|
---|
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] |
Text
- - . - - . . . . - - - - - - - - - - - -
J
~ ) Commonwealth 1400 Opus Plac) Edison Downers Grovn. Ilkncis 60515
]
l l
January 16,1995 ,
h U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk l
Subject:
Quad Cities Nuclear Station Units 1 and 2, Core Shroud Modification Design Documents and Unit 2 Core Shroud '
Inspection Plan i NRC Docket Nos. 50-254 and 50-265 !
Reference:
G. Benes (Comed) to W. Russell letter dated August 23,1994,. ;
i In the referenced letter, Commonwealth Edison (Comed) provided a response to .
Generic Letter 94-03, "Intergranular Stress Corrosion Cracking of the Core l Shrouds in Boiling Water Reactors." In that letter, Comed committed to provide I the inspection plan for the Quad Cities Unit 2 core shrouds (GL 94-03 Item 2.(a))
and the plans for the repair of the Quad Cities Unit I and Unit 2 core shroud (GL 94-03 Item 2.(b)). This letter provides the Design Documents for the repair of the Quad Cities Station Unit I and Unit 2 core shrouds as Attachment A (with Enclosures 1 through 9), and the Quad Cities Station Unit 2 Core Shroud i Inspection Plan as Attachment B.
The Unit 1 and Unit 2 Core Shroud repair was developed in accordance with ASME Section XI repair and replacement program requirements. This modification does not remove the existing flaws, nor replace the flawed components, but rather structurally replaces the core shroud horir ,tal circumferential welds H1 through H7, and accounts for cracking W the H8 weld.
The design has been developed considering through-wall 360 degree circumferential cracks at the H1 through H7 welds. The repair will be performed j as an alternative tc the ASME Section XI Code as permitted by 10 CFR l 50.55a(a)(3). In accordance with requirements of the above reference, Comed is j submitting this alternative code repair for your review and approval, kinla s quad 11695.wpf 1 9501310013 950116 PDR ADOCK 05000254 h, y//1 -
l Chye:&Poe ; ipW, j
1 3
U.S. NRC January 16,1995 Upon completion of the Unit 2 core shroud repair installation package, Comed will provide the 10CFR50.59 safety evaluation as a supplement to the design packag,e. Comed is presently planning to install the core shroud repair hardware into Quad Cities Unit 2 on April 26,1995 during the Q2R13 refueling outage. The Quad Cities Unit 2 inspection plan (Attachment B) has been integrated with the design of the modification. The Quad Cities Unit 1 installation will be performed during the Q1R14 refuel outage.
This submittal contains items which are proprietary in nature to the General Electric Nuclear Company. These proprietary items are contained in Enclosures 5 and 8 of Attachment A. Comed has specifically marked the portions of the submittal that are considered proprietary and requests that ell material within Enclosures 5 and 8 which is specifically marked as proprietary be withheld from public disclosure. To that end, Comed has provided non-proprietary versions of Enclosures 5 and 8 as Attachment D. Comed has included, as Attachment C, an aflidavit per the requirements of 10CFR 2.790(b) explaining the reasons and circumstances for withholding the applicable information from public disclosure.
To the best of my knowledge and belief, the analyses and evaluations contained in l
these documents are true and correct. In some respects these documents are not based on my personal knowledge, but on information furnished by other Commonwealth Edison employees, contractor employees, and/or consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.
- If there are any questions concerning this matter, or need for further clarification, l please contact this office. .,,....,.,.,,..,,__,,,,,..,...
