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Category:CORRESPONDENCE-LETTERS
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action ML20217F6321999-10-0707 October 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee ML20212K9421999-10-0505 October 1999 Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage ML20212J0451999-09-21021 September 1999 Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr ML20212D8231999-09-20020 September 1999 Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21 ML20212C6961999-09-15015 September 1999 Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys ML20211Q7961999-09-0909 September 1999 Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr, ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20211Q6511999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211F8251999-08-25025 August 1999 Forwards Insp Repts 50-254/99-15 & 50-265/99-15 on 990816-20.No Violations Noted.Insp Evaluated Effectiveness of Maint Rule Program & Review Periodic Evaluation Specifically Required for 10CFR50.65 ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20211D1491999-08-19019 August 1999 Forwards Insp Repts 50-254/99-16 & 50-265/99-16 on 990719-22.Staff Identified Major Discrepancy Re Accuracy of Data Submitted to NRC for Protected Area Security Equipment Performance ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20210R7451999-08-13013 August 1999 Forwards Insp Repts 50-254/99-11 & 50-265/99-11 on 990601-0720.NRC Identified Several Issues Which Were Categorized as Being of Low Risk Significance.Two Issues Involved NCVs of Regulatory Requirements SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated ML20210R9541999-08-10010 August 1999 Informs That During 990804 Telcon Between J Bartlet & M Bielby,Arrangements Were Made for NRC to Insp License Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M5461999-08-0606 August 1999 Discusses 990804 Telcon Between J Bartlet & M Bielby,Where Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L8371999-08-0202 August 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML20210M4691999-07-30030 July 1999 Forwards Insp Repts 50-254/99-14 & 50-265/99-14 on 990713-15.One NCV Was Identified & Discussed in Encl Insp ML20210H4661999-07-29029 July 1999 Forwards Insp Repts 50-254/99-13 & 50-265/99-13 on 990628-0702.No Violations Noted.Insp Consisted of Selective Examination of Procedures & Representative Records, Observations of Activities & Interviews with Personnel 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999 Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999 Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999 Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601 SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999 Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999 Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period ML20196F7921999-06-24024 June 1999 Forwards Meeting Summary,Nrc Meeting Handout & Licensee Handout from 990608 Meeting ML20196E7131999-06-23023 June 1999 Forwards Insp Repts 50-254/99-09 & 50-265/99-09 on 990421-0531.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20196E4821999-06-21021 June 1999 Discusses 990617 Meeting by Region III Senior Reactor Analysts (SRA) in Cordova,Il to Meet with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999 Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999 Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999 Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601 05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999 Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999 Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested SVP-99-125, Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl1999-06-15015 June 1999 Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl ML20195E3491999-06-0707 June 1999 Withdraws Util Requesting License Change for Plant Security Plan Rev.Licensee Will re-evaluate Situation & May Request Approval of Change in Future ML20207G1451999-06-0707 June 1999 Forwards Rev 45 to Comed Quad Cities Nuclear Power Station Security Plan.Rev Includes Changes Listed.Security Plan Is Withheld from Public Disclosure Per 10CFR73.21 ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs SVP-99-105, Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 9905291999-05-20020 May 1999 Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 990529 ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB SVP-99-111, Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-05-17017 May 1999 Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions SVP-99-098, Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i)1999-05-17017 May 1999 Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i) SVP-99-099, Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval1999-05-13013 May 1999 Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval SVP-99-096, Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 19991999-05-12012 May 1999 Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 1999 05000254/LER-1999-001, Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions1999-05-12012 May 1999 Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape SVP-99-108, Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 9903301999-04-30030 April 1999 Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 990330 SVP-99-036, Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions1999-04-29029 April 1999 Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions SVP-99-088, Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B1999-04-29029 April 1999 Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 SVP-99-065, Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License1999-04-14014 April 1999 Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License SVP-99-058, Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations1999-04-14014 April 1999 Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations SVP-99-063, Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval1999-04-0909 April 1999 Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick