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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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ftom n s IL lhs sm Italtirnore Gas and 1:Irctric Compmy Yurl'rt5ident Coin'11 CIWs Nucian l'us ucr I'lant Nw It or I no r n "'3" ("I" (I'N' I'"' 5 "'"5 Imin. Manland 20157 1 4 to $Wnw 1 tt 445$ la al 410 lrgo44$$ llultimore June 30,1994 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk SUllJECT: Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50 317 & 50 318 Final Response to Generic Letter 8913, "Senice Water System Problems AfRflip23afrudchted.listipment"ITAGps. M73978 anO173979)
ItEFEllENCES: See Attachment (2)
NRC Generic Letter (GL) 8913 outlined concerns regarding the safe operation and maintenance of open-cycle cooling water systms and identified several recommendations associated with ensuring proper heat transfer capability of their components. For Calvert Cliffs Units 1 and 2, the open-cycle, cooling water system in the scope of GL 89-13 is the Saltwater System.
Due to the large amount of correspondence describing our plans and actions to address the GL, the status of our actions may be unclear. Therefore, Attachment (1) to this letter provides the status of the five tasks outlined in the original response (Reference b). Attachment (1) supersedes all previous correspondence on GL 8913 and all commitments made to address GL 8913 issues.
Should you have any further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, s
[ ] ~
\
RED /JMOldlm Attachments: (1) Status of Actions for Generic Letter 8913 (2) Generic Letter 8913 Correspondence Chrenological List i
9407000176 940630 0 1 l PDR ADOCK 05000317 i l P POR i
. . . I
+
Document Control Desk June 30,1994 l' age 2 cc: D. A. Ilrune, Esquire J. E. Silberg. Esquire M. K. Iloyle, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R.1. McLean, DNR J. II. Walter, PSC t
. A1TACilSIENT (1)
STATUS OF ACTIONS FOR GENERIC LINTER 89-13 SERVICE WATER SYSTEh! PROllLEhlS AFFECTING SAFLTY RELATED EQUIPhlENT ,
5
- 1. TASK 1 - sal,TWATER IllOFOUI.ING PROGRAM e
The purpose of TASK 1 was to implement and maintain an or. going program of surveillance and control techniques to significantly reduce the incidence of flow blockage problems as a result of biofouling in open cycle systems. All activitics to address TASK I have been completed as described Lelow:
A. Repetitive maintenance tasks have been developed to ensure the intake Structure is cleaned and inspected on a pericdic basis.
- 11. Procedures are in place to ensure that infrequently-used, safety related Salts ter (SW) loops are flushed routinely. Flow through these loops is monitored monthly and afler debris-causing events II. TASK 2 - TEST PROGRAM FOR SAFETY-REl,ATED IIEAT EXCilANGERS The purpose of TASK 2 was to conduct a test program to verify the heat transfer capability of all safety-related heat exchangers (llXs) cooled by the SW, Service Water (SRW) and Component Cooling (CC) Systems (i.e., closed- and open-cycle systems).
A. Closed-sycle Initial Test Progam
- lhe goal of the closed-cycle test program was to determine if the quality of chemistry control programs has been sufficient to conclude that testing of closed cycle, safety-related ilXs under the scope of Generic Letter (GL) 8913 is not necessary. In the original response, we stated that closed-cycle systems would be removed from the scope of the GL 89-13 test program if none of them exhibited fouling caused by sys'em-wide corrosion.
%crefore, if no such fouling was identified in these systems, then the adequacy of chemistry control programs over the entire operating history of the plant was established.
The initial test activities included testing some IIXs and inspecting others. From the results of the initial test activities detailed in References (h) and (j), it was concluded there was no system-wide, corrosion-induced fouling in the closed-cycle systems, and confirmed that the closed-cycle llXs adequately transfer heat. They have been removed from the scope of our GL 8913 test program. The results arc shown below:
1
ATTACllMENT (1)
STATUS OF ACTIONS FOR GENER!C LI" ITER 89-13 SERVICE WATER SYSTEM PROllLEMS AFFECTING SAFETY-RELATED EQUIPMENT l
- 13. C]pigd-Cycle iigat.fiqban2C.[11C11.;md. InspsqtioMcsgJh Closed-Cycle IIcat Exchanger Test / Inspection Repits Containment Air Coolers Type Ill.B All coolers tested satisfactorily and all coolers were cleaned.
