Letter Sequence RAI |
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MONTHYEARML20151X8521998-09-0202 September 1998 Forwards RAI Re Plant,Units 1 & 2 Integrated Plant Assessment Repts for Containment Isolation Group,Containment Spray Sys & Primary Containment Heat & Ventilation Sys. Response Requested within 30 Days of Receipt of Ltr Project stage: RAI ML20151Y1531998-09-0303 September 1998 Forwards Request for Addl Info for Review of Units 1 & 2 Integrated Plant Assessment Rept Containment Spray Sys Project stage: RAI ML20151V3711998-09-0404 September 1998 Forwards Request for Addl Info Re Licensee 980408 Renewal Application,Specifically,Integrated Plant Assessment for Heating & Ventilation Systems Project stage: RAI 1998-09-03
[Table View] |
Forwards RAI Re Plant,Units 1 & 2 Integrated Plant Assessment Repts for Containment Isolation Group,Containment Spray Sys & Primary Containment Heat & Ventilation Sys. Response Requested within 30 Days of Receipt of LtrML20151X852 |
Person / Time |
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Site: |
Calvert Cliffs ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
09/02/1998 |
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From: |
Dave Solorio NRC (Affiliation Not Assigned) |
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To: |
Cruse C BALTIMORE GAS & ELECTRIC CO. |
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References |
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TAC-M99211, TAC-M99221, TAC-M99224, TAC-MA0603, TAC-MA0604, TAC-MA1038, TAC-MA1039, TAC-MA1106, TAC-MA1107, TAC-MA603, TAC-MA604, NUDOCS 9809170275 |
Download: ML20151X852 (9) |
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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 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) 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 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 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 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 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 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 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 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 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 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 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 ML20196E0371999-06-16016 June 1999 Forwards Insp Repts 50-317/99-03 & 50-318/99-03 on 990321-0508.Apparent Violation Being Considered for Escalated Enforcement Action ML20207G4331999-06-0707 June 1999 Informs That in Response Request by Nrc,Fema Evaluated Adequacy of Evacuation Plans & Training of Local First Responders for Area Around Ccnpp.Copy of FEMA & Encl to Ltr,Which Provides FEMA Recommendations Encl ML20207G4701999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20207B2491999-05-21021 May 1999 Forwards Insp Repts 50-317/99-04 & 50-318/99-04 on 990405-16.No Violations Noted.Insp Revealed Few Potential & Plausible Aging Effects NRC Team Determined Should Be Included in License Renewal Application ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206A6171999-04-22022 April 1999 Responds to Request for Statistics on Allegation Re Plant by J Osborne.Encl Tables Provides Breakdown of Allegations by Source Category for Allegations Receive in CY95-98 & First Six Month of 1999 ML20205R0961999-04-15015 April 1999 Forwards Insp Repts 50-317/99-01 & 50-318/99-01 on 990131- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20205P1381999-04-0909 April 1999 Discusses 990223 Ppr.Forwards Plant Issues Matrix & Insp Plan.Since Spring 1998 Unit 1 Operated at Essentially Full Power.Unit 2 Had Similar Power History Except for Jul 1998 Manual Reactor Trip Due to Small Bore Pipe Steam Leak ML20205P1281999-04-0808 April 1999 Forwards Monthly Status Rept on Licensing Activities & Regulatory Duties of NRC for Mar 1999.Targets for Licensing Action Age & Completion Rates & License Renewal Process for Calvert Cliffs Remains on Schedule ML20205E5511999-03-26026 March 1999 Forwards Insp Repts 50-317/99-02 & 50-318/99-02 on 990208-12.No Violations Noted.Insp Was First of Three Planned Visits to Verify Ccnpp License Renewal in Compliance with Requirements of Rule for License Renewal ML20205G8841999-03-24024 March 1999 Discusses Bg&E Application Filed on 980408 for Renewal of Operating Licenses DPR-53 & DPR-68 for Calvert