! OFFICIAL SEAL l:
Sincerely,
/
f ll MARY JO YACK l,> NOTARY PUBuc SuTE OF GNotSl
- 'l YY coy,ylSS0N}{Rf S] }/2p Nuclear Licensing Administrator %,,y 4 gj gg
/- /, /)
Attachment A Quad Cities Station Unit 1 and Unit 2 Core Shroud Repair Design Documents (includes Enclosures 1 through 9) ;
Attachment B Quad Cities Station Unit 2 Core Shroud Inspection Plan Attachment C Quad Cities Station Unit 1 and Unit 2 Selected Core Shroud ,
Repair Design Documents - General Electric Company Affidavit Attachment D Quad Cities Station Unit 1 and Unit 2 Selected Core Shroud Repair Design Documents; Non-Proprietary Version -
Enclosures 5 and 8 i cc: J. Martin, Regional Administrator - RIII R. Pulsifer, Project Manager - NRR C. Miller, Senior Resident Inspector - Quad Cities Office of Nuclear Facility Safety - IDNS k:nla: quad:11695 wpf:2
t ATTACIIMENT C Quad Cities Station Unit 1 and Unit 2 Selected Core Shroud Repair Design Documents General Electric Company Affadavit l
l l
l l
I l J
l l
i General Electric Company l
1 1
AFFIDAVIT I, George B. Stramback, being duly sworn, depose and state as follows:
(1) I am Project Manager, Licensing Services, General Electric Company ("GE") and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in the GE proprietary report GENE-771-71-1094, Revision 1, " Quad Cities Units 1 & 2 - ShroudRepair Seismic Analysis", (GE Proprietary), January 5,1995 and drawings 107E5487, Rev.1,
" Reactor Modification / Installation Drawing", including a color piutare of the 107E5487 modification and those drawings listed in the Afmehmen'. These documents, taken as a whole, constitutes a proprietary compilation ofin'brmation, some ofit also independently proprietary, prepared by the General Electric Company.
The indept ndently proprietary elements that are drawings or a picture are marked as proprietary :.nformation and the independently proprietary elements that are in reports are delineat d by hars marked in the margin adjacent to the specific material.
(3) In making this application for withholding of proprietary information of which it is the owner, GE relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec.1905, and NRC regulations 10 CFR 9.17(a)(4), 2.790(a)(4), and 2.790(d)(1) for " trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which !
exemption from disclosure is here sought is all " confidential commercial information",
l and some portions also qualify under the narrower definition of " trade secret", within j the meanings assigued to those terms for purposes of FOIA Exemption 4 in, i respectively, Critical Mass Enerav Project v. Nuclear Reculatory Commission.
975F2d871 (DC Cir.1992), and Eublic Citign Health Research Group v. FDA, 704F2dl280 (DC Cir.1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting l data and analyses, where prevention ofits use by General Electric's competitors afQCmod. doc Aflidavit Page 1
without license from General Electric constitutes a competitive economic advantage over other companies; i
i
- b. Information which, if used by a competitor, would reduce his expenditure of 1 resources or improve his competitive position in the design,- manufacture, i shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information which reveals cost or price information, production capacities, l budget levels, or commercial strategies of General Electric, its customers, or its l suppliers; I
- d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential conunercial l value to General Electric; !
- e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
Both the compilation as a whole and the marked independently proprietary elements incorporated in that compilation are considered proprietary for the reason described i in items (4)a., (4)b. and 4(e), above.
l (5) The information sought to be withheld is being submitted to NRC in confidence. l l That information (both the entire body ofinformation in the form compiled in these drcwings, tnd the mrked individua l p-oprietary elements) is of a sort customarily l held in confidence by GE, and has, to the best of my knowledge, consistently been l held in confidence by GE, has not been publicly disclosed, and is not available in I public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or !
proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent i steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6)
, and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the l originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access to such ,
l documents within GE is limited on a "need to know" basis.
l (7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination !
of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, afQCmod doc Affidavit Page 2 l
and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) and the Attachment, above, is classified as proprietary because it constitutes a confidential compilation ofinformation, including a report and detailed design drawing results and a picture of a hardware design modi 6 cation (stabilizers for the shroud horizontal welds) intended to be installed in a reactor to resolve the reactor pressure vessel core shroud weld cracking concern.
The development and approval of this design modification utilized systems, components, and models and computer codes that were developed at a significant cost to GE, on the order of several hundred thousand dollars.