SVP-99-057, Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re1999-04-0505 April 1999 Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) SVP-99-062, Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-03-31031 March 1999 Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20065D0511990-09-17017 September 1990 Forwards Objectives & Scope of 901205 Emergency Plan Exercise ML20064A7091990-09-14014 September 1990 Forwards Endorsement 133 to Nelia Policy NF-187 & Endorsement 116 to Maelu Policy MF-54 ML20059F4891990-09-0404 September 1990 Forwards Listing of Changes,Tests & Experiments Completed During Month of Aug 1990 for Plant ML20059B9721990-08-28028 August 1990 Forwards Reactor Head & Upper Shell Insp Plan,Per 900419 Meeting.Insp Plan Does Not Encompass Uppermost shell-to- Shell Weld Due to Technological Limitations ML20059F0311990-08-27027 August 1990 Provides Schedule for Completion of Installation of Mods to Plants Reactor Water Level Instrumentation,Per Generic Ltr 84-23.Penetrations Will Be Installed During Outage 13 for Dresden & During Outage 12 for Quad-Cities ML20059E9531990-08-27027 August 1990 Forwards Summary of Fabrication History for Upper Reactor Vessel,Per 900419 Technical Meeting.Summary Indicates That Fabrication Mismatches,Considered to Be Significant for Development of Insp Plan,Identified at head-to-flange Weld ML20059C7201990-08-23023 August 1990 Forwards Effluent & Waste Disposal Semiannual Rept,Jan-June 1990 Gaseous Effluents-Summation of All Releases & Rev 8 to Quad-Cities Station Process Control Program for Processing of Radioactive Wet Waste ML20058P3481990-08-0909 August 1990 Forwards Summary of Fuel Performance,End of Cycle 10,May 1990. No Leakage or Fuel Failure Noted ML20058M8221990-08-0707 August 1990 Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20058M8041990-08-0606 August 1990 Advises That W/Completion of Operator Training Program,Plant SPDS Meets Requirements Delineated in NUREG-0737,Suppl 1 ML20058M8591990-08-0606 August 1990 Forwards Rept of Metallurgical Exam That Revealed No Evidence of Defects,Porosity or Slag in Weld Overlay. Rept Responds to IGSCC Insp Performed on Facility IGSCC Susceptible Piping ML20058M4101990-08-0101 August 1990 Forwards Listing of Changes,Tests & Experiments Completed During Month of Jul 1990 for Plant ML20058M8291990-07-31031 July 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements of Corrective Actions. Status of Implementation of Generic Safety Issues Encl ML20055J1631990-07-26026 July 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Quad-Cities Nuclear Power Station Unit 2,900427-28, & Related Apps Describing Type a Test,Per 10CFR50,App J, Section V.B.1.Next Test Scheduled for Fall 1991 ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055G6331990-07-18018 July 1990 Responds to Generic Ltr 89-06 Re SPDS to Meet Requirements of Suppl 1 to NUREG-0737.SPDS Lesson Plan Incorporated Into Initial License Class Training Program ML17202L2861990-07-0202 July 1990 Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. ML20055D4741990-06-29029 June 1990 Forwards Annual FSAR Update for Quad-Cities Station ML20055D4341990-06-29029 June 1990 Forwards Comm Ed Rept on Evaluation of Cracking in Quad- Cities Unit 2 Reactor Head, Per Commitment Made at 900419 Meeting W/Nrr.Rept Concludes That Cracks Caused by Interdendritic Stress Corrosion Cracking Mechanism ML20055C8551990-06-15015 June 1990 Forwards Special Neutron Attenuation Test for High Density Spent Fuel Racks (Wet), Final Rept.Rept Provides Results of Neutron Radioassay Measurement Program Conducted During Fall,1989 Refueling Outage ML20043D7661990-06-0404 June 1990 Responds to J Lieberman 900501 Ltr Re Rl Dickherber. Confidence in Dickherber Performance in Future for Nonlicensed Duties Can Be Based Upon Demonstrated Record of Good Past Performance ML20043D7691990-06-0404 June 1990 Responds to 900501 Ltr Re Work Hours for Dickherber.During Outage,Dickherber Worked Extended Hours Traditionally Associated W/Refueling Activities ML20043G4251990-06-0202 June 1990 Forwards Listing of Changes,Tests & Experiments Completed During May 1990 ML20043D3201990-06-0101 June 1990 Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043B6681990-05-22022 May 1990 Forwards Proposed Changes to SER Re Hot Shutdown Repairs in Event of Fire,Per 10CFR50,App R Section Iii.G Covering Spurious Operations & High Impedance Faults & Electrical Isolation Deficiency ML20043A4681990-05-10010 May 1990 Forwards Proposed Changes to 880721 SER Re App R Section Iii.G Exemption for Fire Zones 1.1.1.1S & 1.1.1.2,southern & Northern Torus Level in Unit 1 Reactor Bldg Column & Unit 1 Reactor Bldg Elevations 623 Ft & 647 Ft ML20042H0011990-05-0303 May 1990 Forwards Listing of Changes,Tests, & Experiments Completed During Apr 1990 ML20042G3501990-05-0202 May 1990 Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-254/90-02 & 50-265/90-02.Corrective Actions:Continuous Fire Watch Initiated & Training Conducted on Procedure Rev ML20042F1181990-05-0101 May 1990 Advises of Listed Value for Secondary Containment,Per NRC Request for Addl Info Re LER 50-254/87-025.Value Based on Info Contained in Plant FSAR ML20042F0691990-05-0101 May 1990 Responds to Generic Ltr 83-28,Item 4.5.3 Re Reactor Protection Sys on-line Functional Test Intervals.Endorses Two BWR Owners Group Topical Repts NEDC-30844 & NEDC-30851P Generic Evaluations ML20042F1221990-05-0101 May 1990 Forwards Preliminary Rept of IGSCC Insp Results.Flaw Indication Detected in Weld Overlay Matl of Weld 02J-S3 & Removed by Boat Sample & Std Weld Overlay Thickness Restored.Final Rept Will Be Forwarded within 30 Days ML20042E4491990-04-11011 April 1990 Forwards Request for Rev to Previous NRC Exemption Approval on 860625 Re Combustible Load Values ML20042F0351990-03-23023 March 1990 Forwards Part 3 of 1989 Operating Rept.W/O Rept ML19330D5161990-03-14014 March 1990 Advises That Revs to Inservice Testing Program & Implementation Procedures Will Be Completed by 900629,per Generic Ltr 89-04 ML20012C0721990-03-0808 March 1990 Comments on SALP Board Repts 50-254/89-01 & 50-265/89-01 for Oct 1988 to Nov 1989.Util Appreciates NRC Recognition of Overall Improvements