Cliffs Units, 1 & 2.For Listed Reasons,Partial Exemption from 10CFR170 Fees Granted IAW 10CFR170.11(b)(1) ML20205B0291999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of License Renewal Application for Plants,Units 1 & 2,dtd 980408,that Staff Determines Has Generic Value to Industry ML20204H6281999-03-21021 March 1999 Forwards SER Reflecting Status of Staff Review of Util License Renewal for Calvert Cliffs Nuclear Power Plants, Units 1 & 2 ML20207E9641999-03-0404 March 1999 Forwards Insp Repts 50-317/98-12 & 50-318/98-12 on 981213- 990130 & Notice of Violation Re Failure of Maint Workers to Tighten Bolting for Svc Water Heat Exchanger ML20207G8631999-02-25025 February 1999 Forwards Operator Initial Exam Repts 50-317/99-301OL & 50-318/99-301OL on 990122 & 25-29 (Administration) & 990201- 05 (Grading).All Applicants Passed All Portions of Exams ML20203D3981999-02-0505 February 1999 Forwards Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20203A6141999-02-0303 February 1999 Submits Details on Listed Areas Re Inspection Plan of Insp Scheduled for 990203 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20199G4121999-01-20020 January 1999 Forwards SE Accepting Util USI A-46 Implementation Program for Plant ML20199K8481999-01-19019 January 1999 Forwards Insp Repts 50-317/98-11 & 50-318/98-11 on 981025-1212.No Violations Noted ML20199L6621999-01-19019 January 1999 Informs That Licensee Authorized to Administer Initial Written Exam to Listed Applicants on 990122.NRC Region I Operator Licensing Staff Will Administer Operating Test to Applicants ML20199F4101999-01-0808 January 1999 Forwards SE Accepting Util 960213,0725 & 981202 Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety- Related Power-Operated Gate Valves ML20198S4291999-01-0707 January 1999 Requests Addl Info Re License Renewal Application as Application Relates to Staff Position on Environ Qualification ML20198S7491999-01-0707 January 1999 Forwards SER Accepting Licensee ,Suppl by 980424 & 1124 Ltrs Proposing Changes to Rev 49 of Calvert Cliffs Nuclear Power Plant Quality Assurance Program Description in Accordance with 10CFR50.54(a)(3) ML20196K2991999-01-0404 January 1999 Forwards Notice of Consideration of Approval of Transfer of Facility Operating License & Matl License & Opportunity for Hearing in Response to Application ML20202D0271998-12-15015 December 1998 Forwards Notice of Withdrawal of Application for Amend to License DPR-69.Proposed Change Would Have Modified Svc Water Head Tanks.Without Encl ML20198L3431998-12-12012 December 1998 Forwards Insp Repts 50-317/98-10 & 50-318/98-10 on 980706-10 & 1118.Insp Rept Documents App R Issues Which Constituted Violations of NRC Requirements.Nov Not Issued Because, Violations Identified by Licensee Staff as Part of C/A ML20198B1791998-12-10010 December 1998 Advises of Planned Insp Effort Resulting from Calvert Cliffs NPP Review Conducted on 981110.Details of Insp Rept for Next 6 Months & Historical Listing of Plant Issues Considered During Process Encl 1999-09-08
[Table view] |
Text
_ _
. Mr. Charl:s H. Crus), Vice Presid:nt September 2,1998 Nucirr En;rgy Division Baltimore Gas and Electric Company 1650 Calvert Chffs Parkway Lusby, MD 20657-47027
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 & 2, INTEGRATED PLANT ASSESSMENT REPORTS FOR THE CONTAINMENT ISOLATION GROUP, CONTAINMENT SPRAY SYSTEM, AND PRIMARY CONTAINMENT HEATING AND VENTILATION SYSTEM (TAC NOS. MA0603, MA0604, M99211, MA1038, MA1039, M99221, MA1106, MA1107, AND M99224)
Dear Mr. Cruse:
By letters dated November 14,1997, January 21,1998, and March 3,1998, Baltimore Gas and Electric Company (BGE) submitted for review the Containment Isolation Group (5.5),
Containment Spray System (5.6), and Primary Containment Heating and Ventilation System (5.118) integrated plant assessment technical reports, respectively, as attached to the
Request for Review and Approval of System and Commodity Reports for License Renewal."
BGE requested that the Nuclear Regulatory Commission (NRC) staff review reports 5.5,5.6, and 5.118 to determine if these reports meet the requirements of 10 CFR 54.21(a)," Contents of application-technical information," and the demonstration required by 10 CFR 54.29(a)(1),
" Standards for issuance of a renewed license," to support an application for license renewal if BGE applied in the future. By letter dated April 8,1998, BGE formally submitted its license renewal application.