Spent Fuel Pool Cooling IlXs TvpcII.B All coolers tested satisfactorily.
Emergency Diesel Generator Type ll.A No.1I EDO Jacket Water and Air (EDG) Coolers Coolant ilX tested satisfactorily. All EDG coolers are inspected at 18-month intervals.
Shutdown Cooling IIXs Type ll.B /.11 coolers tested satisfactorily.
liigh Pressure Safety injection Type IV.13 (oolers for No.12 were flow-tested (IIPLI) Pump Seal and Bearing satisfactorily. Coolers for No. 21 were Coolers inspected.
C. Opsn-Cycig Initial Testhegana
%c goal of the open-cycle program was to determine the heat removal capability of systems that are cooled by Chesapeake Bay (i.e., raw) water. There are three groups of IlXs in open-cycle systems - SRW llXs, CC IIXs and Emergency Core Cooling System (ECCS) pump room air coolers. From the results of the initial test activities, it was concluded that the open-cycle llXs are designed and maintained such that their safety-related heat removal requirements are satisfied. Our conclusion is based on the results of completing the initial test activities as indicated below:
- 1. SRW IIcat Exci anggrj As described in Reference (h), difficulties were encountered with establishing sufficient heat load (i.e., appropriate plant conditions) to conduct valid tests of the Unit 1 SRW llXs during the 1992 refueling outage. A valid test has reasonable uncertainties in comparison to its acceptance criteria. As described in Reference (j), it was decided there was no benefit to performing initial tests or; the Unit 2 SRW !!Xs prior to comple ing significant modifications that would be installed during the spring 1993 r'.iueling outage. He modifications included replacing most concrete-lined nb witn mbber-lined pipe, modifying pipe runs and diameters where possible, and improving ixations for installing test equipment.
Additionally, similar to the Unit i SRW llXs, a valid test of the Unit 2 SRW IIXs requires suflicient heat load. For both of the Unit I and 2 SRW HXs, initial testing was performed afler they were cleaned by quarterly tube bulleting. The results of the tests were reviewed and determined to be valid. The HXs were able to remove the required amount of accident heat load for the highest recorded bay temperature (i.e.,85 F).
2
m ATTACIISIENT m STATUS OF ACTIONS FOR GENERIC LITTER 89-13 SERVICE WATER SYSTEM PROllLEMS AFFECTING SAFETY-RELATED EQUIPMENT in LER 50-317/93-007 (Reference 1), BGE reported that the results of thermal performance tests performed in fall 1993 indicated that the SRW llXs may not have been capable of meeting their intended safety function during the most limiting design basis requirement for bay temperature, (i c.,90*F). The original design calculation assumed minimum SRW flow was the limiting case. When maximum SRW design now rate to the CACs is assumed, heat is transferred from containment to the SRW System at a faster rate. This causes higher SRW temperatures than previously calculated, with the result being higher EDO temperatures. Since that report, it was concluded that the plant was safe in the past based on the following:
> the bay water temperature has never exceeded 85'F; and,
> the EDO vendor (Fairbanks Morse) reviewed the worst-case transient and concluded that EDG performance is not impacted.
To provide additional assurances of SRW llX heat removal capability for maximum expected bay temperatures, How control valves were installed for the CACs and SW pump differential pressure indication was improved (Reference m).
These modifications have been credited in re >idons to plant operating instructions.
- 2. CmnenLQlo igJilegt fischangey _
Due to an unscheduled shutdown just prior to the 1992 Unit I refueling outage, the Unit I CC IIXs could not be tested during the cooldown es scheduled.
Reference (h) describes difficulties associated with performing a valid test of the Unit 1 CC llXs due to insufficient heat loads. Specifically, the test was invalid because SW Dow had to be reduced to a level that maintained the CC water teniperature at 95'F so that the controlled bleed-off temperature for the Reactor Coolant Pump Seals did not fall below 110 F. If the Unit I test could have been performed during the plant cooldown, we expect that we could have met these requirements and also had sufficient SW Cow to perform a valid test.1-lowever, since the EPRI guidelines for IIX testing (Reference k) are based on steady-state cenditions, we had an additional concern that we would have difficulties achievir.g the required steady-state criteria during a plant cooldown. Therefore, in Reference (h), we stated that we would develop and validate a method to account for transient ilX conditions that exist during a plant cooldown (i.e., transient test).