in Areas of Operation & Emergency Preparedness & Good Performance in Area of Security ML20012B5921990-03-0202 March 1990 Forwards Listing of Changes,Tests & Experiments Computed During Month of Feb 1990 for Plant ML20006F3361990-02-0808 February 1990 Responds to NRC Ltr 900110 Ltr Re Violations Noted in Insp Repts 50-254/89-25 & 50-265/89-25.Corrective Actions:Safety Evaluations Submitted Via 900116 Ltr & Table of Content Will Be Completed for 1989 FSAR Update to Be Submitted by 900630 ML20012A9551990-02-0808 February 1990 Responds to Violations Noted in Insp Repts 50-254/89-26 & 50-265/89-26.Corrective Action:Procedure Qis 47-1 Revised to Include Requirement That Equalizing Valve Be Open During Isolation of Transmitter ML20011E7131990-02-0606 February 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test,Quad Cities Nuclear Power Station,Unit 1,891114-15. Next Type a Test Scheduled for Fall 1990 ML20006E1721990-02-0202 February 1990 Forwards Listing of Changes,Tests & Experiments Completed During Jan 1990,including Items Completed in 1989. Interlocks Installed on Refuel Bridge Fuel Handling Machine to Prevent Raising Hoist While Hoist Loaded ML20006C5071990-01-30030 January 1990 Identifies Schedular Change for Completion of Corrective Actions Associated W/Human Engineering Deficiencies 159,187 & 489 Re Escutcheon Plates for Control Switches Which Need Replacement.Plates Will Be Replaced During Outages ML20006C7401990-01-22022 January 1990 Advises of Receipt of Accreditation Renewal by INPO in Sept 1989 for Operator Requalification Training Program,Per Generic Ltr 87-07 Requirements & Informs That Programs Developed Using Systematic Approach to Training ML19354E8591990-01-16016 January 1990 Responds to NRC 891128 Ltr Re Violations Noted in Insp Repts 50-254/89-17 & 50-265/89-17.Corrective Actions:Procedure NSWP-E-01, Electrical Cable Installation Insp, Will Be Revised to Enhance Human Factor Aspect ML19354D8131990-01-11011 January 1990 Forwards Corrected App C to Monthly Operating Rept for Dec 1989 for Quad Cities Units 1 & 2 ML20005F6441990-01-0303 January 1990 Forwards Listing of Changes,Tests & Experiments Completed During Dec 1989.Summary of Safety Evaluations Being Reported in Compliance w/10CFR50.59 & 10CFR50.71(e) Also Encl ML20005E1691989-12-22022 December 1989 Forwards Rev 22 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facility.Rev Withheld (Ref 10CFR73.21) ML20043A5741989-12-21021 December 1989 Responds to NRC 891124 Ltr Re Violations Noted in Insp Repts 50-254/89-23 & 50-265/89-23.Corrective Actions:Compressed Gas Cylinder Bottles Secured W/Chain & Fire Marshall Will Increase Tours of Plant Re Transient Combustible Matl ML20005E1211989-12-18018 December 1989 Forwards Final Rept of Fall 1989 IGSCC Insp Plan,Discussing Items Such as Overlay Repair on Weld 02G-S4,mechanical Stress Improvement & Piping Mods ML19332G3401989-12-0808 December 1989 Forwards Response to Generic Ltr 89-21, Implementation Status of USI Requirements. Actions to Resolve USI A-9 Re ATWS Will Be Completed in June 1990 & USI A-42 Re Pipe Cracks in BWRs Will Be Completed in Dec 1990 ML19332F9091989-12-0101 December 1989 Forwards Listing of Changes,Tests & Experiments Completed During Nov 1989 1990-09-04
[Table view] |
Text
_ .__ __ _ __ _ _ _ . . _ . . . _ _ _ _ __ _ -
Commonwealth Edison '
2 1400 Opus Place E Downers Cr:ve, lilln:Js60515 J
June 4, 1990 Mr. A. Bert Davis Regional Administrator ,
Nuclear Regulatory Commission 799 Roosevelt Road
Subject:
In the Matter of R. L. Dickherber, License No. SOP-2365-8, ,
Docket No. 55-5043, EA 90-031 and In the Matter of '
Commonwealth Edison Company, Quad Cities Nuclear Power Station Docket Nos. 50-254 and 50-265, License Nos. >
DPR-29 and DPR-30 and EA 90-032 Referencess (a) J. Lieberman to Cordell Reed letter ,
dated May 1, 1990.
(b) S.R. Lefstein to J. Lieberman letter I dated April 13, 1990.
Mr. Davis This is in response to the reference (a) letter which states, in part, as follows:
' "As a separate matter, please provide to the. Regional Administrator Region III, your views concerning the adequacy of the company's controls for work hours in view of the information provided by l Mr. Dickherber on page 13 of his answer." -
Attachment A provides our discussion of work hour controls, as requested.
We have conducted a review of Mr. Dickherber's work hours. That review did not substantiate his stateseents concerning overtime. On June 1, l 1990, Mr. Dickherber did submit a clarification and retraction of certain '
parts of the statements contained in his April 13, 1990 response. Attachment i B provides a weekly summary of the hours worked by Mr. Dickherber from January ,
2, 1990 through the date (October 17, 1989) of the event that prompted these l consnun iques .
I l
L 9006110134 900604 ,
PDR ADOCK 05000?54
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+
.i Finally, we believe that our controls over work hours have been offective and will continue to ensure a high level of compliance with the i NRC's guidelines on overtime as well as provide assurances that our personnel !
are not working to the evtont that fatigue would impair their performance. [
If your staff has any questions or comunents regarding this gubmittal, l please refer them to Ms. Rita Stols (708) 515-7283. !
Sincerely yours.
P Dennis Galle A% &Yb '
90 Vice President j BWR Operations ;
i cc: J. Lieberman, Director, Office of Enforcement '
J. Zwolinski, Assistant Director, NRR L. 01shan, Project Manager, NRR W. Shafer, Branch Chief, RIII J. Hind, Section Chief, RIII Senior Resident Inspector, Quad Cities '
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l ATTACHMENT A C0f990NWEALTH EDISON CONTROLS OF HOURS WORKED l
I Conunonwealth Edison's controls over the number of hours worked by its employees in nuclear power plants are divided into two categories depending on how the individual's activities affect the safety of plant operation. ;
Personnel who are directly involved with the operation or maintenance of safety-related plant equipment are encompassed by a formal program for ll monitoring work hours in accordance with Generic Letters 82-12 and 83-14.
