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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999 Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System ML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999 Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999 Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-03
[Table view] |
Text
. . - . - - - - . . - .- - .--__.- - -- -- - -. .-
4 g g g y 8. g v.ii.y eo ,si.iu>n Shippingport. PA 15077-0004 l o$n vNesw.nl March 27, 1996 r.x N $ N
. : :l:: 2 L n U. S. Nuclear Regulatory Commission Attention: Document Control Desk ,
Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Steam Generator Tube Pull Data (Supplemental)
Supporting Alternate Tube Plugging Criteria Implementation Attached is a copy of the industry steam generator tube pull data in support of our proposed Operating License Change Request 229. This data is proprietary and replaces that previously provided by our letter dated March 7,1996, identified as Table 1 and Table 2, with supporting text. This data supports the upper voltage repair limit calculation for the Unit 1 eleventh refueling outage as presented in Enclosure 1 of our March 7,1996, submittal. This data is provided in response to a request from our NRC j Sr. Project Manager to clarify the basis for exclusion of proprietary information since the March 7 submittal was not specific. An affidavit is provided as an attachment pursuant to 10 CFR 2.790(aX4) from the Electric Power Research Institute (EPRI), the owner of the information, which sets forth the basis on which the information may be withheld from public disclosure.
On March 25,1996, it was agreed to docket an earlier verbal commitment regarding the reporting of the fraction of rotating pancake coil no detectable degradation (RPC NDD) indications included in the beginning of cycle distribution. Therefore, the Duquesne Light Co. will include the fraction of RPC NDD applied in the beginning of cycle voltage distribution and the RPC NDD confirmation rate from the inspection data in the 90 day report following steam generator inspections. (Ref: Generic Letter 95-05, Attachment 1, item 6.b).
If you have any questions regarding this submittal, please contact Mr. G. S. Sovick at (412) 393-5211.
Sincerely, 01CCSO Sushil C. Jain c: Mr. L. W. Rossbach, Sr. Resident Inspector / MW' ERING Mr. T. T. Martin, NRC Region I Administrator gf j gg,t,7y Mr. D. S. Brinkman, Sr. Project Manager plF l ENERGY 9604020034 960327 A PDR ADOCK 05000334 U d UO( )
P PDR ~ i i t\
4 l
i AFFIDAVIT :
I, ARTHUR KENNY, being duly sworn, depose and state as follows:
I am a Intellectual Property Attorney of the Electric Power Research Institute
- ("EPRI") and I have been specifically delegated responsibility for reviewing the records,.
documents and information sought under this affidavit. to be withheld (the "Information") and authorized to apply for their withholding on behalf of EPRI. This i
affidavit is submitted to the Nuclear Regulatory Commission ("NRC") pursuant to 10 CFR 2.790 (a)(4) based on the fact that the Information consists of trade secrets of EPRI owned by EPRI and that the NRC will receive the Information from EPRI under ;
privilege and in confidence. )
The Information, which EPRI requests the NRC to withhold, consists of EPRI !
owned Proprietary Informe. tion contained within The attached document entitled "EPRI . t ARC Database For 3/4 Inch and 7/8 Inch Diameter Tubes and Updated ARC '
Correlation For 7/8 Inch Diameter Tubes". The Information has been marked as PROPRIETARY AND CONFIDENTIAL. i EPRI desires to disclose the Information to the NRC for informational purposes to assist the NRC. EPRI would welcome any discussions between EPRI and the NRC related to the Information that the NRC desires to conduct.
The basis for which the Report should be withheld from the public is set fo'r th below:
(i) The Information has been held in confidence by EPRI. EPRI intends to provide copies of the Informaion to EPRI members and to one or more EPRI contractors. EPRI members and contractors are bound by confidentiality agreements to preserve the confidentiality of proprietary and confidential documents received from EPRI. Receipt of the Information by such members and contractors will not impair the proprietary and confidential nature of the Information nor will such receipt impair the value of the Information as trade secrets. In addition, EPRI may license the Information to organizations that are not EPRI members.
