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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: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 ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl 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 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 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) ML20195B3751999-05-25025 May 1999 Forwards ECCS Codes & Methods Rept, as Required by 10CFR50.46(a)(3)(ii) ML20195B2521999-05-25025 May 1999 Submits Response to RAI Re LAR for Tube Repair Using Leak Limiting Alloy 800 Sleeves for Ccnpp,Units 1 & 2.Test Repts Encl ML20195B2271999-05-24024 May 1999 Forwards Certified Copy of Nuclear Liability Policy NF-216, Endorsement 128 ML20206U3051999-05-19019 May 1999 Submits Written Rept as Required follow-up to Verbal Rept Given to NRC Regional Administrator on 990419 of SG Tube Insps Conducted,Cause of Tube Degradation & Corrective Measures Taken as Result of Insp Findings ML20206U8281999-05-18018 May 1999 Forwards Missing Pages C-30,C-31,C-114 & C-115 from 990319 Response to NRC RAI, Wind Tunnel Modeling of Calvert Cliffs NPP Cpp Project 94-1040. Complete Copy of 1985 Rept, Wind Flows & Dispersion Conditions of Calvert Cliffs, Encl ML20212G9751999-05-12012 May 1999 Forwards Draft write-up Re OI 16 for F Grubelich to Consider ML20206K6921999-05-10010 May 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsements,In Compliance with 10CFR140.15(e).Without Encl ML20206K1711999-05-0707 May 1999 Informs That on 990430 Util Filed Encl Articles of Share Exchange with Maryland Dept of Assessments & Taxation to Form Holding Company,Constellation Energy Group,Inc (Ceg). CEG Is Parent Company of Bg&E ML20206C7521999-04-29029 April 1999 Provides Rept of Number of Tubes Plugged in Calvert Cliffs Unit 2 SGs During Recently Completed Isi,As Required by Calvert Cliffs Unit 1,TS 5.6.9.a ML20212G9891999-04-28028 April 1999 Forwards Current Draft Response to Ci 3.3.2.2-1 to Be Used as Example for OI Vs License Condition Vs Commitment Situation ML20206C7271999-04-28028 April 1999 Forwards Occupational Radiation Exposure Repts for 1998, as Required by Units 1 & 2 Tech Specs 5.6.1 & 6.1 of Isfsi. Repts Contain Tabulation of Number of Station,Util & Other Personnel Receiving Exposures Greater than 100 Mrem ML20206C7211999-04-27027 April 1999 Forwards Addl Info Which Is Being Made Available in Encl Licensed Operators Fitness for Duty Questionnaire.Encl Specifics of Personal Info Are Withheld,Per 10CFR2.790 ML20212G9851999-04-26026 April 1999 Provides Proposed Response to OI 4.1.3-1 for B Elliott to Consider ML20206U6691999-04-26026 April 1999 Advises That Documents Re Operation of Calvert Cliffs Nuclear Power Plant Should Be Addressed to Listed Natl Marine Fisheries Svc Office ML20205F8851999-04-0202 April 1999 Provides First Annual Amend to Bg&E License Renewal Application for Ccnpp,Units 1 & 2,as Required by 10CFR54 ML20205J0691999-04-0202 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20205G2971999-04-0101 April 1999 Requests That NRC Complete Review of Rev 0 to CENPD-396-P, Common Qualified Platform TR & Rev 0 to CE-CES-195-P, Software Program Manual for 'Common Q' Sys, by 990930 ML20205D7471999-03-30030 March 1999 Forwards Biennial Rept on Status of Decommissioning Funding, IAW 10CFR50.75(f)(1) ML20207G4391999-03-30030 March 1999 Responds to from Cl Miller,Requesting Assistance of FEMA in Addressing Concerns Received by NRC Involving Offsite Emergency Preparedness at Plant NPP ML20205C4091999-03-26026 March 1999 Submits Info Related to Scope,Risk Mgt & Summary of Risk for Performing Preventive Maintenance on P-13000-2 Unit Transformer Re License Amend 205 1999-09-28
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BALTIMORE GAS AND ELECTRI CHARLES CENTER.