Work hours for other personnel whose activities do not directly or immediately impact the safe operation of the plant are monitored by more traditional .
management techniques.
Currently, Cosenonwealth Edison's control over work hours for plant personnel who perform safety-related functions is implemented through Nuclear ,
Operations Directive. 0A.13, revision 0 dated December 31, 1989. This ,;
directive became fully effective on April 30, 1990. It incorporates the guidance contained in Generic Letter 82-12 and 83-14 and Cosusonwealth Edison's conunitments in its NRC approved programs to control overtime hours.
The current Directive was developed following a coaprehensive review of practices at each of our Nuclear Stations.. Cosusonwealth Edison's adoption of the directive assures that overtime controls are applied uniformly to specific Station positions consistently throughout our Nuclear Stations. In addition to providing a consistent policy, the Directive expanded the scope of the coverage to include additional positions that were not included prior to formalizing our approach in Nuclear Operations Directive OA.13. Positions currently encompassed by this Directive includes the Operating crew, ,
Maintenance crews, Fuel Handling Foreman (during fuel movement), one Radiation Protection and one Chemistry Technician. The Directive requires that deviations be approved by the Station Manager or responsible supe" visor (for call-out situations) prior to deviating.from the guidelines. 1 The current Directive also includes an oversight procedure to ensure j compliance. That procedures requires that deviations from the Directive- ,
guidelines be reported to upper Station Management on a monthly basis and to senior Corporate Management on a semi-annual basis. Included in the reports are the number of personnel who exceeded the guideline. In addition, the report to senior Corporate management requires that actions to prevent recurrence be defined, if the guidelines were exceeded without proper approval.
l For personnel who are not encompassed by the guidance contained in the Generic Letters, management relies on the traditional methods of both personal awareness and supervisory observation to ensure that individuals are not fatigued by working excessive hours. When individuals believe they are becoming fatigued or are so observed by their supervisors, the work [
assignments-for those individuals are adjusted accordingly. For non-salaried employees, overtime sheets are required to be approved by Supervisors. This permits each Supervisor to review the hours worked by his/her subordinates l during a two-week pay period and to adjust subsequent work schedules, if 1
Attachment A (continued) appropriate. For salaried employees, during periods of high activity such as a Refueling Outage, individuals must complete special forms to receive compensation for extended hours. Because such compensation requires the approval of supervisory personnel, supervisors review extended hours worked and can adjust subsequent assignments accordingly. In addition, management monitors work group overtime hours on a quarterly basis. This enables management to identify work groups with substantial overtime and to use this information to plan future work activities. While this approach is less formal than required by the Directive, experience has shown that this approach is effective and appropriate for assuring that personnel do not work excessive hours as a matter of course.
As Mr. Dickherber's supplement has clarified, the ef fectiveness of Commonwealth Edison's controls of overtime hours is not contradicted by Mr.
Dickherber's record of work hours. At the time of the incident, the Fuel llandling Foreman was not encompassed by the formal program for monitoring work hours covered by the Generic Letters. Nevertheless, in our response dated March 26, 1990 Commonwealth Edison noted that the numerical limits in the overtime guidelines were exceeded in a few of cases by no more than two hours based on NRC allowances for turnover. This conclusion has now been corroborated by Mr. Dickherber's clarification of June 1,1990, in which he has clarified his previous statements regarding hours worked. That clarification essentially shows that from the beginning of 1989 until shortly before the Refueling Outage, Mr. Dickherber worked the normal hours for plant personnel, that shortly before the outage Mr. Dickherber took a vacation and j that during the outage Mr. Dickhetber worked the extended hours traditionally i associated with refueling activities. For clarity, a summary of Mr. j Dickb*rber's weekly hours are provided in Attachment B.
For these reasons, Commonwealth Edison believes that its programs for ,
controlling overtime hours comply with the Commission's guidelines where '
applicable and otherwise provide ef fective work controls for individuals in nuclear power plants.
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ME .
R. DICEIERBER 1989 M ME E0tRS 1989 '
Mon. thru Sun. PA Computer Training Other Facation/ Holiday -
Period Hours Hours Hours Total Hours P- -- tm .
01/02 - 01/08 35.5 35.5 8 Holiday 01/09 - 01/15 35.5 35.5 01/16 - 01/22 41.5 41.5 01/23 - 01/29 36.0 36.0 01/30 - 02/05 43.5 43.5 02/06 - 02/12 45.0 45.0 02/13 - 02/19 24.5 24.5 16 Holiday & 1 Vacation Day 02/20 - 02/26 36.0 36.0 8 Holiday .