a Page 2
, l i
6 (ii) The Information is of a type customarily held in confidence by EPRI and there is a rational basis therefor. The Information is of a type that EPRI considers to be trade secrets. Such Information is customarily held in confidence by EPRI because to ;
disclose it would prevent EPRI from licensing the Information at fees which would l allow EPRI to recover its investment. If consultants and other businesses providing services in the electric power industry were able to obtain the Information, they would ,
be able to use it commercially for profit and avoid spending the large amount of money !
that EPRI was required to spend to obtain the Information. The rational basis that EPRI !
has for classifying information as a trade secrets is the Uniform Trade Secrets Act which ,
California adopted in 1984 and which has been adopted by over twenty states. The Uniform Trade Secrets Act defines a " trade secret" as follows:
" Trade secret" means information, including a formula, pattern, compilation, program, device, method, technique, or process, that:
(1) Derives independent economic value, actual or potential, from not being generally known to the public or to other persons who can obtain economic value from its disclosure or use; and (2) Is the subject of efforts that are reasonable under the circumstances to maintain its secrecy.
(iii) The Information will be transmitted and received by the NRC in confidence.
The purpose is to maintain the confidentiality of the Information. ,
(iv) The Information is not available in public sources. EPRI developed the Information only after making a determination that the Information was not available from public sources. EPRI was required to spend a large amount of money through payments to contractors. In addition, EPRI was required to use a large amount of time of EPRI employees. Finally, the Information was developed only after a long period of effort. '
(v) A public disclosure of the Information would be highly likely to cause substantial harm to EPRI's competitive position. The Information can be properly acquired or duplicated by others only with an equivalent investment of time and effort.
1
'c Page 3 I have read the foregoing and the matters stated therein are true and correct to the best i of my knowledge,information and belief.
l I make this affidavit under penalty of perjury under the laws of the United States of l America and under the laws of the State of California. j Executed at 3412 Hillview Avenue, Palo Alto, being the premises and place of business of the Electric Power Research Institute l
March 22,1996 l Arthur Kenny ;
)
Subscribed and sworn before me this day: i r
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/ ,
i 4 NOTARY PUBLIC
.....me
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7 TAMSEN HELEN GAGNON E a t= COMM. # 1016243 2
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u SANTA CLARA COUNiY
' My Comm. Emowes FEB 5.1998 y f
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t NOTIX
- 1. All voltages normalized to the recommenkd values of this report.
- 2. Qack network length for txrst crack, with tirough wall crack length given inem;a
- 3. N.O. leak rates are adjusted to AP = 1450 psi per Appendix B of Referenm 1. SLB leak rates are adjusted to reference AFs shomt
- 4. Normalized to 150 ksi flow stress (sum of yield and ultimme stress).
- 5. Coham uncaes agplication of specimen in leak rate and'or burst cxurelations. 0 = Ng i = Yes
- 6. Ihta excluded from agplication to m mlaions based m EPRI data exclusion criterion 2.
- 7. N.R. = Not Reliable data.
- 8. 98% deep for 0.22"; >95% deep for 035". '
- 9. N.M. = Not Meastred; value of 169.8 ksi in parenthses assumed for burst presstue adjustments when measurements not available.
- 10. Aw fmultiple meastrervents,
- 11. Burst test cordicted within TSP. Diast gressure not used in ARC database
- 12. Inferred frtun destructive exarn depth, leak test not performed. Cormsion depth too shallow leakage at SIE ardtions.
- 13. Den exduded frorn applictim to mm;oiki6 based m EPRI chta exclusion critenon 1. .
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NOIES
- 1. All voltages inmalized to the inu-u.ded values of this report. l
- 2. Crack network length for burst crack, with through wall crack length given in parentheses. ,
- 3. N.O. leak rates are adjusted to AP = 1300 psi per Appendix B of NP.7480-1, Volume 2. SLB leak rates are adjusted to reference ops shown.
- 4. Normalized to 150 ksi flow stress (sum of 3ield and ultimate stress).
- 5. Column indicates application of specimen in leak rate and/or burst conelations. 0 = No,1 = Yes
- 6. leak rate infemd from destructive examination crack morphology Conosion depth too shallow for leakage at SLB conditions.
- 7. N.R. = Not Reliable data.
- 8. Burst tests performed with TSP constramt; data not used in ARC burst conelation. l
- 9. Conservatively calculated with CRACKFID code; included per NRC directive.
