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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 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 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 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 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 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) 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 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 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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 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 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 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 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 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 ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl 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 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 ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) 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 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 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 ML20196K5721999-03-25025 March 1999 Forwards 1998 Annual Rept of Individual Monitoring, Using Form NRC-5 Format,Per Requirements of Reg Guide 8.7,App a, Format for Electronic Transmission of Exposure Data. Without Electronic Media 1999-09-28
[Table view] |
Text
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i; BALTIMORE GAS AND ELECTRIC 1650 CALVERT CUFFS PARKWAY + LllSBY, MARYLAND 20657-4702 oconoc c. cace' November 27,1991
- VICC PRESIDENT NUCLE AM ENEMQY (4 o)aeo.4 ass U. S. Nuclear Regulatory Commission Washingten, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Temporaty Non-Code Renair of ASME Code Class 3 Piping Gentlemen:
Baltimore Gas and Electric Company requests relief from ASME Code requirement; as allowed by 10 CFR 50.55a(g)(6)(i). This relief will allow the use of a temporary non. Code repair on Calvert Cliffs Unit 1 Class 3 piping in accordance with the requirements of Generic letter (GL) 90-05.
DESCRIPTION Cn November 24,1991, a 3Sinch through. wall hole was discovered on a 30" diameter concrete-lined carbon steel pipe in the Unit 1 No.11 Saltwater IIcader. The leak occurred on the inside radins of a 900 cibow on the discharge of butterfly valve 1-CV-5150 and upstream of the inlet of the No.11 Service Water IIcat Exchanger. A one-line drawing of the Saltwater system showing the location of the leak is included as Attachment (1).
The leak was discovered by a plant operator during normal watch rounds. The leak rate was estimated as less than 20 gallons per minute. At the time the leak was discovered, Unit 1 was operating at full power. Upon discavery of the leak, a wooden plug was inserted into the hole as a temporary means to stop the leak.
FLAW CilARACTERlZATION The Daw size was determined using ultrasonic examination. A large scale (1 inch between measurements) ultrasonic examination was performed to determine the extent of the flaw. A finer mesh examination (1/16 inches between measurements) was performed to provide data for the analysis. Sketches of the profile of the Gaw are included as Attachment (2). A drawing depicting the location of the Gaw is included as Attachment (3).
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'4 Document Control Desk November 27,1991 Page 2 ROOT CAUSE DETERMINATION Based upon the limited available data and until the flaw can be removed and analyzed, the most probable cause of the leak is accelerated corrosion as a result of failure of the concrete liner. This failure is most likely attributed to stress fluctuations caused by flow instabilities immediately downstream of butterfly valve 1-CV-5150.
The Dow disturbances probably caused a lluctuating pressure profile on the surface of the concrete liner, At the inner radius 01 the elbow, this would result in cyclic forces which tend to lift and separate the concrete from the metal surface. Eventually, the concrete would crack due to fatigue and the crack would propagate to the surface of the metal.
The surveyed failure indicates a long axis which is neither perpendicular nor parallel with the direction of How. As indicated by the attached sketches, the failure is relatively k)calized. These observations lead to the conclusion that the failure in the concrete is relatively small, exposing a small area of metal to accelerated corrosion and subsequent failure.
Following the Code repair, the Dawed material will be examined and a more detailed root cause analysis will be performed.
IMPRACTICAlliY OF CODE REPAIR WITIIOtrl' PIANT SilUTDOWN A Code repair of the flaw will require removal and replacement of the flawed section. Replacement of the elbow would require removing No.11 Saltwater Header from service for an extended period of time to effect the repair. Technical Specification 3.7.5.1 requires that the plant be shutdown if a saltwater header is out of service for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Therefore,it is not tx>ssible to perform a Code repair to the flaw without a forced shutdown of the plant.
PROPOSED MITilOD OF TEMPORARY REPAIR Our proposed temporary non-Code repair is to clamp a rubber lined patch over the hole. De clamp is not integrally attached to the pipe but rather relies upon the mechanical force of a U-bolt to hold it in place. The patch is Safety Related. The U-bolt has a channel steel strong-back with a pad and jacking screw that forces a r.bber patch (backed with a piece of steel plate) over the hole. A sketch of the temporary repair is included as Attachment (4). This patch is currently installed and it climinates allleakage from the Daw.
We have also examined the effects of flooding, spraying of water on equipment, and loss of flow if the temporary repair should fail and determined that it would not prevent safety related equipment from performing its function.
