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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
[Table view] |
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BALTIMORE ,
GAS AND l ELECTRIC l
%, l 1650 CALVERT CUFFS PARKWAY LUSBY, MARYLAND 20657-4702 ROBERT E. DENTON VICE PRESIDENT j l
NUCLEAR ENERGY
, ( io) reo-4.ss I
. August 17,1993 U. S. Nuclear Regulatory Commission Washington,DC 20555 ,
I ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Emercency Diesel Generator Uncrade Proicct
REFERENCE:
(a) Letter from H. Silver (NRC) to W.3. Wilgus (FPC), dated .
September 25,1989, C ystal River Unit 3 - Pre-Operational Testing l of the Upgraded Emergency Diesel Generator We are proposing to modify our existing Emergency Diesel Generators (EDGs) to improve their electrical capacity. This modification will provide additional margin for the electricalloading of the 4.16 kv safety related busses. In turn, this gives the operators flexibility in the addition of discretionary loads post-accident. The capacity upgrade is described in the Attachment. The upgrade is the same type as the one performed at Crystal River in 1990. At that time, the NRC Staff proposed a testing program to re-qualify the load capacity and reliability of the EDGs (Reference a).
We have reviewed that testing program and established a testing program almost identical to it. Our testing program is described in the Attachment.
We request that you review our testing program and concur that it will provide reasonable assurance c,f the load capacity and reliability of the upgraded EDGs. We intend to upgrade EDG No.11 during the spring 1994 refueling outage with the other two EDGs upgraded during subsequent outages.
Therefore, we request concurrence with our testing program by January 15,1994 to support the outage schedule.
Should you have any questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, 5
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i RED / PSF / psf / dim Attachment '" Jfjg n 9308230204 930817 0~
PDR ADOCK 05000317 '
PDR a i P
M pas 9e nr 4
. Document Control Desk August 17,1993 Page 2 cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNR J. H. Walter, PSC i
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'. ATTACIIMENT (1) i EMERGENCY DIESEL GENERATOR UPGRADE
]
DESCRIPTION ,
l We are planning to modify our existing Fairbanks-Morse diesel generators to improve their electrical capacity. The diesel engines provided to Calvert Cliffs were shipped in 1970 with a 300 HP/ cylinder i design. An engine conversion is now available which will improve the design of the engine to i 350 HP/ cylinder. The modifications to the diesel generator will involve: the pistons, cylinder liners, j air inlet check valves, turbochargers, blowers, injection nozzles, combustion air piping, and support systems. As a result of these modifications the following ratings will be achieved:
Ratine (existine) Ratine (Upgraded) Time Limit 0 -2500 kw 0 - 3000 kw Continuous 2501 -2700 kw 3001 -3300 kw 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> 2701 - 3000 kw 3301 -3500 kw 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> 3501 - 3600 kw 30 minutes The capacity upgrade is being pursued to gain additional margin between the accident loads and the capacities of the machines. The emergency diesel generator upgrade consists of two distinct parts:
capacity upgrades and qualification testing. The capacity upgrade consists of the following: ,
- Upgraded design cylinderliners
> Upgraded design blowers
> Upgraded design pistons
> Larger turbochargers
> Upgraded design combustion air piping Included in the upgrade is an evaluation of the support systems for the diesel generators. The following systems will be evaluated to determine if modifications are required: Service Water System, Electrical Distribution System, Starting Air System, Fuel Oil System and the Ventilation System.
Based on preliminary engineering, it appears that none of these systems will require modification.
However, additional modifications to the diesel generator will include: a new lube oil heat exchanger tube bundle, a new air cooler heat exchanger tube bundle, a new intercooler heat exchanger, and newintercooler pipmg.
The second part of the upgrade will consist of the qualification testing program described below.
OUALIFICATION TESTING PROGRAM We intend to perform a preoperational testing program which meets the intent of Regulatory i Guide 1.9, Resision 3 (draft, April 1992) and IEEE 387 (1984). These guidance documents are not part of our licensing basis for the Fairbanks-Morse diesels and performance of this testing program does not commit us to any other portion of these documents. Because we intend to perform these tests on diesel generators which are already installed at Calvert Cliffs, and we are not modifying other parts of our onsite emergency power system, we will not be able to perform the tests exactly as the standard requires. Our testing program is described below and is almost identical to that proposed by the NRC Staff for Crystal River (Reference a) with the only exception being the 30 start and load tests. As described below (item 8), we will be performing 25 start snd load tests in accordance with Regulatory Guide 1.9, Revision 3 (draft, April 1992).
I
_ _ ._ ,. , _. __ __ ..,.._..a..,__.2,.. .- _._. - ~ _ ~ ,
. A*ITACIIMENT (1)
EMERGENCY DIESEL GENERATOR UPGRADE Factory Testine As described in IEEE-387, initial design qualification is accomplished by the performance of type tests, or analysis, or a combination of both. The proposed testing would utilize a modified diesel engine identical to the installed engines at Calvert Cliffs. We provided Fairbanks-Morse with our spare engine and they are performing the upgrade on that engine. Fairbanks-Morse has proposed a testing program similar to that performed on Crystal River's diesel generator. They propose running the engine at 3300 kW for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, 3500 kW for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> and then perform an engine inspection. The engineering report produced from this testing would qualify the engine ratings given above. We consider the testing program recommended by the manufacturer to be adequate to meet the IEEE requirement. This is contingent upon the successful completion of the pre-operational testing described below.