- 10. Data excluded from application to correlations based on EPRI data exclusion criterion 2.
- 11. Burst test showed insignificant extension at the corrosion crack tips. Therefore, burst pressure is a minimum va!ue since burst is defined to include crack extension.
- 12. Data excluded from application to correlations based on EPRI data exclusion entenon 1.
- 13. Data meets EPRI data exclusion entenen 3.
- 14. Second thruughwall crack 30 degrees frern burst crack.
i i
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4 1
b T4pme WP54 3
L 1.0 Updated ARC Correlations for 7/8" Tubes This section reports on the evaluations performed which utilized the results ofleak '
rate and burst testing of tube sections removed from SGs at utility sites in the
- United States after the publication of the original EPRI database for 7/8" diameter SG tubes (NP-7480-L, Volume 1). The results of the destructive examinations of the tube sections were reported in utility specific reports, and will be summarized in the complete data update report to follow. The additional pulled tube data ger-mane to the APC correlations, and the bobbin amplitudes for APC applications, will be contained in a table in the complete update report to be issued at a later date.
The additional data consist of results from pulled tube sections from Beaver Val- ;
ley 1 (SG 95 06-006, May 1995), Farley 2 (SG 95 07-010, July 1995), Sequoyah 1 (SG-96-01-007, January 1996), and Farley 1 (SG-96-01-003, January 1996).
The results of the leak and burst tests are compared herein to the database of ,
similar test results for 7/8" outside diameter SG tubes, and the effect ofincluding j the new test data in the reference database is evaluated. In summary, the applica- i ble test data are consistent with the database relative to the burst pressure, the probability ofleak, and the leak rate as function of bobbin amplitude correlations i for 7/8" diameter tubes. The comparisons and evaluations follow. j l
Suitability for Inclusion in the Database l l
l The morphology of the degradation of each indication considered herein was i reviewed relative to the EPRI guidelines for inclusion / exclusion of tube specimen data in the alternate plugging criteria (APC) database. The findings of the reviews were recorded in documents prepared for each utility as the data were obtained.
The details of the reviews will be included in a comprehensive report to be issued at a later date dealing with multiple tube sizes. None of the reviews revealed information that would lead to a conclusion that the data considered in this section should not be included in the database. Therefore, the correlations reported herein should be considered applicable to the use of APC for indications in 7/8" diameter tubes in Westinghouse SGs and constitute the analyses of the updated database.
1.1 Free Span Burst Correlation The burst pressure database used in this report for 7/8" tubes consists of the EPRI recommended database, plus test results from tube R11C60-1 removed from D.C. !
Cook Unit ' . The results for this tube section were abnormally high, but the l degradation morphology did not meet all of the exclusion criteria developed for degradation with abnormally high burst pressures, hence it was retained in the correlation database. The results from ten (10) burst tests, performed on tube D:\APC\EPRI 78.296 }*1 03/26/96
0 specimens which exhibited a non-zero bobbin amplitude at a TSP elevation location, were considered for evaluation. A plot of the burst pressures of the additional !
specimens is depicted on Figure 1-1 relative to the burst pressure correlation devel-oped using the reference database and relative to a 95% confidence band to contain l 90% of the population of burst pressures.
l 1. A visual examination of the data relative to the EPRI database indicates l that the burst pressures measured fall within the scatter band of the refer-l ence data.
l I
l 2. Nine, i.e.,90%, of the data points fall within a 95%/90% tolerance interval l l (approximate) about the regression line (95% confident to contain 90% of the underlying normal population).
- 3. One, i.e.,10%, of the data points falls outside of the 95%/90% tolerance i l band about the regression line.