The detailed results of the analytical models, methods, and processes, including computer codes, and conclusions from these applications, represent, as a whole, an integrated process or approach which GE has developed, and applied to this design modification. The development cf the supporting processes was at a significant i additional cost to GE, in excess of a million dollars, over and above the large cost of i developing the underlying individual proprietary report and drawings information.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GE's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GE's comprehensive BWR ,
technology base, and its commercial value extends beyond the original development ,
cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and indudes development of the expertise to determine and apply the appropriate evaluation process. In addition, the achaalcgy b:.n ;
includes the value derived from providing analyses done with NRC-approved methods.
GE's competitive advantage will be lost ifits competitors are able to use the results of the GE experience to avoid fruitless avenues, or to normalize or verify their own process, or to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
While some of the underlying , analyses, and come of the gross structure of the i process, may at various times have been publicly revealed, enough of both the analyses and the detailed structural framework of the process have been held in ,
confidence that this information, in this compiled form, continues to have great competitive value to GE. This value would be lost if the information as a whole, in i the context and level of detail provided in the subject GE drawings, were to be disclosed to the public. Making such information available to competitors without their having been required to undertalce a similar expenditure would unfairly provide competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing its analytical process.
afQCmod. doc Affidasit Page 3
STATE OF CALIFORNIA )
) ss:
COUNTY OF SANTA CLARA )
George B. Stramback, being duly sworn, deposes and says:
That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.
Executed at San Jose, California, this /2 day of m 1995.
/
L&
'" - Ge6rg/BT Stramback '
General Electric Company Subscribed and sworn before me this ,. , day ofhW4.{3(_ _.1995.
i l
ukceW l 6ML Notary Public, State of C$llfdrnia
. . . - PAULA F. HUSSEY q m COM!A #1046120
. Notary PWie - Cohfornio 3
{
{ - [f - $ANTA CLARA COUNTY y 1
j Mr Comm. Experos DEC 1,1098 )
7 m l
afQCmod. doc Affidavit Page 4 I
L i
Attachm:nt i
Drawing No. Revision Identification A 112D5256 1 BRACKET YOKE ASSY B 112D5264 1 LOCK, BOLT C 112D6506 1 LOWER STABILIZER ASSY D 112D6508 1 TOGGLE BOLT ASSY E 112D6509 1 TlE ROD ASSY F 112D6510 1 STABILIZER SUPPORT ASSY G 112D6511 1 UPPER STABILIZER ASSY H 112D6512 1 LATCH I 112D6513 1 SCREW, MID SUPPORT J 112D6514 1 RING, MID SUPPORT K 112D6515 1 WASHER, JACK BOLT L 112D6516 1 SLEEVE, JACK BOLT M 112D6518 1 RETAINER N 112D6519 1 NUT, TOP SUPPORT O 112D6520 1 BOLT, TOP SUPPORT P 112D6521 1 PIN O 112D6522 1 NUT, TIE ROD R 112D6523 1 PIN, CLEVIS S 112DS525 1 8:
.XTENSION, LOWER SPRING T' 112D6527 1 SCREW, YOKE U 112D6528 1 BRACKET, UPPER SPR'NG V 112D6529 1 CLIP, RETAINER W 112D6530 1 BOLT, JACK X 112D6531 1 NUT, TOGGLE BOLT Y 112D6532 1 WASHER, TOGGLE BOLT Z 112D6533 1 PIN, TOGGLE BOLT AA 112D6534 1 TOGGLE BB 112D6535 1 SUPPORT, LOWER CC 112D6536 1 BOLT, TOGGLE DD 112D6537 1 CONTACT, UPPER EE 112D6539 1 CONTACT, LOWER FF 112D6540 1 SUPPORT GG 112D6541 1 UPPER SUPPORT, LONG aIQCmod doc Affidavit Page 5
Att: chm:ct (c:nt'd) >
HH 112D6542 1 SPRING, UPPER 11 112D6543 1 SPRING, LOWER JJ 112D6544 1 ROD, TIE KK 112D6545 1 TIE ROD SPRING ASSY LL 112D6594 1 SPRING, RETAINER MM 112D6595 1 BRACKET YOKE NN 112D6596 1 UPPER SUPPORT SHORT 00 112D6597 1 NUT, LOCK PP 112D6598 1 BOLT, TENSION ARM QQ 112D6599 1 ARM, TORSION RR 112D6607 1 MID SUPPORT ASSY SS 112D6612 1 SUPPORT, MID SHROUD l
l l
t l
l l
afQCmod. doc Affidavit Page 6 l i
ATTACHMENT A Quad Cities Station Unit I and Unit 2 Core Shroud Repair Design Documents l f
I Enclosures I through 9 '
i i
1 i i I
f
i I
l ATTACHMENT A I
The Quad Cities Unit I and Unit 2 core shmud repair Design Documents are pmvided in the following l
Enclosures:
l Enclosure 1. GENE Design Specification,25A5668 Revision 2, "Shmud Stabilizer Hardware - r Quad Cities Units 1 & 2" Enclosure 2. GENE Code Design Specification,25A5669, Revision 2, " Reactor Pressure Vessel - ;
Quad Cities Units 1 & 2" !
