Letter Sequence Other |
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MONTHYEARML20087C6921992-01-0606 January 1992 Informs of Changes Made to Programs Re Revised Response to NRC Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety Related Equipment Project stage: Other ML20141M3771992-08-0404 August 1992 Submits Revised Testing Schedule in Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Hx of at Least One Train of Each Safety Sys Tested Project stage: Other ML20118A6711992-09-16016 September 1992 Summarizes Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety Related Equipment, Activities Completed for Unit 1,per Util Project stage: Other ML20125D5131992-12-0909 December 1992 Discusses Util Providing Summary of Actions Completed for Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment Project stage: Other ML20070D5391994-06-30030 June 1994 Provides Final Response to GL 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment Project stage: Other ML20141F9181997-05-16016 May 1997 Application for Amend to License DPR-53,implementing Mod Involves Replacing Service Water Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability Project stage: Request 1992-08-04
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20211J1611999-08-17017 August 1999 Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements 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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i BALTIMOr E GAS AMJ E L E' ,T R I C 1650 CALVERT CLIFFS PARKWAY . LUSBY, MARYLAND 20657 4702 GEoPot C CREEL vice PatsiotNT Nvckt an ENTnoy (480) 860-e456 January 6,1992 U. $. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Phnt Unit Nos.1 & 2; Docket Nos. $#317 & 50-318 Revised Response to NRC Generic Letter 89-13,
" Service Water 7 stem Problems Affecting Salety Related Equipment"(TAC Nos, h173978 and h173979)
REFERENCES:
(a) NRC Generic Letter 8913, "Senice Water System Problems Affecting Safety Related Equipment," dated July 18,1989 (b) Letter from hir. G. C, Cicel (BG&E) to NRC Document Control Desk, dated January 29, 1990, Response to NRC Generic Letter 8913, same subject l
i l Gentlemen:
l NRC Generic Letter 8913. Reference (a), outlined concerns regarding the safe operation and maintenance of the senice water systems and identified several recommendations associated with ensuring proper heat transfer capability of service water system components. Recommendations were provided to confirm that plant service water systems continue to meet the heat removal requirements associated with their safety functions.
l Baltimore Gas and Electric Company's response to Generic Letter 89-13 was provided in Reference (b). In that response we outlined a program of surveillance and control techniques to significantly reduce the potential for Dow blockage as a result of biofouling (Task I - Saltwater Biofouling Program). We also outlined a test program for the safety-related heat exchangers within the Saltwater, Service Water and Component Cooling Systems to demonstrate that the required heat transfer capability can be met (TASK II Test Program). The iurpose of thLs letter is to inform you of changes which we have made to these two programs No e aanges have been made to Tasks III, IV, or V. /
no s ~,
Mull 40360 KO104, 4/& 1 FOR \ \
ADOCK Co.sou217 I F FDR -
Document Control Desk January 6,1992
. Page 2 REVISIONS TO TASK ! SAlllWATER lilOFOULING PROGRAM in Reference (b) wc av:aitted to install a new chlorination (sodium hypochlorite) system to reduce biofouling in the Saltwater System. System installation was completed in April 1990. Following further study and operating experience with the Sodium liypochlorite System, we have found that the system is not effective in controlling heat exchanger tube blockage due to macrofouling (grass, mollusks, etc). Instead, we are now successfully controlling macrofouling in the Saltwater System by performing routine cleaning of the intake structure cavity walls, relocation of the ECCS cooler supply line penetration from the bottom of the 24-inch Saltwater header piping to the side of the piping, and removing unnecessary, stagnant water piping runs (dead legs) in the Saltwater System.
Operation of the Sodium Ilypochlorite System is no longer deemed essential to assure the capability of the Saltwater System to perform its safety function; it is being retained for possible use in controlling microfouling (e.g., algae) as an enhancement to heat exchanger performance. Its use can potentially reduce the frequency of Sen' ice Water IIcat Exchanger tube bulleting.
We originally stated that a new program would be established to ensure that Saltwater loops are properly placed in lay-up with biocide if the need arose. To date, cleaning of the intake structure cavity walls has significantly reduced the sloughing and intake of macrofouling debris and the need for lay-up with biocide has not arisen. We will continue periodic inspections of isolated portions of the system and re-evaluate the need for lay-up with biocide if significant macrofouling is observed in the future.
REVISIONS TO TASK 11 TEST PROGRAM NRC Generic Letter 89-13 recommended that a test program be conducted to verify the heat transfer capability of all safety related heat exchangers cualed by senice water. The Reactor Vessel Support Coolers and the Steam Generator Support Coolers are classified in the CCNPP Q-List as non-safety related (NSR) and do not perform any safety-related heat removal function. The Containment Penetration Coolers rnd LPSI Pump Seal and Bearing Coolers are safety grade components but only for the function of being a pressure boundary (PB) in a safety system. They do not perform a safety-related heat removal function. Because these coolers do not have a safetv-related heat removal function we have climinated them from this test procram.