- BALTIMORE, MARYLAND 21203 1475 GEORGE C CnEEL vect Pwsotwf NUCLEAR int RGY (301) 260-4455 November 8,1991 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATI'ENTlON: Document Control Desk SUlHECT: Calver? Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Ncs. 50-317 & 50-318 Response to Generie Letter 91-06, Resolution of Generic issue A-30,
" Adequacy of Safety-Related DC Power 'lupplies " Pursuant to 10 CFR 50.54(h
REFERENCE:
(a) Letter from Mr. J. G. Partlow (NRC) to all lloiders of Operating Licenses, dated April 29,1991, same subject Gentlemen:
Generic Letter 91-06, Reference (a), addresses the resolution of Generic Issue A-30," Adequacy of Safety-Related DC Power Supplies" The specific area of concern in GI A-30 is the adequaev of safety-related DC power in operating the nuclear pow:r plant with regard to multiple and comrunn cause failures. Failure of the minimum DC power system could represent a significant contribution to the unreliability of shutdown cooling.
Reference (a) requests information pursuant to 10 CFR 50.54 (f) regarding the implementation of plant specific maintenance, surveillance, and monitoring provisions related to safety-related DC systems. Our written responses to the questions in Enclosure 1 of Generic Letter 9106 are provided in Attachment (1) to this letter. Attachment (2)is a single line diagram of the 125V DC system.
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n.o 9111180123 9tilOS - 'l PDR- ADOCK G3000317 POR
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l ' Document Control Desk Novemner 8,1991 Page 2 l
Should you have any further questions regarding this matter, we will be pleased to di.; cuss them with you.
Very truly yours, ,
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)( -l ) k 4%i foi e G. C. Cree:
Vice President - Nuclear Energy STATE OF MARYLAND :
- TO WIT :
CITY OF BALTIMORE :
. I hereby certify that on the 7 day of "///7&m /2ro 19_94 before me, the subscriber,
-a' Notary Public of the. State of h1aryland in and for /bn n < d a<,- /z/ (cwM, personally appeared G. Dowell Schwartz, Jr., being duly sworn, and states that he is Vice President.jf the Baltimore Gas and Electric Company, a corporation of the State of hiaryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge. information, and belief; and that he was authorized to provide the response on' behalf of said Corporation.
^
WITNESS my lland and Notarial Scal: I'/(72u'IcrEA 'b< cdC .-
p / Ndtary Public hly Commission E' - ires: /C '//9V /bWr:/rt 7 , / 9 f/
Date' GCC/Lh1D/Imd/ dim Attachment cc: D. A~ Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. hicDonald, Jr., NRC T.T htartin, NRC L E. Nicholson, NRC R. I. hicLean, DNR J. H. Walter, PSC
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1 4
A'ITACilMENT 1 IIAll!'IMORE t;AS & ELECTRIC COMPANY'S RESPONSES TO GENERIC 1.E'ITElt 9106 OUESTIONS SYSTEM DESCRIPTION The 125V DC power supply system at Calvert Cliffs is common to Units 1 and 2. As described in the Updated Final Safety Analysis Report (UFSAR), the DC power supply system is designed to provide
- uninterruptible power to the plant vital instrumentation and control systems. The system is designed in accordance with "IEEE Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations," IEEE No. 308-1974.
The DC power supply system is comprised of four independent and redundant isolated channels, and a reserve 125V DC system. Each of the four channels consists of one battery, two battery chargers, a battery monitor, one DC bus, multiple DC unit control panels, and two inverters.
The reserve 125V DC system for the plant is completely independent and inlateo .;om the four separation groups, yet is capable of replacing any one of the 125V DC batteries. This system consists of one battery, one battery charger, one battery monitor, and the assoc.ated DC switching equipment.
There is one battery chara,er fed from Uni 1 and another battery charger fed from Unit 2 connected to each 125V DC bus. The reserve battery is connected to its own charger when it is not connected to a safety-related 125V DC bus.
