ML20066C237
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| ML20066C237 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 08/31/1982 |
| From: | Swartz E COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20066C217 | List: |
| References | |
| REF-SSINS-6820 4925N, IEB-79-08, IEB-79-8, NUDOCS 8211090420 | |
| Download: ML20066C237 (2) | |
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
[Table view]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 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 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, 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 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 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 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 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 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 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 ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety 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 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 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 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 ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 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) 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) 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 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray 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-99-066, 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 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 1999-09-09 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
[Table view]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-99-170, 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 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 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 ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 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) 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 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 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 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-99-103, 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 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 ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data 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-99-098, 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-99-111, 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-99-099, 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 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 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-99-088, 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 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 ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem 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 1999-09-30 Category:UTILITY TO NRC MONTHYEARML20065D0511990-09-17017 September 1990
[Table view]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. 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 ML20055D4741990-06-29029 June 1990 Forwards Annual FSAR Update for Quad-Cities Station 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 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 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 ML20043G4251990-06-0202 June 1990 Forwards Listing of Changes,Tests & Experiments Completed During May 1990 ML20043D3231990-06-0101 June 1990 Forwards Rev 31 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043D3201990-06-0101 June 1990 Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043C8181990-05-30030 May 1990 Forwards Rev 1 to Core Operating Limits Rept,Dresden Station Unit 2,Cycle 12. Rev Reflects MCPR Limit Adjustment for Cycle 12 Due to Number of Reused Channels,Per Discussion of Channel Bow Effects in BWRs in NRC Bulletin 90-002 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 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 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 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 ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) 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 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested 1990-09-04 |
Text
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Commonwrith Edison
[o!DN i Y. On3 First Nationti Plus. Chicags--Hhnois
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C I" Addrtss R: ply to: Post Offica Box 767
. Chic go, Illinois 60690 Augus t 31, 1982 Mr. James G. Keppler, Regional Administrator Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Dresden Station Units 2 and 3 Quad Cities Station Units 1 and 2 IE Bulletin No. 79-08 Item No. 6 Daily Position Verification of ECCS Valves NRC Docket Nos. 50-237/249 and 50-254/265 Re ferences (a): Cordell Reed letter to J. G. Keppler dated April 27, 1979 (b): Cordell Reed letter to T. A. Ippolito dated Augus t 3, 1979 (c): J. G. Keppler letter to Byron Lee, Jr.
dated April 14, 1979 (d): T. A. Ippolito letter to D. L. Peoples dated March 10, 1980
Dear Mr. Keppler:
References (a) and (b) provided the Commonwealth Edison Company commitments concerning safety-related valve position verification in response to Reference (c) IE Bulletin No. 79-08 Item 6 for our Dresden and Quad Cities Stations. Subsequently, Reference (d) provided the results of the NRC Staff evaluation which concluded that our commitments satisfied the intent of IE Bulletin 79-08 for this Item 6.
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In particular, we indicaEed that the positions of vital manual ECCS valves are controlled by the use and documentation of locks on the handwheels. Additionally, we committed to implement a procedure for daily verification that all accessible ECCS valves in the main flow paths are in their proper positions.
8211090420 821104 SEP 2 1832 PDR ADOCK 05000237 G PDR
l Since the implementation of this procedure in 1979 at both
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Dresden and Quad Cities Stations, the daily valve position verification has never identified any locked manual ECCS valves as being out of proper position. For this reason, and the fact that thi position of these valves is controlled by chains and padlocks, we believe that daily surveillances are no longer warranted in order to address the original NRC Staff concerns regarding valve position verification.
In view of the above, we f eel that monthly verification is now a more appropriate response to IE Bulletin 79-08 Item 6 concerning manual ECCS valves. Therefore, we intend to reduce the frequency of position verification on locked, manual valves in the ECCS systems from once per day to once per month at our Dresden and Quad Cities Stations. Our current position verification practice on other valves in the ECCS systems will remain unchanged.
Please address any questions that you or your staff may have concerning this matter to this o f fice.
Very truly yours, E. ouglas Swart Nuclear Licensing Administrator cc: Region III Inspector - Dresden Region III Inspector - Quad Cities Darrell G. Eisenhut - D/DL 4925N 1
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