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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
, / #]1^Commonwe:lth Edison j Ouad Citf 'juclear Power Station
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Director of Of fice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Refe rence: Quad-Cities Nuclear Power Station Docket No. 50-265, DPR-30, Unit 2 Abnormal Occurrence Report, A0 50-265/75-8 The attached table represents an update of missiig and loose parts iden-tified during the Unit 2 refueling outage in the spring of 1975 Sending this supplemental update has been inadvertently averlooked until this date.
The information contained in the Table represents a compilation of items identified by both the Station and General Electric Company. The items were identified or observed during the various phases of work conducted in the reactor during the outage. The time span of the work covered per-lods from February 1975 through April 1975 Some of the i tems were ob-served or identified during initial work in February, but not retrieved until March when the outage schedule provided time for retrieval. Other items were retrieved as they were observed or as time permitted. At the conclusion of the outage, four items identified as missing were assumed to remain in the vessel.
Prior to resuming power operation of Unit 2 in April 1975, General Electric Company at the request of the station provided an analysis of those parts remaining in the vessel; station review of this analysis is documented by Quad-Ci ties Station On-Site Review Number 75-21, dated April 21, 1975 A copy of the General Electric analysis is provided herein.
.Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCL AR POWER STATION ff f ! f /M?
N. J. Kallvianakis '
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- Station Superintendent COPY SENT REGION [ 2 - _ ,2 NJK/ REQ /lk Attachments: 1. Table-Missing and Loose Parts b 33
- 2. GE letter, Apr!I 22, 1975, Loose Parts Analysis cc: Region li t , Regulatory Operations J. S. Abel 8306280134 750729 PDR 8 ADOCK 05000265 PDR ,
MISSING AND LOOSE PARTS - UNIT 2 - CYCLE I REFUELING -
I ORI GINAL DATE OF DATE OF PARTS STATUS DISCOVERY RETRIEVAL DISPOSITION :
- 1. Lighting Support Bracket From Refuel Bridge Missing 1/9/75 1/17/75 Hung in Unit 1 Fuel Pool '.
- 2. Neutron Dosimeter Tube Missing 2/19/75 --
Remaining in Vessel
- 3. Neutron Dosimeter Missing 2/19/75 --
Remaining in Vessel -
- 4. JP 18 Adjusting Stop Screw Missing 2/17/75 --
Remaining in Vessel
- 5. JP 7 1/2" Cap Screw Missing 2/17/75 3/75 Radwaste
- 6. JP 7 Retainer Clip Missing 2/17/75 3/75 Radwaste
- 7. JP 8 1/2" Cap Screw Missing 2/17/75 3/75 Radwaste
- 8. JP 8 Retainer Clip Missing 2/17/75 3/75 Radwaste
- 9. 7 Pieces of Wire Loose 2/17/75 3/75 Radwaste
- 10. Piece of Angle Iron Loose 2/17/75 3/75 Radwaste
- 11. Open End Wrench Loose 2/17/75 3/75 Radwaste i
- 12. 3 Pieces of Tape Loose 2/15/75 2/17/75 Radwaste
- 13. I Piece of Wire Loose 2/15/75 2/17/75 Ra dwas te
- 14. Rag Loose 2/28/75 3/75 Radwaste
- 15. Grinding Burr Loose 2/75 --
Remaining in Vessel 16, 3 Pieces of Tape Loose 2/75 3/75 Radwas te
- 17. Small Piece of Lead ~ Loose 2/75 3/75 Radwaste
- 18. Piece of Nylon Rope Loose 2/75 3/75 Radwaste
- 19. Plexiglass from viewing aid Missing 3/75 3/75 Radwaste 4 20. Straight Edge Ruler Loose 2/75 3/75 Radwaste
- 21. Plexiglass from viewing aid Missing 4/75 4/75 Radwaste
- 22. Jet Pump Stop Screw Loose 2/75 3/75 Radwas te
- 23. 3 Screws 3/16" Dia X 3" Long Loose 2/75 3/75 Radwas te
- 24. 2 1/2" Dia. Hex Nuts Loose 2/75 3/75 Radwas te LOOSE - Observed, but source unknown.
MISSING - Not in normal location and unaccounted for.