Each of the four 125V DC power sources is equipped with the following instrumentation in the control room to enable continual c erator assessment of system status:
- a. DC bus undervoltage alarm
- b. Battery current indication
- c. Charger current indication G. Charger malfunction alarm (includes input AC undervoltage, output DC undervohage, and output DC overvoltage)
- e. DC bus voltage indication
- f. DC ground indication In addition to the above instrumentation, continuous monitoring of the battery's connection to the
~ bus and of battery circuit continuity is provided.
REOUESTED ACTION Provide written responses to the questions in Enclosure 1 of the generic letter.
' OUI'STIONS AND llG&E RESPONSES
- 1. The plant name is Calvert Cliffs Nuclear Power Plant Units 1 aad 2 1
NITACIIMENT I IIAlli'IMOltE GAS & El.ECTitlC COMPANY'S HESPONSES TO GENEltlC 1,lslTEll 91-06 OUESTIONS
- 2. 'a. The number of independent redundant divisions of Class IE or safety-related DC power for this plant is fots (Include any separate Class 11: or safety-related DC, such as any DC dedicated to the diesel generators.)
- b. The number of functional safety-related divisions of DC power necessary to attain safe shutdown for this unit is ihree. This assumes a single failure of any one division.
- 3. Does the control room at this unit have the following separate, independently annunciated '
alarms and indications for each division of DC power?
- a. Alarms
- 1. Battery disconnect or circuit breaker apen? No. There are no separate alarms for each bus to indicate the battery disconnect is onen. Ilowever, there are separate battery monitors which provide a common open disconnect or circuit breaker alarm for batteries 11 and 12. There is a common battery monitor alarm for batteries 21. 22 and reserve batterv 01 also.
- 2. Battery charger disconnect or circuit breaker open (both input AC and output DC)? No. Thne are no separate alarms for each battery charcer disconnect or circuit breaker, llowever. a batterv charcer alarm will indicate an open input AC circuit breaker An alarm would be an indication for an open DC output only if one of the two chargers were aliened to the bus.
There is a common charger alann for charcers 11.12. 23 and 24. and one for charcers 01,13.14. 21 and 22,
- 3. DC system ground? No. There is only one continuous alarm for the DC cround system. This alarm is for DC buses 11 and 21 oniv. Additionally. all
-four buses have a manually operated cround detection s3 tem which is checked once ner shift by niant operators.
- 4. DC bus undervoltage? No. Ilowever, buses 11 and 12 have a common undervoltace alarm. There is also a common undervoltage alarm for buses 21,22 and reserve battery bus 01.
- 5. DC bus overvoltage? No. There are no separate alarms dedicated strictiv for pC bus overvoltacc. A DC but overvohace would cause the battery charcer to trip resultine in a battery charcer alarm. There is one battery charcer alarm for chargers 01.13.14. 21 and 22. and one battery charter alarm for chat eers 11.12,23 and 24.
- 6. Battery charger failure? No. There are two alarms: one for charcers 01,13.
- 14. 21 and 22. and one alarm for charcers 11.12. 23 and 24. This alatni would annunciate if the charcers have an undervollace on the input / output or an overvoltage on the output of the charter.
- 7. Battery discharge? No. There are no alarms for battery discharce. Battery monitor will alarm with DC bus undervoltacc.
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T 4 A'ITACilMENT I IIAlli'IMORE GAS & ELECTRIC COMPANY'S RESPONSES TO GENEltlC 1 FTTER 9106 OUESTIONS y
- b. - Indications:
- 1. Battery float charge current? No. There is a current meter on the outnut of the battery which could be used for indication of float charge current.
1-lowever, the meter accuracy readine range is not small enouch to be able to read the float charce current value.
- 2. Battery circuit output current? Yes
- 3. Battery discharge? Yes
- 4. Bus voltage? Yes
- c. Does the unit have written procedures for response to the above alarms' and indications? Yes
- 4. Does this unit have indication of bypassed and inoperable status of circuit breakers or other devices that can be used to disconnect the battery and battery charger from its DC bus and the battery charger from its AC power source during maintenance or testing? No. There is no direct indication of bypassed circuit breakers or disconnect switches. However, an open circuit will be indicated by the battery monitor alarm (described in 3.a.Q
- 5. If the answer to any part of Questions 3 or 4 is no, then provide information justifying the existing design features of the facility's safety-related DC system.