The NRC staff has reviewed reports 5.5,5.6, and 5.118 against the requirements of 10 CFR 54.21(a)(1),10 CFR 54.21(a)(3). By letter dated April 4,1996, the staff approved BGE's methodology for meeting the requiremena of 10 CFR 54.21(a)(2). Based on a review of the information submitted, the NRC staff has itsntified in the enclosures, areas where additional
)
information is needed to complete its review l Please provide a schedule by letter or telephonically for the submittal of your responses within 30 days of the receipt of this letter. Additionally, the NRC staff would be willing to meet with BGE prior to the submittal of the responses to provide clarifications of the staffs requests for additionalinformation.
Sincerely, W
l N
David L. Solorio, Project Manager License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
Request for Additional Information (3) cc w/enels: See next page DISTRIBUTION:
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PDR ADOCK 05000317 P PDR
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!t Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos.1 and 2 cc:
Mr. Joseph H. Walter, Chief Engineer President Public Service Commission of l Calvert County Board of Maryland Commissioners Engineering Division 175 Main Street 6 St. Paul Centre Prince Frederick, MD 20678 Baltimore, MD 21202-6806 James P. Bennett, Esquire Kristen A. Burger, Esquire Counsel Maryland People's Counsel Baltimore Gas and Electric Company 6 St. Paul Centre P.O. Box 1475 Suite 2102 Baltimore, MD 21203 Baltimore, MD 21202-1631 l
Jay E. Silberg, Esquire Patricia T. Birnie, Esquire Shaw, Pittman, Potts, and Trowbridge Co-Director 2300 N Street, NW Maryland Safe Energy Coalition Washington, DC 20037 P.O. Box 33111 Baltimore, MD 21218 Mr. Thomas N. Prichett, Director NRM Mr. Loren F. Donatell Calvert Cliffs Nuclear Power Plant NRC Technical Training Center 1650 Calvert Cliffs Parkway 5700 Brainerd Road Lusby, MD 20657-4702 Chattanooga, TN 37411-4017 Resident inspector David Lewis U.S. Nuclear Regulatory Commission Shaw, Pittman, Potts, and Trowbridge P.O. Box 287 2300 N Street, NW St. Leonard, MD 20685 Washington, DC 20037 Mr. Richard I. McLean Douglas J. Walters ,
Nuclear Programs Nuclear Energy Institute Power Plant Research Program 17761 Street, N.W. l Maryland Dept. of Natural Resources Suite 400 Tawes State Office Building, B3 Washington, DC 20006-3708 !
Annapolis, MD 21401 DJW@NEl.ORG Regional Adminisyator, Region I Barth W. Doroshuk l' U.S. Nuclear Regulatory Commission Baltimore Gas and Electric Company 475 Allendale Road Calvert Cliffs Nuclear Power Plant King of Prussia, PA 19406 1650 Calvert Cliffs Parkway NEF 1st Floor Lusby, Maryland'20657 l
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DMatthews (DBM)
CGrimes (ClG)
TEssig (THE) .
GLainas (GCL)
JStrosnider (JRS2)
GHolahan (GMH)
SNewberry (SFN)
GBagchi(GXB1)
RRothman (RLR) ' l JBrammer (HLB)
CGratton (CXG1)
JMoore (JEM)
MZobler/RWeisman (MLZ/RMW)
'SBajwa/ADromerick (SSB1/AXD) i' LDoerflein (LTD) l l BBores (RJB)
SDroggitis (SCD)
RArchitzel(REA)
' Craig (CMC 1) l LSpessard (RLS) i RCorreia (RPC)
RLatta (RML1) i l EHackett (EMH1) i AMurphy (AJM1)
TMartin (TOM 2) I
. DMartin (DAM 3)
GMeyer (GVM)
WMcDowell(WDM)
SStewart (JSS1)
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- SDroggitis (SCD) l l- DSolorio (DLS2)
PDLR Staff TMarsh (LBM) l GHubbard (GTH)
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-O REQUEST FOR ADDITIONAL INFORMATION I CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS.1 & 2 CONTAINMENT ISOLATION GROUP INTEGRATED PLANT ASSESSMENT. SECTION 5.5 DOCKET NOS. 50 317 AND 50-318 Section 5.5.1 - Scoolna
- 1. Clarify whether all the containment isolation valves listed in Table 5-3, " Containment l Isolation Valves," of the Calvert Cliffs Nuclear Power Plant Updated Final Safety Analysis ,
Report subject to an aging management review. For any valves that are not, provide the j basis for their exclusion. )
l Section 5.5.2 - Aalna Manaaement l l
- 2. In Groups 1 and 2 under aging management programs and demonstration of aging I management, the statement is made that the occurrence of crevice corrosion, general .
corrosion, microbiologically induced corrosion, and pitting is expected to be limited and I not likely to affect the intended function of the Group 1 and 2 components. Provide the basis for this conclusion.