Site Testine Regulatory Guide 1.9, Revision 3 (draft, April 1992) provides guidance for supplementing the requirements given in Section 7 of IEEE-387. Based on this Regulatog Guide and the IEEE Standard, we propose the following test program. 'Ihese tests will be conducted in-situ on each upgraded diesel generator. These tests will be performed in conjunction with the Baltimore Gas and Electric Company (BG&E) required post modification acceptance testing. Credit will be taken for any BG&E acceptance test that is essentially identical to a test in the pre-operational test program.
- 1. Start and Imad-Run Test
- a. Start Test: We will demonstrate proper startup from ambient conditions and verify that the required design voltage and frequency is attained. For these tests, the diesel generator will be pre-lubricated, have pre-warmed oil and water circulating and will reach rated speed on a pre-specified schedule that is selected to minimize stress and wear.
- b. Imad-Run Test: We will demonstrate the emergency load carrying capability of 90-1009c of its continuous rating (2700 to 3000 kW) for one hour. The loading and unloading of the diesel generator during this test will be gradual and based on a prescribed schedule that is selected to minimize stress and wear on the diesel generator.
- 2. Fast Start Test We will demonstrate that each diesel generator starts from ambient (pre-lubricated) conditions and reaches stable rated voltage and frequency within the limits and time defined in Technical Specification 4.8.1.1.2.a.4 and 4.8.1.1.2.c.
- 3. Combined Safety Iniection Actuation Sicnal and less-of-Offsite Power Test We will demonstrate that: (1) the emergency busses are de-energized and loads are shed from the emergency busses, (2) the diesel generator starts from its ambient (may be pre-lubricated) condition and attains the required rated voltage and frequency within the limits and time required by the plant Technical Specifications, (3) energizes the auto-connected loads through the load sequencer and, (4) operaies at least five minutes loaded with the auto connected loads.
2
l A*ITACilMENT m EMERGENCY DIESEL GENERATOR UPGRADE
- 4. Sincle Load Rejection Test We will demonstrate the diesel generators capability to reject its largest single load (500 hp) and verify the voltage and frequency requirements are met.
- 5. Fullload Reiection Test We will demonstrate the capability of the diesel generator to reject a load equal to 90-100%
ofits continuous rating (approximately 2700-3000 kW). During this test we will verify that voltage requirements are met and that the diesel generator does not trip on overspeed.
- 6. Endurance and Marcin Test We will demonstrate the full-load carrying capability for an interval of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of which 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will be at 3150 to 3300 kW (105-110% of the continuous rating) and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at a load of 2700-3000 kW (90-100% of the continuous rating). We will verify that voltage and frequency are maintained.
- 7. Hot Restart Test The hot restart functional capability at full load temperatures will be verified by starting the diesel generator, attaining the required vohage and frequency within the limits and time provided in the Technical Specifications, and operating loaded to 2700 - 3000 kW (90-100%
continuous rating) for at least an hour.
- 8. ReliabilityTests We will demonstrate that an acceptable level of reliability has been achieved on each diesel generator by performing 25 start and load tests as described in item 1 above without a failure.
Start and load failures are defimed by Regulatory Guide 1.108 and are in accordance with our existing reliability program. The number of tests was selected in accordance with Regulatory Guide 1.9, Resision 3 (draft, April 1992), Position 2.3.1. This position requires, "a minimum of 25 valid start and load demands in accordance with Regulatory Positions 2.2.2 and 2.2.3. . . ." Those regulatory positions require that a load-run test be performed and that we perform fast starts from standby conditions. We will perform the suggested 25 starts, however, to the extent possible they will be slow starts (in accordance with the manufacturers recommendations) from either hot or ambient conditions. This reduces the wear on the diesel generators caused by fast starts (Generic Letter 84-15) and tests the slow start circuitry. Slow starts will comprise the majority of our Technical Specification surveillance testF.
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3 ATTACIIMENT (1)
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. EMERGENCY DIESEL GENERATOR UPGRADE )
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1 To the extent that they apply, the starting and loading performed as part of the manufacturer ,
i recommended testing or surveillance testing will be counted toward the 25 start tests. Baltimore Gas 1 and Electric Company considers the testing program outlined in items 1, 2, 4, 5, 6, and 7 to l adequately demonstrate Operability of the diesel generator for Modes 4,5, and 6. Following these ,
tests, the diesel will be considered Operable for these Modes. While reliability testing is being l performed, the diesel generator may be under manual control and may not start immediately !
i following a loss-of-offsite power. However, in Modes 4,5, and 6, time is available following a loss-of-
- offsite power to manually start a diesel generator and restore power to the decay heat removal
- systems. Prior to being considered Operable for Modes 1,2, and 3, the diesel generator will have ,
i successfully completed items 3 and 8. j
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CONCLUSION i
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We believe that the test program outlined above will demonstrate the capability and reliability of the l upgraded diesel generators. The test program was developed by balancing the NRC's guidance with j the merits of performing such an extensive test program. Additionally, with regard to test 8, an attempt has been made to satisfy the Regulatory Guide 1.9 guidance on the performance of 25 starts per machine without having a significant impact on the length of the refueling outage.
I At the completion of this. upgrade program, we will have diesel generators with more available margin than currently exists. Tnis will provide the operators with more flexibility during conditions
- where the diesel generators are providing onsite power.
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