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.. D N U CLE AR EN Ei!GY DIVISION ccacau. El.ECTOIO COWANY.175 CURTNCR AVENUE. SAN JOSE. CN.!TORNIA 95125 M2'lCodo _ Phona (400) 237-3000. T'.VX NO. 910 303-011S G-EB0-5-160 April 22,1975 CC: G.I. Wells D.P. Galle J.S. Abel I!r. Ilick Kalivianakis Station Superintendent Quad Ci. ties Generating Station Commonwealth Edison Co.
P. O.Ilox 216 Cor.dova, Illinois 61242
SUBJECT:
QUAD CITIES II -
CYCLE I OUTAGE LOOSE PARTS ANALYSIS
Dear !!ick:
Attached is the safety analysis concerning the loose parts uhich were either dropped into the reactor, or are missing and assumed to be in the reactor.
The conclusion reached is that the loose parts will not pose a safety problem, and, based on 10CFR 50.59, there is no unreviewed l safety hazard.
Very trul,y yours, )
/ .,
e LA. ~i f~ct..:x,.Lbhn' :--
if . G . Crockett '
Product Service Engineer
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.c O (D GhM;1Ar. { ELECTalc If1TR000CTION During tha recent refueling outage (Reload 1-Early 1975) at Quad Cities Unit 2, three items were either dropped into the reactor or are missing and assumed to be in the reactor. An extensive search was conducted but the subject itc:as could not be located. The safety implications of leaving these items in the reactor have been evaluated.
DESCRIPTION The following is a description of the items left in the reactor and an estimate of the probable location.
Item 1 - Jet pumo restrainer gate adjusting screw found missing from jet pump #18 during routine jet pump inspection.
Probable location - below jet pump #18 (vessel azimuth approx.
300) on shroud support shelf.
Description - GE Dug. 12933127 - Stainless steel bolt with hex-head, approximately 3 inches long by 3/4 inch diameter. Weight -
less than one pound.
Item 2_ - t'eutron dosiceter (part of surveillance prograra) was not attached to sample holder basket as it should have been. The bracket and holder are also missing.
Probable location - Between jet pump #7 and jet pump #8 on shroud support shelf (vessel azimuth - 950).
Descriotion - GE Dag. 15037636 and 15837635
- Plate OT26 x 6.00 x .031 thick) welded to tube 10.00 x .500 sch 40 pipe with internal spring clip.
- Dosimeter - 6" x 1/2" thick) ar.d internal OD pip spacer .33(e with end diameter plugs x .32" (1/2"Bail thick). diameter x 1/8" ucided to end plugs 4" x 6-1/2" x .188" square stock. 6 wire loop speciments inside (3 iron, 3 cooper). All other materials are stainless steel.
Itca 3_ - Carbide grinding burr lest during repair work on RPV.
Probable location _ - in annulus between shroud and pressure vessel -
azimuth unkno.:n.
.Descr,ip_ tion - carbide grinding burr 1/2 inch long x 3/8 inch dianeter, pear shaped. Shaft not attached.
SAFETY EVALUATIOM
-- The obvious concern associated with the lost pieces is that associated with the potential for fuel bundle flow blockage andsubsequent fuel damage. A detailed
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9
'Ji.b?.3.M [3 E!iOTill4 study of flow blockage in a B'.lR has been made in a GE Topical Report (1) on file in the Public Document Room. As stated in that report, based on analyses of high power dcnsity fuel operating at 18.5 ku/ft:*
a) It would take more than a 905 inlet area blockage to cause a tiCHFR less than 1.0: therefora, no fuel rod damage would occur unless more than a 90% blockage occurs.
b) If the blockage were more than 90%, clad malt and fuel crumbling would occur. This wculd lead to high radiation sensed by the main staan line radi-Offsite doses ation monitors which would scram and isolate the reactor.
remain less than 10CFR?O limits.
Based on the infornation concerning the size of the lost pieces the ~folicwing cen-clusions are drawn:
- 1. If the parts found their way into the lower pleaum the fluid veloci-ties would be high enough to sueep them up toward the fuel bundles only if the parts maintained a horizontal position. In the vertical position, the Also, if the parts were velocities are not high enough to lif t the parts.
lying on the bottoa head where the fluid velocities are low, it is consider-ed unlikely that they could get swa?t up off the vessel surface. Therefore, even though it is possible for the pieces to get lifted up toward the fuel, its occurrance is considered unlikely.