- 3. ASME Code Section Ill, ANSI B31.1 and ANSI B31.7 contain certain fatigue analysis requirements. For ASME Code Class 1 components and ANSI B31.7 piping, the Code requires the calculation of the cumulative usage factor. For ASME Code Class 2 and 3 components, and ANSI B31.1 piping, the Code specifies allowable stress levels based on the number of anticipated transients or thermal cycles. Explain why, in Table 5.5-2, fatigue is not considered as a plausible aging mechanism for the containment isolation (Cl) group components, which are designed in accordance with ANSI B31.7 or similar requirements of ASME Code Section Ill.
- 4. ASME Code Section XI requires system leakage tests and system hydrostatic tests along with certain visual inspections for Class 2 and 3 components. Describe, in summary form, how these Section XI requirements are applied to Cl group components.
- 5. Are there any parts of the systems, structures, or components described in Section 5.5 that are inaccessible for inspections? If so, describe what aging management program will be relied upon to maintain the integrity of the inaccessible areas. If the aging management program for the inaccessible areas is an evaluation of the acceptability of inaccessible areas based on conditions found in surrounding accessible areas, please provide information to show that conditions would exist in accessible areas that would indicate the presence of or result in degradation to such inaccessible areas. If different i aging effects or aging management techniques are needed for the inaccessible areas, l please provide a summary to address the following elements for the inaccessible areas:
- (1) Preventive actions that will mitigate or prevent aging degradation; (2) Parameters monitored or inspected relative to degradation of specific structure and component Enclosure 1 l
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intended functions; (3) Detection of aging effects before loss of structure and component intended functions; (4) Monitoring, trending, inspection, testing frequency, and sample size to ensure timely detection of aging effects and corrective actions; (5) Acceptance criteria to ensure structure and component intended functions; and (6) Operating experience that provides objective evidence to demonstrate that the effects of aging will ;
be adequately managed. ;
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REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS.1 & 2 CONTAINMENT SPRAY SYSTEM INTEGRATED PLANT ASSESSMENT. SECTION 5.6 DOCKET NOS. 50 317 AND 50 318 Section 5.6.1 - Scanina
- 1. Section 6.4.2 of the Calvert Cliffs Nuclear Power Plant (CCNPP) Updated Final Safety Analysis Report (UFSAR) states that "It is expected the containment spray will be effective in removing fission products from the containment atmosphere." Discuss why this intended function is not included as part of the system description or the system scoping results in Section 5.6 of the license renewal application (LRA). If this intended function is included, describe the components included within the scope of license renewal and subject to an aging management review, if not, justify why this function is excluded. ,
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- 2. Discuss why the shutdown cooling intended function, as described in the CCNPP l UFSAR is not included as one of the system scoping results in Section 5.6.1.1 of the LRA. If this intended function is included, describe the components included within the scope of license renewal and subject to an aging management review. If not, justify why this function is excluded.
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- 3. Provide the basis for excluding spray nonles shown in Figure,5.6-1 in Section 5.6.1.1 j from the scope oflicense renewal.
- 4. Chapter 6 of the CCNPP UFSAR states that the containment spray system supplies the emergency dousing noules for the iodine removal units. The ability to put out charcoal fires due to decay heat from buildup of fission products, is normally relied upon at some nuclear power plants as an emergency dousing function. Provide the basis for not including the ability of the containment spray system to supply the emergency dousing noules for the iodine removal units as an intended function in Section 5.6.
4 Section 5.6.2 - Aalna Manaaement i 5. Are there any parts of the systems, structures,' or components described in Section 5.6 that are inaccessible for inspection? If so, describe what aging management program will be relied upon to maintain the integrity of the inaccessible areas. If the aging management program for the inaccessible areas is an evaluation of the acceptability of inaccessible areas based on conditions found in surrounding accessible areas, please provide information to show that conditions would exist in accessible areas that would l Indicate the presence of or result in degradation to such inaccessible areas. If different aging effects or aging management techniques are needed for the inaccessible areas, please provide a summary to address the following elements for the inaccessible areas:
, (1) Preventive actions that will mitigate or prevent aging degradation; (2) Parameters l Enclosure 2
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monitored or inspected relative to degradation of specific structure and component intended functions;. (3) Detection of aging effects before loss of structure and component 3 intended functions; (4) Monitoring, trending, inspection, testing frequency, and sample s're to ensure timely detection of aging effects and corrective actions; (5) Acceptance criteria to ensure structure and component intended functions; and (6) Operating l
experience that provides objective evidence to demonstrate that the effects of aging will l be adequately managed.