In summary, the visual examination doesn't indicate any significant departures from the reference database. Although the burst pressure is less than would have ,
been expected for one of the indications, the appearance of one such indication in i the additional ten data points is not significantly improbable. Moreover, the bobbin amplitude for this indication increased from 4 volts before removal to 12 volts after, thus, the burst pressure could have been reduced as a consequence of mechanical deformation from the tube removal activities. Since the regression line for this analysis represents the mean and median burst pressure to be expected from the l
parent population, it would be expected that additional data should fall about half above and half below the line. For the additional data analyzed, six (6) values were above the line and four (4) values below the line. For ten values drawn at random
! from the population of bursts, the probability that the split would be five above and five below is about 25%, and the probability that the results would be split six/four in either direction is 41%. Thus, distribution relative to above or below the regression line is not unusual. In addition, the average difference in the observed burst pressure relative to the predicted burst pressures is only 1.1%. Finally, al-though the tube data are from SGs at multiple plant sites, an examination of the normalized residuals relative to the predictions of the reference correlation equa-tion was performed. The results of this analysis are shown on Figure 1-2 where the l distribution of observed deviates is compared to those expected from a normal l distribution. There doesn't appear to be any significant systematic departure from normality.
1
( Since the additional burst pressure data were not indicated to be from a separate i population from the reference data, the regression analysis of the burst pressure on i the common logarithm of the bobbin amplitude was repeated with the additional 1
DMPC\EPRI48.296 12 W 26S6
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data included. A comparison of the regression results obtained by including these ;
data in the regression analysis is provided in Table 1-1. Regression predictions ob-tained by including these data in the regression analysis are shown on Figure 1-3.
The appropriate regression equation for future ARC analyses is, l
P3= 7.592 - 2.370 log (Volts), (1-1) ,
i 4
with a SLB structurallimit of 8.6 volts. The changes to the correlation are:
- 1. The intercept of the burst pressure, Po, as a linear function of the common logarithm of the bobbin amplitude regression line is increased by 0.48%.
This has the effect ofincreasing the predicted burst pressure as a function of the bobbin amplitude.
- 2. The absolute slope of the regression line is increased by 2.19%, i.e., the slope is more steep. This has the effect of decreasing the burst pressure as a function of bobbin amplitude for indications greater than about 3 volts.
- 3. There is an increase in the standard error of the residuals of 1.38%. The effect of this change would be reflected in a slightly larger deviation of the 95% prediction line from the regression line.
The net effect of the changes on the SLB structurallimit (1.43 APst,3), using l 95%/95% lower tolerance limit material properties, is to decrease it by 0.2 volts, i.e., ]
from 8.8 volts to 8.6 volts. The increase in the slope relative to the increase in the l intercept, and the increase in the standard error coupled with the fact that the I structural limit is also decreased indicates that the probability of burst would also l increase for bobbin indications over the structural range ofinterest. Based on the l relatively small change in the structural limit, the change in the probability of l burst would also be expected to be small. I 1.2 Probability of Leak Correlation I
As for the burst pressure correlation, there are ten (10) additional data pairs that were considered relative to.the reference database and the probability ofleak (POL) correlation to the common logarithm of the bobbin amplitude. Figure 1-4 illus-trates the additional data relative to the reference correlation. All of the specimens except one exhibited POL behavior commensurate with expectations indicated by the reference database and regression curve. The single exception was an indica-tion with a bobbin amplitude of 4.03 volts that exhibited leakage, thus becoming the indication with the second lowest voltage of the indications that leaked in the database.
DWCWRM8.296 1-3 wasn,s
Based on the reference curve, the POL for the leaking indication is 0.133, thus, roughly 1 in 7 indications with an amplitude of 4.03 volts would be expected to leak. Had the expectation been 1 in 20, statistically anomalous behavior could have been suspected. The indication that leaked was the same indication that exhibited a lower than expected burst pressure. It is strongly suspected that this indication experienced ligament tearing during the tube pull as indicated by the maximum 96% corrosion depth resulting in post-pull Argon leakage at 200 psid and the increase in bobbin amplitude from 4.03 to 12.2 volts. However, since it is difficult to prove that the wall thickness ligament would not have torn during i postulated SLB conditions, the indication is to be retained in the EPRI database.
l In conclusion, data examinations revealed no significant evidence of irregular l results, i.e., outlying behavior is not indicated.
l l In order to assess the quantitative effect of the new data on the correlation curve, l
the database was expanded to include the additional data points and a Generalized ,
Linear Model regression of the POL on the common logarithm of the bobbin ampli- I tude was repeated. A comparison of the correlation parameters with those for the 1 reference database is shown in Table 1-2. These results indicate: '
l
! 1. A 9.7% increase (smaller negative value) in the logistic intercept parame-l ter.