During the cooldown for the 1993 Unit 2 refueling outage, both a standard and a transient type of test were performed on the Unit 2 CC llXs. When the data was analyzed, it was concluded that both tests had met the criteria of the EPRI guidelines. The results of the transient test were essentially identical to those of the standard test. Ilowever, since the cost of pe hrming the transient test was significantly higher than the standard test, BGE ducs not plan to perform it in the 3
. A1TACllMENT (1)
STATUS OF ACTIONS FOR GENERIC Li~lTER 89-13 l SERVICE WATER SYSTEM PROllLEMS AFFECTING SAFL'IT-RELATED EQUIPMENT future, in Reference 0), when we reported that the Unit 2 CC llXs had been tested to conclude that they have adequate heat transfer capability, we did not srecifically state which type of test was used.
1 During the cooldown for the 1994 Unit I refueling outage, initial testing was l performed again on the Unit 1 CC IIXs. These tests did not meet the EPRI l guidelines even though test instrument locations were optimized for the existing system configuration. During the outage, thermal wells were installed. They should improve the ability to perform valid thermal performance tests in the i future.
For the following reasons, we have concluded that the Unit 2 CC llX test results are applicable to the Unit I CC liXs, and that the initial test program for the CC llXs is complete:
> their design and construction are identical; t
> the raw water in their open-cycle sides is identical;
> the chemistry control program for the water in their closed-cycle sides is identical;
> based on other plant activitics, there is no evidence of fouling in closed-cycle systems, i
> their maintenance and testing programs are identical; and,
> they are operated identically.
- 3. ErnergnqnCortCoglintSystemBminRoom Air Cal _ers In References (h) and G), we reported that the initial testing for the Unit I and 2 air coolers had been performed satisfactorily.
D. Continuina Test Prograrn <
Based on the results of our Open and CloscGCycle initial Test Programs, our GL 8913 Continuing Test Program only includes the SRW, CC and ECCS IlXs. We have established a continuing test program to verify the thermal performance of these llXs.
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A1TACllMENT (1) 4 STATUS OF ACTIONS FOR GENERIC LETTER 89-13 SERVICE WATER SYSTEM PROllLEMS AFFECTING SAFETY RELATED EQUIPMENT t
111. TASK 3 - INSPECTION AND MAINTENANCE PROGRAM The purpose of TASK 3 was to establish a routine inspection and maintenance program for the SW piping and components to ensure that corrosion, crosion, protective coating failure, silting and biofouling cannot degrade system performance. All planned actions to address TASK 3 have been completed as described below:
A. Differemial pressure across the SRW llX is momtored twice per shift The SRW llXs and the CC llXs are bulleted quarterly, f it The program for cleaning and inspecting SRW, CC and ECCS IlXs is established. It will be revised as necessary based on the results of plant maintenance and testing activities.
Recommendations from System Engineering, based on their monitoring activitics, arc also r used to establish appropriate cleaning and inspection frequencies. New technologies will be incorporated as necessary.
C. The piping ultrasonic thickness inspection program has been reviewed and revised.
D. An underground piping inspection program has been established.
I V. TASK 4 - 1,1 CENSING llASIS REVIEW i
' Die purpose of TASK 4 was to confirm that the SW, SRW and CC Systems will perform their intended function in accordance with the liccnsing basis for the plant. All planned actions to address TASK 4 have been completed as described below:
A. Sys'em hydraulic and ilX models have been developed. The software was validated by duplicating a number of plant specific hydraulic calculations and comparing the results to the original calculations. System models were validated by comparison to actual plant data. The models have been used to evaluate a variety of flow cases, corresponding to
- system responses to various demands, including associated single failures. - Design basis ,
hydraulic and heat transfer calculations have been validated.
II. System drawings were reviewed and walkdowns were performed to ensure that the syste.ns -
were not vulnerable to single active failures.