02/27 - 03/05 54.0 1 55.0 Radiation Training 03/06 - 03/12 41.5 7 48.5 Rockford 03/13 - 03/19 43.0 43.0 03/20 - 03/26 35.0 35.0 8 Holiday 03/27 - 04/02 45.5 45.5 04/03 - 04/09 26.0 26.0 04/10 - 04/16 36.0 36.C 04/17 - 04/23 35.5 35.5 04/24 - 04/30 35.5 8 43.5 Conduct of Ops Training
.05/01 - 05/07 01.5 40 41.5 Instp Training 05/08 - 05/14 44.0 44.0 05/15 - 05/21 44.0 44.0 05/22 - 05/28 22.0 22.0 05/29 - 06/04 32.5 32.5 8 Holiday 06/05 - 06/11 29.5 29.5 8 Vacation 06/12 - 06/18 45.0 45.0 06/19 - 06/25 16.0 7 23.0 24 3 Vacation Days, Rockford 06/26 - 07/02 36.0 8 44.0 07/03 - 07/09 27.0 27.0 8 Holiday 07/10 - 07/16 57.0 57.0 07/17 - 07/23 10.0 40 50.0 Fuel Handling Training 07/24 - 07/30 26.0 40 66.0 Fuel Handling Training 07/31 - 08/06 27.0 40 67.0 Fuel Handling Training 08/07 - 08/13 65.0 65.0 08/14 - 08/20 37.0 7 44.0 Station Annual Retraining 08/21 - 08/27 40.5 3 43.5 Fitness for Duty Training 08/28 - 09/03 24.0 24.0 09/04 - 09/10 0.0 0.0 40 Holiday & 4 Vacation Days 09/11 - 09/17 79.0 79.0 09/18 - 09/24 61.0 61.0 09/25 - 10/01 64.0 7 71.0 Rockford 10/02 - 10/08 56.0 56.0 10/09 - 10/15 68.0 68.0 10/16 - 10/22 60.0 60.0
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a.w.3.=stmo ev.,,..uv. news owa nm 2379-1 FAX AND U.S. MAIL DELIVERY i James Lieberman, Esq.
Director, Office of Raforcement j OWPN 7H4 United States Nuclear Regulatory Commission Washington, DC 20555 ;
Ret In the Matter of R. L. Dickharber License No. SOP-2365-8 Docket No. 55-5043 EA 90-131 and In the Matter of Commonwealth Edison Company '
Quad Cities Nuclear Power Station Docket Nos. 50-254 and 50-256 i License Nos. DPR-29 and DPR-30 '
E1 90-032
Dear Mr. Lieberman:
1990, Submitted to you by FAX and thereafter by mail on June 1, is the Supplemental Answer of Robert L. Dickherber. We previously advised - Mr. Berson of Region III that this document would be submitted, and in response to my inqui:.7, he.adviced that no motion for leave to file this document was necess.'.ry.
Also enclosed is a Proof of Service with an attached' service Thank you for your attention. j Sincerely, i bdO h M-f-Stuart R. Lefstein i SRL/mlh ,
)
Encl. ! l
+ 4 KATz, McANDREWS, BALCH, LersTEIN & Fitwtorm, P.C.
i James Lieberman, Esq.
June 1, 1990 Page 2 Copies by FAX and U.S. Mail to:
Mr. Charles Bechoefer, Chalunan of Administrative Judges Assistant General Counsel for Esarings and Enforcement Regional Administrator, NRC Region III Sheldon L. Trubatch, Esq.
Michael Miller, Esq.
Copies by U.S. Mai.1 only tot _.
Secretary, U.S. Nuclear Regulatory Commission Senior Resident Inspector at Quad Cities Nuolaa.r Power Station !
6 4
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UNITED STATES-NUCLEAR REGULATORY COMMISSION IN THE MATTER OF: ): License ~No. SOP-2365-8
)- Docket No. 55-5403 R. L. DICKEERBER, ) EA 90-031
___)
IN THE MATTLA OF -- ) ' .
l- ) License Nos. DPR-29 & DPR-30 l' l COMMONWEALTE EDISON COMPANY )- Docket Ncs.-50-254 & 50-256 l .
QUAD CITIES NUCLEAR POWER -) EA 90-032 L STATION )-
1
.\
PROOF OF SERVICE ~
4
- I, Stuart R. Lefstein,'an attorney for Robert L. ;
.i Dickherber, having been sworn on oath, state that copies of' -i Supplemental Answer of Robert L. Dickberber were' served upon. ;
the Agencies and persons on the attached Service List by '
Un; .ad States Mail, postage L prepaid, on June 1,-:1990. i Additionally, copies of that Supplemental Answer were served' ;
l by Fax on June 1, 1990 to the first six-agencies or persons 1 named on the attached service list.
i l = k D j
Stuart R. Letstein% ,
Signed and sworn to before me, a Notary Public, this 'i i
ist day.of June, 1990.
1
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- m A W. p 1 ;
l Notary Public
']
Stuart R. Lefstein
- , KATE, McANDRENS, BALCH,~LEFSTEIN & FIEWEGER, P.C.-
?
j^o bn '5b; O l 200 Plaza Office Building MARILYN L. HACKER 0 ?!
Notmy Pubuc, Stm of lHinois l! -!
Roc I n L 61204-3250 compyq y~agn ,
Telephone: 309-788-5661
. i.
1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _. _ _ . wr_,... - ,_,.. , .-. 4,-. m,
SERVICE LIST l
Charles Bechhoefer, -
-Chairman of Administrative Judges l l
Aromic Safety.and Licensing Board Nuclear Regulatory Commission.
4350 E-W Eighway -
Bethesda,lu) 20852 Director !
Office'of Enforcomant i
U.S. Nuclear Regulatory Commission Washington, D.C. . 20555 i Assistant General Counsel Attn Eugene J. Boller, Esq. 't Hearings and Enforcement i U.S.-Nuclear Regulatory Commission; '
Washington, D.C. 20555-i Regional Administrator Attna Bruce Berson, Esq.
Regional Counsel.
U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 i
Sheldon L. Trubatch, Esq. '
Sidley & Austin Attorneys for Commonwealth Edison Company ,
1722 I(eye) Street, N.N.
Washington, D.C. 20006~ i Michael Miller, Esq. i Sidley & Austin H Attorneys for. Commonwealth Edison Company
- One First National Plaza Chicago, IL 60603
?