- 2. A 6.2% decrease in the logistic slope parameter.
- 3. The absolute values of the parameters' covariance matrix changed by 26.5% to 34.5%. These changes may have a significant impact on the POL
! values used during the Monte Carlo Simulations, but may not have a
! significant impact on the 95% confidence bound on the total estimated leak '
rate from a single SG.
- 4. The Pearson standard error decreased by 7.2% from 0.640 to 0.594. This is a negative indicator since the ideal value would be 1.0, but is not judged to be significant.
l An additional evaluation was performed which demonstrated that most of the changes in the distribution parameters are a result ofincluding the 4.03 V indica-l tion that leaked. In order to assess whether or not these changes are significant, ;
l the reference correlation and the new correlation were also plotted on Figure 1-4.
I An examination of Figure 1-4 reveals a moderate change in the correlation up to i about 5 V, with a 31% increase at 4.03 V. A tabular summary of POL predictions before and after including the additional data point is provided as Table 1-3. For mdications with amplitudes less than 1.0 volt, the POL increases by a factor of 2 to i
DAAPC\EPRI.78.296 1-4 03/28/98
- 4. The POL for indications of 3 volts increases by about 50%, while the change in the POL is not significant for indications of 8 volts and greater.
When the totalleak rate is determined using the leak rate to bobbin volts correla-tion, the resulting value can be quite insensitive to the form of the POL function.
So, the effect of the changes in the parameter values and variances would be expected to be small or insignificant relative to the calculation of the 95% confi-dence bound of the total leak rate from a SG. However, when the leak rate is considered as independent of the voltage, as for the current APC database, the increase in POL will more directly affect the estimated total leak rate.
1.3 Free Span SLB Leak Rate Correlation for 7/8" Tubes As previously noted, only one of the specimens exhibited leakage at SLB operating conditions. The test leak rate value corresponded to 2.19 lph at the SLB tempera-ture and pressure difference conditions. The correlation ofleak rate to bobbin voltage exhibits a p-value of 6.5% for the slope parameter using the reference l
database, and a value of 6.4% with the additional data point. Based on the require- i ments stipulated in NRC Generic Letter 95 05 for voltage based plugging criteria, I the use of the correlation in performing Monte Carlo simulations to estimate the i totalleak rate from a SG is not considered to be justified. Figure 15 illustrates the j nev' data point relative to the distribution predicted mean using the reference j database and relative to a lower 95% confidence limit for a predicted leak rate from -
the distribution. Also illustrated on Figure 1-5, is the relation of the data point to the regression fit (median of the log normal distribution) and to the expected leak rate (mean of the log-normal distribution) based on the regression analysis of the leak rate on the bobbin amplitude.
The common logarithm (log) of the test leak rate,0.340, is lower than the mean log leak rate for the reference database,0.576, but is well within one standard devia-tion of that value. The effects ofincluding the data point in the database on the i estimated parameters of the leak rate distribution are tabulated in Table 1-4. The estimated mean and standard deviation of the population ofleak rates are de-creased, hence, predicted leak rates from Monte Carlo simulations and the 95%
confidence bound on the totalleak rate from a single SG will be reduced. For clarification, the values listed in Table 1-4 for the mean, p, and standard deviation, c, of the population ofleak rates are derived from the sample values of the log leak rate. These are the expected leak rate parameters to result from a simulation of i the log leak rates using the NRC accepted leak rate simulation method as described in WCAP-14277.
1.4 Summary / Conclusions DMPC\EPR148.296 1-5 owx
The review of the effect of the additional data indicates that the SLB structural limit hu se pressure will not be significantly changed by the inclusion of the data.
Therefore, it is likely that the conclusions relative to EOC probability of burst and !
based en the correlation obtained using the reference database would not be signifi- !
cantly affected.
The probability ofleak correlation to the common logarithm of the bobbin ampli-tude is moderately changed by the inclusion of the data, leading to the expectation of predicting slightly larger 95% confidence bound leak rates. At the same time, the mean and standard deviation of the leak rate distribution are decreased, !
leading to the expectation oflower 95% confidence bound leak rates. It may be i expected that the increase in the POL will be at least partially offset by the :
decrease in the predicted leak rates. j
)
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1 D:\APc\EPRI 73.296 16 Om
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Table 1-1: Effect of Additional Data on the 7/8" Tube Burst Pressure vs. Bobbin Amplitude Correlation !