FL_ AW EVALUATION The structural integrity of the Dawed piping has been assessed using a "Through-Wall Flaw" evaluation approach as described in GL 90-05, Enclosure 1, paragraph C.3.a.
1 l
Document Control Desk November 27,1991 Page 3 in order to perform the analysis, ultrasonic readings of the Gaw area were hken at eight radial k> cations from the flaw along four vectors. The first readings were taken at one inch spacing in order to bound the maximum area of the Daw. Upon determining the area of the flaw, the examination area was narrowed to two inches on either side of the Gaw and readings were taken at a 1/16-inch spacing. From this data, the maximum size of the Daw was determined. Of the four pro 0les c.tamined, none execeded the GL 90-05 criteria of three inches or 15% of the circumference.
All deadweight, pressure, thermal, and sarcahutdown carthquake loads were combined to determine the stress at the Daw k> cation. A conservative corrosion rate was used in the evaluation to envelope degradation of the Daw and arrive at a limiting minimum wall thickness requirement. A three month corrosion allowance was used to justify the use of the tempcrary repair until the next inspection (see Augmented Inspecuon, below). A summary of the calculation is included in Attachment (5).
A stress intensity was dete mined as required in GL WOS and the resultant values for each axis were within the acceptance criteria. Therefore, we determined that the structnral integrity of the pipe is maintained and that the Saltwater System remains capabb of paforming all safety functions in the event of Design Basis Accidents and anticipated transients.
AUGMENTED INSPECTION As per the guidance in GL E05, five locations believed to be most susceptible to the same degradation mechanism have been selected and ultrasonically evaluated.
These evaluations determined that the sampled locations have not experienced a degradation.
In accordance with GL E05, the temporary repair will be removed every three months and the flaw will be ultrasonically examined. The results of those examinations will be compared to the structural integrity calculations to affirm the continuing acceptability of the temporary repair.
Additionally, the temporary repair will be visually examined weekly and any leakage quantified. Any 1
substantial increase in leakage will be evaluated and the structural integrity of the piping will be reconfirmed.
CONCLUSIOli Based upo; the guidance provided in GL 90 05, we have determined that temporary non-Code repair of thu llaw to avoid a plant shutdown is justified and that the structuralintegrity of the Dawed piping is maintained. We will perform a '
repair of the Dawed piping during the next refueling outage, which is currently scheduled to bt. un March 6,1992.
We have determined that the requested reliefis:
Authorized by law.
Will not endanger life, propert, or the common defense and security, and, is in the public interest conddering the burden on BG&E if the requirement is imposed.
1 1
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j Document Control Desk -
November 27,1991 Page 4 should you have any questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours,
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1 GCC/DDM/bdm/ dim 1
Attachment ec:
D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC L E. Nicholson, NRC R. I. McLean, DNR J. II. Walter, PSC e
Document Control Desk -
November 27,1991 Page5 bec:
M. J. Micrnicki W. R. Corcoran C II. Cruse /P. E. Katz R. C. DcYoung i
R. M. Douglass/R. F. Ash R. P. Heibel/I'. N. Pritchett j
C. P. Johnson C. C. Lawrence, III/A. R. Thornton R. B. Pond, Jr./S. R. Buxbaum, Jr.
L B. Russell /R. E. Denton/J. R. Lemons W. A. Thornton/E.1. Bauereis C.J. Antirews A. B. Anuje G. L Detter D. V. Graf B. S. Montgomery R. E. Nagel j
K. R. Neddenien i
R. C. L Olson P. A. Pieringer Technical Library L. O. Wenger B. D. Mann W. C Holston T. M. Delaney K. M. Hoffman F;te 13.02 NRC Chrono File
ATTACHMENT (1)
P&ID OF THE SALTWATER _ COOLING SYSTEM r
(DETAIL OF UFSAR DRAWING 9-8A)
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l ATTAcilL4ENT (21 ULTRASONIC MEASUREMENT LOCATIONS AND PROFU.ES OF THE FLAW
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SALT WATER HEADER LEA.K LARGE SCALE READING Pipe Wall Thicitness (Mila) 600 4
500 r- -
t I
t 400'----------------------------------------------------------
s l
t t
I 300------------------------------------------
I r
I I
200.