Genotic Letter 8913 stated that an alternative to testing the heat removal capacity of safety-related hev . < changers is to either inspect or functionally test them. Functional testing verifies that a heat exchanger performs its intended function at operating conditions. This alternative is intended for those heat exchan;;crs for which the design heat removal rate cannot be quantified due to testing limitations. One possible testing limitation is measuring flow in small diameter pipes. The Iligh Pressure Cafety Injection (HPSI) Pump Seal and Bearing Coolers have a small diameter pipe which may prevent now measurement, if the pipe diameter of these coolers does prevent now measurement, we may conduct a functional test instead of testing their heat removal canacity.
Attachment (1) contains an updated version of the Heat Exchanger Test Program. Page 4 of this attachment reflects the modifications to the program.
... . . . - . - - . . . - . . . - . - . - _ . . - . . . . - _ . - . . . - . - ~ = - _ . - _ . . . . . . ..
.f e
Document Control Desk January 6,1992 Page 3 i-Should you have any further questions regarding this matter, we will be pleased to discuss them with you.
Vety truly yours, d ') ^
I (,l GCC/LMD/Imd/bjd/dlm Attachment cc: D. A. Brune, Esquire ;
J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mr Donald, Jr., NRC T. T. Wrtin, NRC A. G. Howe, NRC -
R.1. McLean, DNR J. H. Walter, PSC
'l Page1 of 7 -
A'ITACIIMENT (1) .
~
?
IIEAT EXCHANGER TEST PROGRAM I
IN TEST TEST PERIODICTEST SYSTEM HEATEXCHANGER PROGRAM TYPE FREQUENCY COMMEN'IS Component Cooling ' Y I I At least quarterly. Test Type II.B will also be performed prior to Heat Exchangers and following HX bulleting. Per the
- S ILB ILB. At least once ' recommendation of GL 89-13, periodic test A' per Refueling Cycle. frequencies will be adjusted based on results
'L oftesting.
T
.W A- Service Water Y: I I Atleastquarterly. Test Type ILB will also be performed prior to T Heat Exchangers . . and following HX bulleting. P:r the E ILB ILB Atleastonce recommendation of GL 89-13, periodic test R per Refueling Cycle. frequencies will be adjusted based on results
- of testing.
l
' ECCS Pump Room . Y. I Atleast once per BasM on the results ofinitial tests, the I 'S . AirCoolers IILA. ' Refueling Cycle. appropriate periodic test type will be Y or selected. Per the recommendation of GL 89-13, 4
~S..
IILB periodic test frequencies will be adjusted .
t . T .; based on restas ef tecting.
i E'
M i- Intake Structure N- -. -
These coolers do not perform a safety-related -
i . Air Coolers function. Saltwater flow is isolated on Sdety 3
InWien Actuation Signal f
i t
4 i
. , , ,. , , , . .. . ~ - . . . _ _ _ _ . . m
4 Page 2 or7 ATTAC11 MENT 0) .
11 EAT EXCIIANGER TEST PROG 8' AM IN TEST TEST PERIODICTEST SYSTEM HEAT EXCHANGER PROGRAM TYPE FREQUENCY COMMENTS i Containment Air Y III.A.
V I Spent Fuel Pool Y ILB.
- Periodic testing will only be conducted ifit C Cooling Heat Exchangers is shown that a system wide corrosion induced E fouling problem exists.
Diesel Generator Coolers Y ILA W Main Turbine Lube N - -
A Oil Coolers T
E Main Feed Pump Turbine N -
R Lube Oil Coolers l
EHC Oil Coolers N - -
'Ihese HXs do not perform a safety function. '
Service Water flow to these ILXs is isolated on a S SafetyInjection Actuation Signal.
Y S Generator / Exciter N - -
T Air Coolers E
M Stator Liquid Cooling N - -
Heat Exchangers (U-1)
Hydrogen Seal Oil N - -
Coolers (U-2)
Page3 of 7 i
4 ATTACIIMENT (1) ,
i IIEAT EXCIIANGER TEST PROGRAM IN TEST TEST PERIODICTEST
. SYSTEM HEAT EXCHANGER PROGRAM TYPE FREQUENCY COMMENE Aux Feedpump Room ^ N - -
S Air Coolers - i E
, R Isophase Bus Duct Coolers N .- -
V I- I Condenser Air Removal N - -
i
. C Pump Seal Coolers .. .
. .E' '
Waterbox Priming. N - -
- Pemp Seal Coolers i
- .- W Condensate Booster Pump N -- -
These HXs do not perform a safety funcien.
i: A Lube Oil Coolers Service Water flow to these HXs is isolated on T a Safety Injection Actuation Signal.
. E Instrument and Plant N - -
- j. .R Air Compressor Coolers Turbine Plant Sample iN - -
Coolers i i :- 3
, Y . M/U Demin Vacuum N - -
S Pump Cooler (U-1) i- T
.E' N2Compressor After . N - -
l< M Coolers (U-1) ,
i Steam Generator Blowdown N - -
HX does not remove heat from safety-related '
l Recovery System Heat - system / component. HX is safety rela:cd for -
,- Exchanger pressure beandary purposes only.
4 I i' i
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< ..- ,.-- , -- , ,m .. . - . . . . _ , . - .