1 Po = og + ot2 1og(Volts) !
Reference Database with New / Old ;
arameter Database Value additional Ratio og 7.5555 7.5919 1.0048
^ l 02 2.3192 -2.3699 1.0219 2
r 82.7% 81.8% 0.9891 o'g,,,, 0.81729 0.82853 1.0138 N (data pairs) 70 80 p Value for a, 1.4x10 27 1.3x10 3 9.3x104 Reference ai 68.78 ksit" '
Notes: (1) This is the flow stress value to which all data was normalized prior to performing the regression analysis. This affects the coefficient and standard error values. The corresponding values for a flow stress of 75.0 ksi can be obtained from the above values by multiplying by 1.0904.
1 I
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D:\APC\EPRI 78.296 1-7 0F2GS6 i
g g _ . ~
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Table 1-2: Effect of Additional Data on the 7/8" Tube Probability of Leak Correlation i
Pr(Leak) = f 1 + e-[A
i Reference Database with Parameter Change Database additional R 6.8974 -6.2269 -9.7% l
~
Q 8.35Y/ 7.7739 -6.9%
y (1) 3.4998 2.2911 -34.5%
V,2 -3.8459 -2.6004 -32.4%
V22 4.5822 3.2955 -26.1%
Eop2> 97 107 0 -
Deviance 25.09 28.90 15.2%
Pearson SD 64.0% 59.4 % -7.2%
Notes: (1) Parameters V are y elements of the covariance matrix of the coefficients, @, of the regression equation.
(2) Degrees of freedom. !
l D:\AP;\EPRI 78.296 1-8 03/2G/96
l.'
- o .
l Table 1-3: Effect of Additional Data on 7/8" Tube Probability of Leak Predictions Bobbin EPRI/NRC w/ additional Amplitude Database Database
** I Old Ratm.
(Volts) POL POL 0.100 2.39 10 8.31 10' 3.48 0.200 2.95 10 4 8.63 10' 2.93 l
0.300 1.28 10'8 3.39 10'6 2.64 0.500 8.18 10 1.90 104 2.33
~
0.600 1.58 10'4 3.52 10'4 2.22 l
0.800 4.50 10'4 9.29 10'4 2.07 l 1.000 1.01 104 1.97 10' 1.95 l
l 2.000 0.0123 0.0201- 1.63 l 3.000 0.0515 0.0746 1.45 4.030 0.1367 0.1793 1.31 I l 5.000 0.2572 0.3115 1.21 8.000 0.6557 0.6886 1.05
- , 10.000 0.8105 0.8245 1.02 l
15.000 0.9490 0.9486 1.00
~
20.000 0.9814 0.9799 1.00 '
S0.000 0.9957 0.9948 1.00 40.000 0.9985 0.9980 1.00 50.000 0.9993 0.9991 1.00 D:\.APC\EPRI 78.296 1-9 orsses 1
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? l Table 1-4: Effect of Inclusion of Additional Data !
on the Reference Leak Rate Database
! for 7/8" Tube APC Applications Leak Rate (lph) Log ( Leak Rate )'-
Parameter Reference w/ additional Reference w/ additional Database Database Database Database Sample Size 26 27 26 27 l
Sample 13.74 13.32 0.5764 0.5696 j Sample G 21.13 20.84 0.8338 0.8188 l
p Value ; f <
E 6.5% 6.4%
The following are based on the lognormal distribution sample parameters.
Population 23.91ph 22.0 lph These values are biassed to Population 0 149.1 lph 128.0 lph be higher than expected.
Upper 95% Pred. 100.61ph 92.5 lph These ranges are biassed to Lower 95% Pred. 0.143lph 0.149Iph be wider than expected.
Notes: 1. It has been previously shown that a log normal distribution can be used to describe the population ofleak rates.
i I
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e ourcstrai ts.298 1-10 ov2ces
Figure 1-1: Burst Pressure vs Volts for 7/8" Alloy 600 SG Tubes .