Enclosum 3. GENE Fabrication Specification,25A5670, Revision 2. " Fabrication of Shroud Stabilizer" l Enclosure 4. GENE Installation Specification,25A5615, Revision 0, "Shmud Stabilizer Installation- Quad Cities Units 1 & 2" t Enclosure 5. GENE 771-7l-1094, Revision 1, " Quad Cities Units 1 & 2 - Shroud Repair Seismic Analysis" Enclosure 6. GENE 771-68-1094, Revision 2, "Shmud and Shmud Repair Hardware Stress Analysis -
Shmud Repair for Hi Thmugh H7 Welds for Commonwealth Edison Quad Cities Nuclear ;
Power Station Units 1 and 2" i Enclosure 7. GENE Stress Repon,25A5672. Revision 1. " Pressure Vessel - Quad Cities I and II" l Enclosure 8. One color picture of a computer model of the core shmud sepair installed at Quad Cities.
Enclosure 9. Construction dmwings of the core shmud hardware, as listed below.
Construction Drawings ;
! l. Reactor Modification / Installation Drawing 107E5487 Sheet I of 3, Revision 1 ,
Rextor Assembly ;
- 2. Reactor Modification / Installation Drawing 107E5487 Sheet 2 of 3 Revision 1 Reactor Assembly
- 3. Rextor Modification / Installation Drawing 107E5487 Sheet 3 of 3 Revision 1 ,
Reactor Assembly ,
- 4. Assembly Dmwing 112D6506, Revision 1, Sheet I of 1, Lower Stabilizer Assembly [
l 5. Assembly Dawing i12D6508, Revision 1, Sheet 1 of 1, Toggle Bolt Assembly !
- 6. Assembly Dmwing i12D6509, Revision 1, Sheet I of 1, Tie Rod Assembly l 7. Assembly Dmwing i12D6510 Revision 1, Sheet I of 1, Stabilizer Support Assembly i l 8. Assembly Dmwing 112D6511, Revision 1, Sheet 1 of 1, Upper Support Assembly )
- 9. Detail Drawing Il2D6512, Revision 1 Sheet 1 of 1 Latch
- 10. Detail Dmwing 112D6513, Revision 1, Sheet 1 of 1, Screw, Mid Suppon
- 11. Detail Drawing il2D6514, Revision 1, Sheet I of 1 Ring, Mid Suppon i
- 12. Detail Dmwing Il2D6515, Revision 1, Sheet 1 of 1 Washer, Jack Bolt
- 13. Detail Dmwing Il2D6516, Revision 1, Sheet 1 of 1, Sleeve, Jack Bolt
- 14. Detail Drawing Il2D6518, Revision 1 Sheet 1 of 1, Retainer
- 15. Detail Dmwing Il2D6519, Revision 1, Sheet 1 of 1, Nut, Top Suppon
- 16. Detail Drawing 112D6520, Revision 1, Sheet I of 1, Bolt, Top Suppon
- 17. Detail Drawing ll2D6521, Revision 1, Sheet 1 of 1, Pin
- 18. Detail Drawing 112D6522, Revision 1, Sheet 1 of 1, Nut, Tie Rod
- 19. Detail Dmwing 112D6523 Revision 1, Sheet 1 of 1 Pin, Clevis
- 20. Detail Drawing Il2D6525. Revision 1, Sheet 1 of 1, Extension, Lower Spring I
k:nla: quad:11695.wpf:3 l
l
. ~. - .- - -~ - .- - . - - . - . - . - - - - -- . . - . - ..