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f h-
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f 100'-------------------------------------------------------------------
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1 f
f O
1
-8
-6
-4
-2 0
2 4
6 8
Distance From Center of Flaw (in)
Salt Water Header Leak
- Pipe Wall Thickness (Mils) 200
- ------ - - --- N l ~---
A tv" 150 -fs-W _ _ _ ',m j
4-iao
l--------
l
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so o
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-1 0
1 2
Distance From Center of Flaw (in)
e Salt Water Header Leak
- Pipe Wall Thickness (Mils) 350-300; 250 t-i f
200 t 3/
iso!
- --\\
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(
r-100k --
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Distance From Center of Flaw (in)
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- L Pipe Wall Thickness (Mils) 500 i
400--------------------------------------
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Distance From Center of Flaw (in) 4 h
q.
ATTACHMENT (3)
LOCATION OF THE SALTWATER HEADER LEAK
UNIT 1 SALTWATER HEAbER LEAK o WCATION -:
UNIT 1 SERVICE WATER ROOM o LEAK DESCRlFT10M :
INSIDE RAblUS OF.30" EL20W BOWN5TIEAIA OF 1-CV 5150. ( Vs" # HOLE 1 -
IMLET To NO.11 SERVICE WATER HEAT EXf_HAMC,ER.
EAST tcotNG EAST dCATi$b g
30" LI 01-lol1 y
N j
/
- [ l-- - ~3 m
93
.[
I_
1 s
t_
x n
N l
- -CV-5150 l
(+)~7' FRDM THE FLAAIC,E
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mv
ATTACHMENT (4)
DIAGRAM -0F THE TERPJRARY NOR-C.0_DE REPAIR
- - _ _ _ _ - - -, _ _. - - - - - -, - - - - - - -.. _ _ _, _ _. - - - - - _ _ ~. - - - - - _. - - _ - - _ - - - - _ - - _ _ _. - - - - - - - _ - _ _
3-1/2" w
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f
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s
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/
/
l/
//A 2"
/
/
x y
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If N
O gg / ~~~
1/2" DIA. x 1/4" O
W/////N/////b J'
~
item Description Quantity 1
3/4* A-108 Bar Sto:k 94" 2
C6 x 10.5 A-36 42" 3A 2" x 31/2" x 1/2" A-30 Plate 1
3B 2" x 31/2" x 1/2* Rubber 1
4 7/b" A-193 Grade B7 All Thread G"
/
5 3/4" A-194 Grade 2H Nuts 4
I 6
7/8" A-194 Grade 2H Nuts 2
SEE bTE E f
Notes _;
l l________________________b i
a)
Use safety related material.
4 7
b)
Washers to suit.
y c)
Use 1/4" Fidet Weld to Weld 7/8" Nut to Backside of Channel
/
d)
A 7/8" nut shall be tack welded to the end of item No. 4 5
e)
Channel (Item 2) is actually in contact with the pipe. Note that the above expanded drawing is provided for clarity.
,a p +
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.6 4
ATTACHMENT (5)
SUMMARY
OF STRUCTURAL INTEGRITY CALCULATION 1-l l
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ANALYSIS OF SW THROUGH WALL FLAW UNIT 1-(CA OF.15"/ YEAR,.0587" MIN WALL M91-048)
(.005 TOL UT, Paint Removed) 0 - 180 45 - 225 90 - 270 135 - 315 ELB OD 30.000 ELB OD 30.000 ELB OD 30.000 ELB OD 30.000 R
14.949
=R 14.949 R
14.949 R
14.949 r
147.721 r
147.721 r
147.721 r
147.721 s
3.744 s
3.744 s
3.744 s
3.744 2a 0.836 2a 0.801 2a 0.732 2a 0.640-a 0.418 a
0.401 a
0.366 a
0.320 t(MIN)
O'.101 t(MIN) 0.101 t(MIN) 0.101 t(MIN) 0.101 t(ADJ) 0.101 t(ADJ) 0.101 t(ADJ) 0.101 t(ADJ) 0.101 t(NOM) 0.375 t(NOM) 0.375 t(NOM) 0.375 t(NOM) 0.375 A
3797 A
3797 A
3797 A'
3797 B;
-9717 B
-9717 B
-9717 B
-9717 C
9562 C
9562 C
9562 C
9562 c
0.009 c
0.009 c
0.008 c
0.007
-F 4.117 F
3.926 F
3.563 F
3.100 K
24.7 K
23.1 K
20.0 K
16.3 NOTE: (1)'TO FULLY COMPLY WITH THE GENERIC LETTER, t(ADJ) IS EQUAL TO t(MIN).
(2) NOMENCLATURE MATCHES GENERIC LETTER 90-05.
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