The existine design features of the safetv-related DC system are consisient with the oricinal design requirements to which this system was built. The NRC has reviewed and approved this design as part of the licensine basis and modification 1have been implemented under the authority cranted by 10 CFR 50.59. The answers to Questions 3 and 4. with the exception of the overvoltace alarm m would all be ves if it were not for the stipulation of channel independence. The Calvert Cliffs control room alarms conform to IFEE-308-1974. as reviewed and annroved by NRC. IEEE-308-1974 does not require channelindependence for alarms. With the common alarm system installed at Calvert Cliffs, control room operators are promptiv alerted to faulted conditions. The operators can auickly diacnose the problem and
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Identify the affected channel by consultine tiie alarm manual and other indications in the control room, as descril,ed in Questions 3 and 4. above,
- 6. (1) Iw e jou conducted a review of maintenance and testi ; activities to minimize the potentitj .or human error causing more than one DC division to be unavailable? Yes and
-(2) do plant procedures prohibit maintenance or testing on redundant DC divisions at the same time? ' Yes. This is controlled by the limitine conditions for operation in the plant technical specifications. In fact Plant Operations does not allow even a r.:ncle division to be removed from service for testine or maintenance without substituting the reserve battery for ita 3
NITACllMENT I IIA!!!'IMOltE GAS & ELECTitlC COMPANYS RESPONSES TO GENEltlC LF'ITElt 9106 OUESTIONS If the facility Technical Specifications have provisions equivalent to those found in the Westinghouse and Combustion Engineering Standard Technical Specifications for maintenance and surveillance, then Question 7 may be skipped and a statement to that effect may be inserted here.
- 7. Are maintenance, surveillance and test procedures regarding station batteries conducted routinely at this plant? Specifically:
- a. At least once per 7 days are the following verified to be within acceptable limits:
- 1. Pilot cell c!cctrolyte level? h
- 2. Specific gravity or charging current? h
- 3. Float voltage? h
- 4. Total bus voltage on float charge? Yes
- 5. Physicalcondition of allcells? Yes
- b. At least once per 92 days, or within 7 days after a battery discharge, overcharge, or if the pilot cell readings are outside the 7-day surveillance requirements are the following verified to be within acceptable limits:
- 1. Electrolyte level of each cell? Yes
- 2. The average specific gravity of all cells? h
- 3. The specific gravity of each cell? Yes
- 4. The average electrolyte temperature of a representative number of cells?
Yes
- 5. The float vohage of each cell? Yes
- 6. Visually inspect or measure resistance of ternunals and connectors (including the connectors at the DC bus)? h
- c. At least every 18 months are the following verified:
- 1. Low resistance of each connection (by test)? Yes
- 2. Physicalcondition of the battery? Yes
- 3. 13attery charger capability to deliver rated ampere output to the DC bus? h
- 4. The capability of the battery to deliver its design duty cycle to the DC bus?
Yes
- 5. Each individual cell voltage is within acceptable limits during the service test?
Yes -
4
+
NITACllMENT 1 IIAlli'IMOltE GAS & ELELTIllC d -MPANY'S ItESI'ONSES TO GENEltlC LE'ITElt 9. 36 OUESTIONS
- d. At least every 60 months, is capacity of each battery verified by performance of a discharge test? Xes
- c. At least annually,is the battery capacity verified by performance discharge test,if the battery shows signs of degradation or has reached 85% of the expectea senice life?
g Yes 8.- Does this plant have operational icatures such that following loss of one safety-related DC power supply or bus:
- a. Capability is maintained for ensuring continued and adequate reactor cooling? Yes
- b. Reactor coolant system integrity and isolation c.;pability are maintained? Yes
- c. Operating procedures, instrumentation (including indicators and annunciators), and control functions are adequate to initiate systems as required to maintain adequate core cooling? Yes
- 9. If the answer to any part of Questions 6, 7 or 8 is no, then provide your basis for not performing the maintenance, survei!!ance and test procedures described and/or the bases for not including the operational features cited. N/A l-5
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