Secretary Attnt. Chief, Docketing and Service Station Nuclear Regulatory Commission Washington, D.C. 20555 '
k Senior Resident Inspector Quad Cities Nuclear Power Station 22715 - 206th Avenue North Cordova, IL 61242
_. ~ _ . . __. _
- . .: J I
UNITED: STATES NUCLEAR REGULATORY COMMISSION IN THE MATTER OF: ) License No. SOP _2365 8
) Docket-No. 55-5403 )
R. L. DICIEERBER -)- P2 90-031 .
______________ ) 1 IN THE MATTER.OF: )
) License Nos. DPR-29-& DPR-30 Docket Nos. 50_254 & '50-256 COMMONWEALTH EDISON: COMPANY:- ) I QUAD-CITIES. NUCLEAR POWER ). EA 90-032 -l STATION ) l 1
l SUPPLEMENTAL ANSWER OF ROBERT _L. DICF"RSER i
I, Robert ,L. : Dickherber, hereby submit this Supplemental: ,
Answer, under oath, , to the Answer that I previously filed 'on April 13, 1990. My reason for submitting this . answer .is 7 that further information has come to my attention which I believe' requires; a -
withdrawal of certain statements previously made and a correction j of misleading implications that may flow from those statements.
Specifically, in - Section II: C, appearing ' on . p. 13 _ of my Answer, I made certain statements regarding time worked preceding the incident. The statements made were based on my best y reccllection and memory without having reviewed any' time records,;
with one exception bereafter noted.
- . As a result of the Commission's directive 'to Commonwealth
(
L Edison to comment on the ' hours I' worked, that company developed hours information based upon its computer showing entry access and exit to and from the Cordova Station. Commonwealth has now made !
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this information available to me and my attorney.1 '
n After reviewing this information, I' find it necessary to
withdraw and disavow the statements in the first two paragraphs 'in-Section II C appearing on p.13, except the first sentence which ~
concludes that the incident "was probably occasioned by stress" and-l the middle' sentence of the second paragraph relating . to the. .l
. cleaning of the fuel pool. A study of the hours'information from the computer simply does not support my recollection of the average amounts of time I said -I was working prior to the . incident in <
question.2 It should be noted, however, that my est %
1 of work hours in- thou two paragraphs were offered n- s background-information, and not as a cause of my conduct, . che day of the l-incident. Unfortunately, because I did not regard my hours as a-L reason for my actions, verification of them did not loom as an 1
Commonwealth Edison and its counsel have - been most cooperative in ~ honoring reasonable . requests for. pertinent 1 documents. Undoubtedly, had time- records ; covering the periods '
mentioned in my Answer been requested Commonwealth would have supplied them. Indeed, prior to preparing my Answer and without any request, the company had provided documents relating to my overtime hours from October 9 through ' October 21,- 1989, and a computer report showing the times of my entrances and exits to and from the security area of the-Cordova Station covering the period of October 2 through October 19, 1989. (Ex. 2 attached)' .
2 The hours information developed from - the computer shows time spent at the Cordova Station within the protected area, but I not work hours as such. Attached as l'rhibit 1 is a summary of q information taken from the computer relating to the specific l statements on p. 13 which .I am now withdrawing. While I believe l my hours worked were greater than the hours I was shown to be in l' the protected area, since et times I worked outside the protected area - (again, see Ex. 1 ) , these additional hours are not sufficient to substantiate my initial statements appearing in my Answer.
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3 important consideration in preparing -my Answer. However, upon further review of the first paragraph on p.13, I can see how the proximity of the statements regarding my 1989 hours0.023 days <br />0.553 hours <br />0.00329 weeks <br />7.568145e-4 months <br /> to the sentence i
that "the incident. . .. was probably ' occasioned by stress" could convey an impression that the stress .' resulted from those hours.
I an therefore speci.fically disavowing . any - such impression' . that- .i might: have been inadvertently created.3 I apologize to the !
Commission _ and express my deepest regrets for having possi.bly created this impression and for relying on what is now shown to be.
7 a faulty memory with respect to my hours when they could and should-have been verified, at least to the extent' possible.5 i i
I continue to believe, as previously stated, . that " stress" "probably occasioned" the incident -in question es'sentially because of the reasons set forth in the. last paragraph commencing on p.13 t
of my Answer. To a minimal artent my ' hours within ' the protected l
area in the immediate days 5 and week before the ?i ncident' (which f were 72.5 instead of 81 , Ex.
2 attached) may' possibly have influenced my conduct. '
My misstatement that I worked 81 hours9.375e-4 days <br />0.0225 hours <br />1.339286e-4 weeks <br />3.08205e-5 months <br /> in the week immediately .
before the incident i.nstead of 72.5, which is the number shown on I 3
Note uti statement in the last paragraph on p. 12 of my Answer relating to a dropped fuel bundle occurring in September 1985 which was handled according to proper procedures. Obviously, neither stress nor prior hours worked affected my performance on that occasion. 1 4
See notes 1 & 2, suora, j
5 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> on october 15 and 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on October 16.
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- 4 the computer, results from an i.ncorrect reading and impression of b
a . station management document' (Ex. 2)- first seen by me shortly '
af ter the incident. It was my impression that the 81 hours9.375e-4 days <br />0.0225 hours <br />1.339286e-4 weeks <br />3.08205e-5 months <br /> figure
- shown on the document represented the number of hours 'that'. I had '
worked during the week preceding the.1.ncident. Since filing my Answer on April 13, 1990, I have determined that 'the 81' . hours figure, which appears next to arrows --drawn between days, is .the total hours I was in the protected area for 8 days prior to the c incident instead of 7.
My attorney and-I had a copy of Exhibit 2 available prior to '
preparing my Answer. Unfortunately, we failed- to critically.
examine it and instead simply relied on my mistakentimpression that it represented the hours for the week preceding the incident. My' attorney. and I both apologize for having not ' detect'ed . ? this L
incorrect impression when we had an opportunity to do so. !