Additional Data, Reference o r= 68.8 ksi @ 650 F - .
12.0
.. ., EPRI/NRC Database 10.0 "- -
Additional Data
- _ _ _ _. _ __ Regression Curve N N .,, - ..,' ------ 95%/90% Tol. Band w * -
8.0 's s '
Q .., '-
d.
N y ...
N ..
'N s m 6.0
* .., .. s ,
m '. _. _ _
x h .. _
y ... \
g N 'w N e 4.0
__ _ N 2.0 ...
0.0
- 10. 100.
0.1 1-Bobbin Amplitude (Volts) _ . _ .
ppg. 2/24/96,3:24 PM 1 11 fMV 2se.elTotsend
O t
Figure 1-2: Burst Pressure for 7/8" Diameter Tubes ~
Deviate Analysis of Additional Data 2.5 . ._ . _ _
. Observed Data 2.0 Normal Distribution -
__ / .
t 1.5 _. . . . - __.
. 1.0 e ._. _ _
p ..
1 /. _
> 0.5 B /. _
.a /
l*o /
2+a -0.5
/ .
p,
/ . _ _ _ _ . .___.
M N -1.C .
/
* / - _.. - __.
-2.0
/
-2.5 0.0 0.5 1.0 1.5 2.0 2.5
-2.5 -2.0 -1.5 -1.0 -0.5 Observed Deviate Values RFK- 2/24/96. 3:23 PM 1-12 tvisv_2ss.xlelNow. Dows
~
Figure 1-3: Burst Pressure vs Volts for 7/8" OD Alloy 600 SG Tubes _
NRC/EPRI Database, Reference or = 68.8 ksi @ 650 F 12.0 EPRUNRC Database Additional Data 10.0 - Regression Curve m __ _ _ _ _
_ _ _ _..- - --- 95% Prediction @ LTL ,
+ New Regression cg 8.0 % x New 95% Pred @ LTL g%g~x ' %
.NM g No _
^
2 x. 3 g me 5 *
, % m g 6.0 .,
q ~
K~g~ %
$a u %.
%g
" w.
= N U x .,e N m '
N 40
_ _ _ . 3.657 ksi---
2h: -
Nm i %w ')
_ . . - g_5go y,; . .-. . .- ..... .... .-..-..- ..-......- ...... -. .-
}
I E9 i
,___ 7 s s.
a, 2.0 g
. se -
3:..
8.8 V - 28.5 V - - - - - -
r : -
0.0
- 10. 100.
1.
o.1 _
i Bobbin Amplitude (Volts) nm 2a4ss.3:2s pu peev_2ss.ximi avev.NRc 1-13
9 Figure 1-4: Probability of Leak for 7/8" SG Tubes _ .
Effect ofInclusion of Additional Data e ,
1.0 0.9 EPRI/NRC Database [
e Additional Data 0.8 f !
--- POL EPRI/NRC Data A
$ w/ Additional Data f 02 0.7 E
b *6 'l
< l
,3 0 5 (
.g 0.4
/
3 i
$ 0.3 r e j m
0.2 ri .
0.1 y x
g/
0.0 .
1.0 10.0 100.0 0.01 0.1 Bobbin Amplitude (Volts)
RFIC 2/24/96,3:26 PM F8poLSA]PollogM l-14
Figure 1-5: Leak Rate vs Bobbin Amplitude -
- 7/8" Tube Data, All Data, NRC Correlation 1000.0 _
Test Database _
Additional Data ,
Distribution Mean 100.0 - - - 95% Con 6dence "
-Regression Exp(Q) -
Regression Median (Q) 4 -. ----.. . - pc o 10.0 ,--
's" ,_
/
/
i g - -'
/ -
o _ .
' j ~
# ,< w' s
~
f f
s' W *"
1.0 m- _
m s
s
~
/ .... .. .. .. .. . . ........ ..... ... ... .. .. .... .
0.1 0.01 100.0 10.0 1.0 _
~ Bobbin Amplitude (Volts)
RFK:2/24/96,3:27 PM 1-15 F8qv>wc.2] NRC.PW
_ _ _ _ _ _ _ . _ - _ _ - . _ _ _ _ _ _ _ _ _}}