- 2. If the pieces were swept across a central bundle orifice (diameter
= 2.262 in. , area - 4.019 in )2 it vould cause a maximum of 80 - 83% re-duction in flow area. From Figure 4-3 of Reference 2, this flow blockage would reduce the average bundle MCHFR frcm 3.5 to 3.2, which viould not cause boiling transition. Thus, there would be not subsequent fuel or clad-ding damage.
- 3. It is highly unlikely that gross fuel damai;e will occur since no piece is lerge en6 ugh to cause blockages greater than 90% and it is highly improbable tint all-the pieces would accumulate in one bundle.
- 4. Mo dcmage would occur to cny bundle adjacent to the bundle with the flow blocked.
- 5. If the piece passed through the orifice, it would have to pass through -
the nose piece guards and the lower tie plate, which require very unlikely alignm::nt of the_ piece and the scull pissages.
4 Quad Cities II has a maximum linear heat generation rate limit of,-17.5 kw/ft.
l
-(i) liEDO 10174, " Consequences of a Postulated Flow Clockage Incident in a l' Boiling (fator Raactor,G.J. Scatena; May 1970.
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- 6. If the parts uere broken into small pieces they could possibly becoma lodged in a spacer which could cause boiling transition and over heating.
Fretting of the cladding could also occur which would lead to failure and s consequent fission product release.
Dased on the above, it can he concluded that the lost parts uill not pose a safety problea. Since the parts are still in the reactor there is a remote possibility of a highly localized ficu blochge uith subseqitent fuel rod damage and smll fission product r'elease. However, offsite doses will remain less than 10CFR20 lirni ts. Ther2 fore, based on 10CFR50.59, operation of the reactor with the lost parts in tha reactor doas not constitute an unrevieuad safety hazard.
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Cordova,1:linois 61242 D Telephone 309/654 2241
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February 28, 1975 N7 n - - I976 w g
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,1 hs Mr. John F. O ' Leary , Director Q,i' Directorate of Licensing Regulation wiu ,;. /'y',/\
Nuclear Regulatory Comission Washington, D. C. 20545
Reference:
quad-Cl ties Nuclear Power Station Docket No. 50-265 DFR-30 Appendix A, Sections 1.0.A.4, 6.6.S.I.a
Dear Mr. O ' Leary:
Enclosed please find Abnormal Occurrence Report No. 50-265/75-8 for quad-Cities Nuclear Power Station. This occurrence was previously reported to Region ill, Directorate of Regulatory Operations by telephone on February 18, 1975 .and to you and Region li t , Directorate of Regulatory Operations by telecopy on February 19, 1975.
This report is submitted to you in accordance with the requirements of Technical Specification 6.6.B.I.a.
Very truly yours, C0!V10fulEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION N. J. Kallvianakis .
Station Superintendent NJK/MPF/j eh cc: Region t il , Directorate of Regulatory Operations J. S. Abel 2E80
. O O REPORTi; UMBER: A0-50-265/75-8
_ REPORT DATE: February 28, 1975
_0CCURRENCE DATE: February 18. 1975 IDENTIFICATION OF OCCURRENCE: /
Jet pump components were discovered missing during a jet pump inspection.
_ CONDITIONS PRIOR TO OCCURRENCE:
The Unit Two reactor fuel assemblies had been removed and inserted into t fuel storage pool to facilitate out-of-core sipping operations and recirculation piping repairs during the refueling outage.
DESCRIPTION OF OCCURRENCE:
With the core inspection void of fuel during refueling operations, a scheduled jet pump was performed.
underwater television camera and video tape unit.This inspection was carried out are listed below. The details of the inspection are illustrated on Figures 1 and 2The various jet pump components and their physical loc f
(1)
Beam bolt assemblies were observed for movement while applying 300 ft-lbs of toraue to tha ha= Mit ! . bot:.- Lt.e vluckwise and counter-clockwise directions.
(2)
Beam bolt keepers were inspected with respect to the following:
(a) Position f
1 (b) Evidence of movement (c) Condition of the four tack welds *
(3) - The hold-down beams were inspected with respect to the following* i (a) Position t 1
(b) Check of beam pocket fits (c) Evidence of movement (4)
The lock plates were inspected with respect to the following:
(a)
Condition of the four flat head screws and their respective tack welds. ;
(b) Evidence of movement a
c.
< e - A0 50-265/75-8 Q February 28, 1975 (5) The beam bolt retainers were Inspected to determine the ,
condition of the 1/2" cap screw and its tack weld. l i
(6) The restrainer gate wedges were inspected with respect to the following:
(a) Position (b) Engagement with the restrainer and belly band of the jet pump .