ATTACHMENT A (continued)
Quad Cities Units 1 and 2 Cose Shroud Design Modification Document List:
Construction Drawines (continued)
- 21. Detail Drawing i12D6527, Revision 1, Sheet 1 of 1 Screw, Yoke
- 22. Detail Dmwing 112D6528, Revision 1, Sheet 1 of 1, Bmcket, Upper Spring
- 23. Detail Drawing Il2D6529, Revision 1, Sheet 1 of 1, Clip, Retainer
- 24. Detail Dmwing 112D6530, Revision I, Sheet 1 of 1, Bolt, Jack
- 25. Detail Drawing 112D6531, Revision 1, Sheet 1 of 1, Nut, Toggle Bolt
- 26. Detail Dmwing 112D6532, Revision 1, Sheet 1 of 1 Washer, Toggle Bolt
- 27. Detail Drawing 112D6533, Revision 1, Sheet I of 1, Pin, Toggle Bolt J 1
- 28. Demil Drawing 112D6534, Revision 1, Sheet 1 of 1, Toggle
- 29. Detail Drawing i12D6535, Revision 1, Sheet 1 of 1, Suppon, Lower
- 30. DetailDrawing 112D6536, Revision 1, Sheet 1 of 1, Bolt, Toggle ,
- 31. Detail Drawing 112D6537, Revision 1 Sheet 1 of 1, Contxt, Upper
- 32. Detail Dmwing Il2D6539, Revision 1, Sheet 1 of 1, Contact, Lower ];
- 33. Detail Dmwing 112D6540, Revision 1, Sheet 1 of 1, Suppon
- 34. Detail Drawing 112D6541, Revision 1, Sheet I of 1, Upper Suppon, Long
- 35. Detail Dmwing 112D6542, Revision I, Sheet I of 1, Spring, Upper l
- 36. Detail Drawing Il2D6543, Revision 1, Sheet 1 of 1, Spring, Lower i
- 37. Detail Drawing ll2D6544, Revision 1, Sheet I of 1, Rod, Tie
- 38. Assembly Drawing Il2D6545, Revision 1 Sheet 1 of 1, Tie Rod-Spring Assembly ,
l 39. DetailDrawing Il2D6594, Revision 1, Sheet i of 1, Spring, Retainer i l
- 40. Detail Drawing i12D6595, Revision 1, Sheet 1 of 1, Bracket Yoke l
- 41. Detail Dmwing 112D6596, Revision 1, Sheet 1 of 1, Upper Suppon Shon I l
- 42. Detail Drawing Il2D6597 Revision 1, Sheet 1 of 1, Nut, Lock
- 43. Detail Dmwing i12D6598, Revision 1, Sheet 1 of 1, Bolt, Torsion Ann l 44. Detail Drawing 112D6599, Revision 1, Sheet I of 2, Arm, Torsion i 45. Detail Dmwing i12D6599, Revision 1, Sheet 2 of 2, Ann, Torsion l 46. Assembly Dmwing 112D6607, Revision 1, . Sheet 1 of 1, Mid Suppon Assembly 112D6612 Revision 1, Sheet 1 of 1
- 47. Detail Drawing Suppon, Mid-Shroud
- 48. Assembly Drawing 112D5256, Revision 1 Sheet I of 1, Bracket Yoke Assembly
- 49. Detail Drawing Il2D5264, Revision 1, Sheet I of 1, Lock, Bolt 1
)
I l
k:nlazquad:11695.wpf:4 l
1 l
Enclosure 1 GENE Design Specification,25A5668, Revision 2
" Quad Cities Units 1 & 2 - Shmud Stabilizerliardware" )
l I
l l l l
l 4
l i
l k:nla: quad:11695.wpf:S