V. 'I n * - SERVICE WATER SYSTEMS PROGRAMS REVIEWS The purposes of TASK 5 were to confinn that: 1) maintenance practices, operating and emergency j procedures, and training associated with the SW, SRW and CC Systems are adequate to ensure that safety-related systems will function as intended; and, 2) operators of this equipment will perform efTectively. All planned actions to address TASK 5 have been completed as described below:
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NIT 4C1131f.NT m STATUS OF ACTIONS FOlt GENEltlC LE'ITElt 89-13 SEltYlCE WATEll SYSTEM l'ItOllLEMS AFFECTING SAFETY-ItELATED EQUll' MENT A. Under the Prcwedure Upgrade Program, numerous technical procedures associated with operating, testing and maintaining SW, SRW and CC Systems have been revised to enhance human factors and technical accuracy. These include Abnormal Operating Procedures, Operating instructions, Surveillance Test Procedures and Chemistry Procedures. Ruisd Wintenance Procedures inchide procedures associated tutn ricaning IlXs, overhauling pt.:r,rs, pipe repair, vahr repair, component cleaning and component inspection.
II. Site administrathe piocedures require that all plant modifications and changes to both administrative and technical procedures must be evaluated to dete mine if training must bc __
conducted prior to their implementation a,
P 6
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ATTACllMENT 4)
GENERIC LETTER 89-13 CORRESPONDENCE CI'RONOLOGICAL LibT
REFERENCES:
(a) Senice Water System Problems Affecting Safety-Related Equipment (Generic Letter 8913), dated July 18,1989 (b) Letter from Mr. G. C. Creel (BGE) to NRC Document Control Desk, dated January 29, 1990, Response to Generic Letter 8913, "Senice Water System Problems Affecting Safety Related Equipment" (c) Senice Water System Problems AfTecting Safety-Related Equipment ;
(Generic letter 89-13, Supplement 1), dated April 4,1990 (d) Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. G. C Creel (BGF), !
dated April 27,1990, NRC Generic Letter 89-13, "Senice Water System l Problems Affecting Safety-Related Equipment," Calvert Cliffs Nuclear !
Power Plant - Unit 1 & 2 (c) Letter frorn Mr. G. C. Creel (BGE) to NRC Document Control Desk, dated January 6,1992, Revised Response to NRC Generic Letter 89-13 "Semice Water System Problems Affecting Safety Related Equipment" (TAC Nos. M73978 and M73979) _!
l (f) Letter from Mr. D. G. Mcdonald (NRC) to Mr. G. C. Creel (BGE), dated February 6,1992, Updated Res9anse to NRC Generic Letter (GL) 89-13, j "Senice Water System Problems Affecting Safety-Related Equipment,"
Calvert Cliffs Nuclear Power Plant - Unit I & 2 (g) 1xtter from Mr. G. C, Creel (BGE) to_ NRC Document Control Desk, dated August 4, 1992, Revised Testing Schedule; NRC Gener;c Letter 89-13, " Service Water System Problems Affecting Safety-Related ,
Equipment"(TAC Nos M73978)
(h) Letter from Mr. G. C. Creel (BGE) to NRC Document Control Desk, dated September 16, 1992, Summary of Completed Actions; NRC Generic Letter 89-13, "Senice Water System Problems Afreeting Safety- .
Related Equipment"(TAC Nos. M73978 and M73979) 4 (i) Letter from Mr. D. G, Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE),
dated December 9,1992, Generic Letter (GL) 89-13. "Senice Water System Problems AtTecting Safety-Related Equipment," - Calvert Clifts
+
Nuclear Power Plant - Unit I & 2 (TAC Nos. M73978 and M73979) l j (j) ' Letter from Mr. R.' E. Denton (BGE) to NRC Document Control Desk, dated July 12, 1993, Summary of Completed Actions; NRC Generic Letter 8913 "Scnice Water System Problems Affecting Safety-Reitted - .
Equipment"(TAC Nos. M73978 and M73979) l 1
. NITACll%1ENT (2)
GENERIC 1IIITER 89-13 CORRESPONDENCE CilRONOLOGICAL LIST llEIT.RENCES: (k) IIcat Exchanger Performance hionitoring Guidelines (EPGI NP-7552) (
(1) Letter from hir. C.11. Cruse (BGE) to NRC Document Control Desk, dated December 29,1993, Licensee Event Report 93-007, " Performance Tests Indicate Possibility of SRW llcat Exchanger Inoperability" (m) Letter from hir. C.11. Cruse (BGE) to NRC Document Control Desk, dated June 17, 1994, Reply to Request for Additional Information -
Service Water System Operational Performance Inspection f
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