(c) Evidence of movement (7) The restrainer stops (adjusting screws) were inspected with respect to the following:
(a) Tightness with the belly band of the jet pump.
(b) Evidence of movement (c) Condition of the adjusting screw tack weld.
(8) The restrainer gates were inspected with respect to the following:
(a) Condition of the two clamp bolts.
(b) Condition and tightness of the two clamp bolt nuts.
(c) Condition of the two tack welds of each clamp bolt keeper.
Upon completion of the above inspections on all twenty Jet pumps, the following discrepancles were noted:
(1) The beam bolt retainer clips and 1/2" cap screws were found to-be. missing on jet purops 7 and 8 (2) The restrainer adjusting screw on the shroud side of jet pump 18 was found to be missing.
(3) Restrainer gate keepers on jet pumps I, 8, 12, 15, and 18 were found to have their welds in place, but not fused to the restrainer gate.
' Dest CtlATI0tt OF APPAREllT CAUSE OF OCCURREtlCF:
Equipment Failure-The apparent cause of the missing retainer clips, the 1/2" cap screws, and the
_ adjusting screw is attributed to equipment failures caused by instal.lation deficiencies. Based on the parts being inadequately installed, the vibrational forces present during normal operation could cause these components to become dislodged from their normal positions.
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A0 50-20/75-8 Q (] February 28, 1975 During the jet pump repairs to Unit 2 during 1972, the beam bolts and keepers were the prinary components repaired. The ecpairs necessary to Unit I during its past refueling outage in 1974 revealed that further defective installation existed. It is felt that these present components were originally installed in a deficient manner and that the possibility of their failure was not known at the time of the original Unit 2 repairs. The discovery of their failure at this time is consistent with the deficiencies noted during the Unit I outage in 1974 ANALYSIS OF OCCURRENCE:
The jet pumps are designed to withstand the combined loadings from differential pressure and temperature, dead weight, fluid movement, seismic acceleration, and vibration without failure or loss of integrity. The missing jet pump com-ponents did not lead to jet pump f ailure er loss of integrity. Particularly, there were no failurcs of any jet pump hold-down components. There were thus no unsafe conditions existing during previous periods of reactor power operation.
Jet pump component failures and missing or loose parts have been previously analyzed in the following documents:
(1) Quad-Citics Station, Unit 2, Special Report No. 2, " Jet Pump O pe rab i l i ty" .
(2) NE00-10174, May 1970, G. J. Scateno, " Consequences of a Postulated Flow Blockace incident in a Bnilinn Water Rear. tor".
(3) Qut.d-ci ties S tation, Uni t 1, Abnorn'al Occurrence Report Ictters of April 25, 1974, May 30, 1974, and July 12, 1974.
The health and safety of the public were not adversely affected by this occurrence.
CORRECT!VE ACTION:
The missing bean bolt retainer clips and 1/2" cap screws of Jct pumps 7 and 8 will not be replaced. These pieces,are important only during the initial construction of the jet pump beam assembly or during their rensoval. After installation of the beam bolt, the function of these pieces is completed.
A replacement stop (adjusting) screw has been installed and tack welded to its holding clamp on jet pump 18. As an alternative to removal of the jet pump throat, the welding tool used to tack weld the stop screw was modified to per-form its intended function.
Although it has been postulated that the restrainer gate keeper on jet pump 18 was loosened during the repair of the stop screw, the tack welds of all jet pump restrainer gates were reinspected as a precautionary measure. As a result of the faulty tack welds discovered on the jet pump restrainer gate keepers of jet pumps 1, 8, 12, 15, and 18, the restrainer gate bolts were retorqued, and new tack welds were placed and verified. A similar inspection of the twenty jet pump beam bolt keepers was performed with satisfactory results.
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A0 50-265/7,5-8 1-1 February 28, 1975-
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A list of objects, known to date, which are loose or missing in the unit 2 reactor vessel is attached. Further search for loose or missing parts is L j being conducted and an attempt will be made to retrieve all these objects before returning the unit to operation. Details of the searches for these parts will be reported in the future.
FAILURE DATA:
i s l The problems discovered on this inspection of Unit 2 are similar but were less severe than those discovered following a jet puno failure of Unit 2 in August 1972. At that time, a jet pump assenbly had become dislodged from its nornal position and rotated in the vessel. Extensive inspections and repairs were perforned on all Unit 2 jet pumps and they have since operated satisfactorily.