A
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Page 4 of 7 A'ITACllMENT (1) .
IIEAT EXCIIANGER TEST PROGRAM IN TEST TEST PERIODICTEST SYSTEM IIEATEXCIIANGER PROGRAM TYPE FREQUENCY COMMENTS Shutdown Cooling Y - ILB. *
- Periodic testing will not be performed unless it C Heat Exchangers is shown that a system wide corrosion induced O fouling problem exists.
M.
P IIPSI Pump Seal & Y IV.B. *
- Periodic testing will not be performed unless it O Bearing Coolers is shown that a system wide corrmion induced N fouling problem exists. Initial tc4 ting will E verify adequat- component cooling flow and the N bearing and seal cooler temperatures can be T maintained below the design limit.
LPSI Pump Seal & N - - 1 C Bearing Coolers O These Heat Exchangers do not perform a O Containment N - -
safety-related function. They are safety L Penetration Coolers ;.: lated for pressure boundary purposes only.
I. Main Steam N Main Feedwater G Letdown RCSample r S/G Blowdown S
Y Reactor Vessel N - -
S Support Coolers These Heat Exchangers do not perform any T safety-related heat removal function. They '
E_ S/G Lateral Support - N - --
are classified as non-safety related.
M - Coolers
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Page 5 of 7 NITACIIMENT (1) .
IIEAT EXCIIANGER TEST PROGRAM IN TEST TEST PERIODICTEST 4 SYSTEM HEAT EXCHANGER PROGRAM TYPE FREQUENCY COMMENTS I
C Reactor Coolant N - -
O Waste Evaporators M
P Control Element Drive N - -
These IIXs perform no safety-related function.
O Mechanism Coolers Component Cooling flow is isolated on N Containment Isolation Signal.
E Reactor Coolant Pump N -- -
N Seal and Lube Oil Coolers T
Reactor Coolant Drain N - -
Tank. Heat Exchangers C
O Letdown Heat Exchanger N - -
O L Waste Gas Compressor - N - -
I Coolers N
G RCW Degasifier Vacuum N - -
These HXs perform no safety-related function.
Pump Coolers They are classified as safety related for '
Component Cooling System pressure boundary S. NSSS Sample Coolers N g- -
purposes only.
i Y RC Sample :
S SG Blowdown Sample T MWS Sample E
M Post Accident Sample N - -
System Cooler
I' age Gof 7 ATTACIIMENT (I) .
IIEAT EXClIANGER TESTI'ROGRAM INTEST TEST PERIODlCTEST SYSTEM IIEAT EXCIIANGER PROGRAM TYPE FREQUENCY COMMEN"IS CCS Gas Analyzer Sample N - -
OOY Coolers MOS These HXs perform no safety selated function.
PLT Hey are classified as safety related for OI E MWS Heat Exchanger N -- --
Component Cooling System pressure boundary NNM purposes only.
EG N
T S/G Blowdown RAD Monitor N - -
Sample Cooler 4
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' Page 7 of 7 ATTACIIMENT (2)
IIEAT EXCllANGER TEST PROGRAM TEST TYPES
- 1. Monitor av - -ling water now and inlet and outlet temperatures for all affected heat exchangen , s of t ution in which cooling water is flowing through the heat exchange, 't .
..caem, erhy that the cooling water temperatures and Dows are within desip ' . Niorn of the measurement. The test results from periodic testing shoulo i ~
that flow blockage or excessive fouling acetimulation does not exist.
II.A. Perform functional m. s schonger operating, if practical, at its design heat removal rate to verify u . panni r:. remperature and flow compensation should be made in the calculations to adjust the rafts of the design conditions. Trend the results, as explained above, to monitor degradation, ll.B. If it is not practical to test the heat exchanger at the design heat removal rate, then trend test results for the heat exchanger efficiency or the overall heat transfer coefficient. Verify that heat removal would be adequate for the system operating with the most limiting combination of Dow and temperature.
Ill.A Perform efficiency testing with the heat exchanger operating under the maximum heat load -
that can be obtained practically. Test results should be corrected for the off-design conditions. Design heat removal capacity should be verified. Results should be trended, as explained above, to identify any degraded equipment.
III.B If it is not possible to test the heat exchanger to provide statistically significant results (ior example, if error in the measurement exceeds the value of the parameter being measured),
then
- 1. Trend test results for both the air and water flow rates in the heat exchanger.
- 2. Perform visualinspections, where possible, of both the air and water sides of the heat exchanger to ensure cleanliness of the heat exchanger.
IV.A. If plant conditions allow testing at design heat removal conditions, verify that the heat exchanger performs its intended functions. Trend the test results, as explained above, to monitor degradation.
IV.B. If testing at design conditions is not possible, then provide for extrapolation of test data to Design conditions. The heat exchanger efficiency or the overall heat transfer coefficient of the heat exchanger should be determined whenever possible. Where possible, provide for periodic visual inspection of the heat exchanger. Visual inspection of a heat exchanger that is an integral part of a larger component can be performed during the regularly scheduled disassembly of the larger component. For example, a motor cooler can be visually inspected when the motor disassembly and inspection a : -beduled.
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