In attempting to assess the reasons for my inaccurate memory i and recollection, .I assume -that I was influenced by hours - worked -
during the month of September and that with respect to that month and earlier months I focused on the days where I worked long hours, l and that those days- then became exaggerated in my mir.d.as the norm.
For example, on September 13 I was in the protected area for 14 ,
hours and in the 7-day period: from Saturday, September 16 through
-Friday, September 22, the computer shows that I was in. the.
protected area for 82.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, with a 13.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> day on Saturday, a 13 hour1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> day on Sunday, a 13 hour1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> day on Thursday, a 12.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> day on Friday, and al.1 days in that period at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
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In the days -immediately-preceding the day of- the incident the I
computer shows I was in- the protected area for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> on Sunday, 7 October 15, and 13 honrs on Monday, October -16. My inaccurate perception that I . had worked 81 hours9.375e-4 days <br />0.0225 hours <br />1.339286e-4 weeks <br />3.08205e-5 months <br /> in . the week; preceding the - !
incident probably also contributed to my incorrect statements-about L average hours.-
Similarly, in earlier months I had a few days'wliich were quite
- 9
-long. On August 7, 8, and 9, the computer shows my- presence at the ' '
station for days of 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />,11 hours,: and 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />si respectively.
My memory failed me in that I did not recall that for each of these-long days I had ' numerous shoitter days which reduced my overall i average hours. ( Again, see Ebc.~ 1 ) .
One final correction'should-'also be noted. In Section!I'B, l
- p. 3, I commented on a reduction'in radiation exposure. This was-
' based on my memory. Commonwealth : has advised me of certain inaccuracies in these comments. The exposure drop between.1976 and 1977 was only 484, not 624, and from 1974 through 1977 the exposure j rate had not exceeded 4 Rem, as I believed and stated.
Additionally, while not discussed in - my Answer, exposure rates - l
,1 returned to high levels for several years after 1977. This^was because of new work that had not been previously requirod.
Radiation exposure at high levels continued because of repair work 1 dor:o to tools and fuel handling equipment, ~especially the refuel' bridge, and because of other: work assignments. From 1985 through the present radiation expos = a rates again dropped dramatically when conhminated materials were discarded. 4 l
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~I Once again, my incorrect statements should have been subjected to critical vari.fication before filing my Answer. At this time all l I can do is set forth the actual facts as they have been brought ,
to my attention and offer my sincere apologies to the Commission for these inaccura,,les. I i
. Respectfully submitted,- !
Robert L.-Dickharber i
STATE OF ILLINOIS ) i
) SS.
COUNTY OF ROCK ISLAND )
Robert L. Dickherber, bei.ug.first duly. sworn on oath, states that he has read the foregoing - statement- and that all factual !
j statements made'in knowledge-and belief.. the same are true and correct to the best of his YsRoberthr L. Dickherber 4 ,
Signed and sworn to before me, a Notary Public, this 1st day of Junn, 1990. _
= :: ::n.s. m : :::
R HA Notsry Pubtle, S:sts of IIDnots
( __ 1"
- Notary Wublic
- ; MyC m.n Egree Jan.10.1983 ' ; '
L ::::_ m .oa..,...s.~.:--^ -
Stuart R. Lefstein KATE, McANDREWS,-
BALCH, LEFSTEIN & FIENEGER, P.C. ,
Attorneys for Robert L. Dickberber 1705 Second Avenue, Suite'200 P.O. Box 3250 Rock Island, IL 61204-3250 Phone: 309/788-5661 l
7,.,
l UNITED STATES.
NUCLEAR REGULATORY COMMISSION IN THE MATTER OF: ) License No. SOP-2365-8 ;
R. L.-DICMERBER
). -Docket No. 55-5403 EA 90-031; j
) }
______.________._) !
IN TEE MATTER OF )- 1
-) License Nos. DPR-29 & DPR-30: 1 COMMONWEALTH EDISON COMPANY ) Docket Nos. 50-254 & 50-256
-QUAD-CITIES: NUCLEAR POWER ) EA 90-032 STATION .)
_.1 EXEIBIT 1 TO SUPPLEMENTAL ANSWER OF _ ROBERT L. - DICFWD31L'R The following information, ' developed from' Commonwealth Edison's security computer, is set forth .to correct- -the misstatements appearing-in.my~ Answer:
- )
The fuel outage occurred on or about September 10,-1989. I had been on vacation from September 1 through September 10. From September 11 through September 23 I was withh the computerJ access 1'
area every day, including two Saturdays and' .one Sundayj at an average of 10.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per : day with my longest day at 14. E hours.-
From September 24 through September 20 I had one Sunday off and my !
I average hours within the protected area were 10,67 per day with my -
i longest day at 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. From October 1 through October 17, which was the day of the incident, I had two Sundays off. My average hours in the protected area were 9.7 honrs with my longest day at q 4
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.'
1 Also, and neces .;.rily, the computer shows that generally'my starting times were ne,mewhat later than initially stated and my
< exit' times were generally earlier than I had recalled and stated j
r in the Answer. Sometimes there is approximately a 5 minute wait
, 'to gain access.
.?
EMBIT 1 (CONTINUED) 1 j In the eight months prior to the fuel outage, the security -
computer shows my presence on the following weekends only: Sunday, February 19; Saturday, March 4; Saturday, March 11; Saturday, July.
15; Sunday, July 30; Saturday,. August 5; Sunday, August $; and a
Saturday, August 12. 'My presence is not-shown on any other weekend dates by the security computer during.those months, e The average daily hours of'my presence shown by the computer for the eight months prior to the. outage was approximately eight.