An extensive inspection of all Unit 1 Jet pumps during its first refueling outage in April,1974, revealed a large number of Jet pump discrepancies. These included beam bolt torque test failures, sheared restrainer gate bolts and keepers, trissing and cracked restrainer gate bolt keeper tack welds, a missing j restrainer gate wedge and indications of ucar in the vicinity of the wedge indicating possibic vertical movement of the wedge prior to the inspections.
All of the jet pump problems which have occurred at quad-Cities Station have
, been attributed to faulty craft installation and workmanship during the initial construction of both units.
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Or.l Gill / L CATE OF i CATE CF PART STATU! DISCOVERY R ETP. l EV AL DISPOSITION
- 1. Lighting Support 3 racket From Refuel Bridge Missir o 1/ 9/75 1/17/75 Huno in Unit 1 Fuel Fool
- 2. Neutron Dosimeter Tube Missir q 2/19/75 3 Neutron Oosimeter Missir g 2/19/75
- 4. JP 18 Adjustinq Stop Screw Missirq 2/17/75
- 5. JP 7 1/2" Cap Screw M issir g 2/17/75
- 6. JP 7 Retainer Clip Missirq 2/17/75 I k
- 7. JP 8 1/2" Cap Screw Missiro 2/17/75
- 8. JP S Petainer Clip Missirq 2/17/75
- 9. 3 Pieces of Wire Lcose 2/17/75 10 Piece of Angle Iron Loose 2/17/75
- 11. Open End Wrench Loose 2/17/75 12, 3 Pieces of Tape Loose 2/15/75 2/17/75 R e dwas t e
- 63. I Piece of Vire Loose 2/15/75 2/17/75 Radwaste l h4 Rag Loose 2/23/75 LOOSE = Observed, but source unknown.
MISSING = Not in normal location and unaccounted for.
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- Tciphwa.!/ EnZ'41 UJK-75-76 Region III, Attention: Mr. C. Felerabend Telecopy:
February 19, 1975 J. Keppler, Henienn2 Olroctor Directorate of Iicc:letary Operatione llegion III U. S, Nuclear Re;~.,ulatory Corr.innien
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~/99 Roouevelt Homi Glen lillyn , Illincia 60137 ,
Refer,ance: Quad-citiec Uncletm Pouer Station , Unit 2 -
Dochen ua. 50-265, r;PD-30 Appendix A, Ucetionc 1.0.It . 4, 6.6.D.1.a. .
Dane Mr. Keppler:
(
The purpone of this letter in t.o provide ac required you with.notifien.
by Technical Spacification tion of on Abnormal Occurmance ,
6.6.n.1.a within 24 hours of the cccurrence. k Uith. Unit 2 in the jetcold' (mnpuhutdonn.cendition innpoetionn revealed for the thefollowing current. re-fuellug outage, -
discrepancien: scrcu.
Jet Pung 07 - niscing n huan bolt retainer and cap 1.
Jet, Purp FG - niincing a beam bolt retainer and cap nercu.
2.
3 Jet. Puna #10 - nissing the rentrainer gate adjucting f~
i screw on tha :ahroud nido.
- 4. A piece of wire was observed loone' in the annulun area.. :
acrowc should not affect-The minuine benr1 bolt retainero and capTnn minning rentraince cute the operation of jet purps 7 and 3.
ndjuuting screu nho .nd not prevent jet pump 18' from being ade-quntely accured since the beau bolt una properly torqued and intuot.
An atterrpt will be nado ara
.P.lanr- to retricve all minaing being developed to installparts afrom nuu.the reactor adjucting vennel.
screw on the jet pur.n 18 rentrainer gato.
Thic occurrence was18, discuaned 1975 ny telephone with Mr. Knop of yourFurther infor office on February uhich uill be sub-by Abnorcul Occurrence Report AO-50-265375-8 mitted within 10 dnys of' thin occurrenco.
Very truly yours, COPJQliMEALTH EDIS0!T COMPANY Q D-CITIES HUCLEAR FOWER STATIO)!
K'aaw.s; j;*, i wgCL I J. Kalivinnakia 4 -
ti t 1 orint.cncont J.S. Abel Q._g Oc: Direct.. i.tc c;' 1 aensing. .
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