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REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS.1 & 2 PRIMARY CONTAINMENT HEATING AND VENTILATION SYSTEM
, INTEGRATED PLANT ASSESSMENT. SECTION 5.11B DOCKET NOS. 50 317 AND 50-318 l
Section 5.11B.1 - Scoolna
- 1. Section 5.118.1.2 of the LRA states that the portion of the Containment Air Recirculation and Cooling System within scope includes: cooling units, fans, and connecting ductwork up to and including the fusible dropout plates. Section 6.5.5," Containment Air Recirculation and Cooling System," of the Calvert Cliffs Nuclear Power Plant (CCNPP)
Updated Final Safety Analysis Report (UFSAR) states that each fan discharge duct is provided with a fusible link door that opens at an abnormally high containment ;
temperature such as would occur under a loss-of-coolant accident. While Section 6.5.6 i I
of the CCNPP UFSAR also states that the containment air cooler blowdown door fusible links are to be replaced every refueling outage to ensure that the links perform their ,
design function and as a result would not be subject to an aging management review, l clarify on what basis were the fusible links excluded from the scope of license renewal.
- 2. Section 6.5.6, " Containment Air Recirculation and Cooling System," of the UFSAR concludes that water-logging of the cooling units' coils is not a problem because the coil section drainage characteristics were validated by the manufacNrer's sizing and test program. For this conclusion to remain valid, the staff believes that to drain condensate )
would have to be an intended function of the system. If it is an intended function of the system, clarify whether the piping described in Section 6.5.4 of the UFSAR which transfers the condensate leaving the coils to the containment sump and ultimately to the waste processing system is within the scope of license renewal and subject to an aging management review? If not, justify why this function is excluded.
- 3. Clarify whether the instrument lines are included in the scope of license renewal.
10 CFR 54.21(a)(1)(i) excludes instrumentation from the scope of renewal, in part because the instruments are routinely subjected to surveillance testing. The sample linec to such instruments as pressure transmitters, pressure indicators, water level indicator, and containment atmosphere draw samples (like those described in Section 6.8 of the UFSAR, " Hydrogen Control Systems," are not always tested to the same extent as the associated instmments. If the instrument lines have been excluded from the scope of license renewal, provide the justification for that exclusion with consideration of the foregoing concem.
- 4. Section 6.8.2, " Electric Hydrogen Recombiner," of the CCNPP UFSAR states that the service life of the recombiners is 40 years. Describe how this component was addressed for license renewal.
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- 5. Section 5.118.1.3 of the LRA states that the hydrogen recombiner only functions actively. This appears to be inconsistent with Section 6.8.2.3 of the CCNPP UFSAR which states that the recombiner is a completely passive device. Because the recombiner housing acts as a passive holdup volume to allow the containment atmosphere to be heated to a temperature above 1150*F, please provide the basis for considering the hydrogen recombiner to only have active functions and therefore not subject to an aging management review.
Section 8.11B.2 - Aaing Manan?mant l 6. Are there any parts of the systems, structures, or components described in Section 5.5 i
that are inaccessible for inspection? If so, describe what aging management program will be relied upon to maintain the integrity of the inaccessible areas. If the aging management program for the inaccessible areas is an evaluation of the acceptability of inaccessible areas based on conditions found in surrounding accessible areas, please provide information to show that conditions would exist in accessible areas that would indicate the presence of or result in degradation to such inaccessible areas. If different aging effects or aging management techniques are needed for the inaccessible areas, please provide a summary to address the following elements for the inaccessible areas:
(1) Preventive actions that will mitigate or prevent aging degradation; (2) Parameters monitored or inspected relative to degradation of specific structure and component intended functions; (3) Detection of aging effects before loss of structure and component intended functions; (4) Monitoring, trending, inspection, testing frequency, and samole ,
size to ensure timely detection of aging effects and corrective actions; (5) Acceptance criteria to ensure structure and component intended functions; and (6) Operating experience that provides objective evidence to demonstrate that the effects of aging will be adequately managed.
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