However, my average hours actually worked during those -months is ;
necessarily higher, although undoubtedly less than what I stated.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> average was arrived at by taking an avere;,. hours' per -i day for each of 32 weeks of 1989 through the' end of-Jugust,' except the week of May 1,2 as shown by the ' security compui er. . Certain weeks entering into this average contained- ' average . days substantially less than eight hours, suchlas 2, 4.3, 3.8, and 5.5..
These numbers contributed to bringing the average down to 8, 'as a
reported, t
However, it is high.ly probable that for most week days where l
the security computer showed me with.an: average of J.ess than eight '
I 1
I was on j ob assignments elsewhere performing at least _8 hours of I work for the entire day. - As an example, .during the ' summer of 1989,-. b o
I spent approximately.3 weeks in license requalification trasning.
outside of the protected area. These hours do not show -on the i-computer but are factored into the 8' hour daily average based only 2
I was in a management training prog am during that week outside of the protected area.
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EXEIBIT 1 (CONTINUED) },
on the computer.. Additionally, when I was taking this training I-would usually spend several hours at home in the evening study'ing, which, of course, is not contained in the average.
Besides taking training, other work was parformed outside.of the protected area. Dur1ng the fuel outage I wrote approximate".y.
five or- six different fuel handling procedures at heme.
- Commonwealth had never asked or suggested that I:do this _ woek at home but I did so-in _ order to get the job done.
Also, I have escorted on several occasions Commonwealth '
personnel to medical offices in Rockford for alcohol and drug.
t stating. A trip to Rockford from the Cordova- Station and back with waits at the medical offices averages approximately six hours, and I' probably was involved in such escorts during the eight month period prior to the incident approximately five times. I also had meetings with contractors witside of the station ,which are not shown on the computer records. I possibly. had such meetings approximately three or four times during the periods involved with a range of time from two to four hours.
Since there is no documentation for the precise number of -
hours worked outside the protected area in the eight months _ prior to the outage,- and based on the above information, it is reasonable -
to conclude that I was working an average of more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per day but not 10 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> par day as_ stated, nor was I regularly working 6-day weeks.
Finally, I was substantially mistaken regarding my recc11ection of holidays worked. In addition to Memorial Day and a
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EmBIT 1 (CONTIh m )_
Independence Day mentioned in my Answer, the computer shows me off on Ntv yea.r's Day, Lhcoln's Birthday, President's Day, Good Friday
-andLaborDay,whichfellduringmyvacaNon. A holiday for which I am shown present is Columbus Day.
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G-4_R S ^ L' 9 I Y "
EPeh .C=u ATES'10/20/0? PACE '
L i ,. 12116310 -
Eb-
.....i FOR T'ERSONS EXITING liETWEEN - 10/01/89; 00!00 AND 10/20/89 12812 1
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- CeRP C AL P"a!. Pr" ST4TISM ?TeTIa9 EF"^"fE - _
NO, Ev2T TI"r C ' '"" - "
NANE . NUMBER . DEPT DATE TIME-DATE TIME SPENT LATIVE .
01856 DICK 1tERDER ROBER 128
, A f B Et 1 h Y PL'EJrD urD D M D t* D AOn -
FUEL rhag.g o l 10/02/89 06820.10/02/89 15127 9106333 90 4.
4AInIIDO A A 4 Set 4 A / A'I Inn i1#BA e9AA94A 4 L" . .. . A I "A % ' ,
- f. hIB5I DICKlfdRhkR.RbbkR I2b FbEl Ib/h4/09 bII27 Ib/h4/09 I6545 10113555 :593655U2 01?56 SICErR*" ROSER 12e rLaEL' is/05/9= ei!?2 10/e5/e? 15!5!
a!!?!!?
01856 DICKHERDER ROBER 128 ??!2'!'!? -
FUEL. 10/06/99 06131 10/06/09 15333 9301140 47!26107-l As95g gycengtppgo onggp igg .rygt 39f97 ego ng 9 A. - i9f97ean 35 gig gg73747 5535795 p j .
- l. 01856 DICKlfERBER RDBER 128 FUEL? 10/69/99 06133 10/09/89 15!05:
01a56 P!Pruros,go oggge ggo c ygi_ yaf.9foo ag9p gnf,9fg. g7;g7 8132845 3935tgan 6413013$ h !
01856 DICKHERDER ROBER 7.cggge75 -
n 128 FUEL 10/11/89'06136 10/11/89 16215 9339302 J L, c_ een53 nyruurns.Ep onaro- igg rurs 85300137 infigfgo agtyg infigfoo syrig sn t mon g r o5eantna l 01856 DICKilERBER ROBER 129 FUEL 10/13/99.06I36 10/13/89 15135 8159812 104 t(39116 inningt44- (
nin51 purutarongo onngo 7,9 ent s_ p i-sn/na/no ngsto 19fea/go notag- 3tg7t3a 1 01956 DICKHERBER ROBER 128 FUEL 10/14/89 2213'-10/15/89'14850' p 46!13148 124816137i k,
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-nsn53 nicruronro onneo ! in curi_ i tafezfoo azegn gneigfgo 4oegn s o n ico e g g s r s t i 5 f g, f 01856 DICKilERDER ROBER, 128
- j g asg53 pyrvurongs> nnns o FUEL 10/17/B9.068I/f 10/17/89 14856 8139334 145 t 55 t 2744-- @
i
_ inina/no azes'y ineinfgo 13eng oeacgtan 15=y a n a 77 I 01056 DICKHERBER ROBER 128. FUEL I
k 10/19/89 04 32 10/19/99 15117 8845!03 164833810tk,;*
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17 RECORD (S) SELECTED - *
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