequent requirements that require a specific flowrate.
- 20. Discussion of Change LA.4 to Section 5.0 has been revised to state that the Technical Requirements Manual will be the location of the relocated requirements. This change was requested by the NRC in their comments to Section 5.0 (comment 34).
- 21. Discussion of Change A.7 to Section 5.0 has been revised to spell out the acronym "NRC."
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