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Category:CORRESPONDENCE-LETTERS
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999
Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217K7011999-10-13013 October 1999
Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl
05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999
Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action
ML20217F6321999-10-0707 October 1999
Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations
05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999
Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee
ML20212K9421999-10-0505 October 1999
Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999
Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage
ML20212J0451999-09-21021 September 1999
Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr
ML20212D8231999-09-20020 September 1999
Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21
ML20212C6961999-09-15015 September 1999
Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted
SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999
Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys
ML20211Q7961999-09-0909 September 1999
Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr,
ML20217H5661999-09-0909 September 1999
Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl
ML20211Q6511999-09-0808 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306
ML20211G1221999-08-27027 August 1999
Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d)
ML20211F8251999-08-25025 August 1999
Forwards Insp Repts 50-254/99-15 & 50-265/99-15 on 990816-20.No Violations Noted.Insp Evaluated Effectiveness of Maint Rule Program & Review Periodic Evaluation Specifically Required for 10CFR50.65
ML20211B8691999-08-20020 August 1999
Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed
ML20211D1491999-08-19019 August 1999
Forwards Insp Repts 50-254/99-16 & 50-265/99-16 on 990719-22.Staff Identified Major Discrepancy Re Accuracy of Data Submitted to NRC for Protected Area Security Equipment Performance
ML20211C7601999-08-19019 August 1999
Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program
ML20210R7451999-08-13013 August 1999
Forwards Insp Repts 50-254/99-11 & 50-265/99-11 on 990601-0720.NRC Identified Several Issues Which Were Categorized as Being of Low Risk Significance.Two Issues Involved NCVs of Regulatory Requirements
SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999
Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl
SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999
Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety
ML20210T9941999-08-13013 August 1999
Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted
SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999
Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated
ML20210R9541999-08-10010 August 1999
Informs That During 990804 Telcon Between J Bartlet & M Bielby,Arrangements Were Made for NRC to Insp License Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
ML20210M5461999-08-0606 August 1999
Discusses 990804 Telcon Between J Bartlet & M Bielby,Where Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
ML20210L8371999-08-0202 August 1999
Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves
ML20210M4691999-07-30030 July 1999
Forwards Insp Repts 50-254/99-14 & 50-265/99-14 on 990713-15.One NCV Was Identified & Discussed in Encl Insp
ML20210H4661999-07-29029 July 1999
Forwards Insp Repts 50-254/99-13 & 50-265/99-13 on 990628-0702.No Violations Noted.Insp Consisted of Selective Examination of Procedures & Representative Records, Observations of Activities & Interviews with Personnel
05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999
Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed
SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999
Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2
SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999
Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept
SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999
Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625
ML20210B7071999-07-16016 July 1999
Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7)
ML20196J9061999-07-0101 July 1999
Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21
ML20196J9131999-07-0101 July 1999
Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3)
ML20209B8241999-06-30030 June 1999
Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes
SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999
Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage
ML20209B2081999-06-29029 June 1999
Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901
05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999
Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action
SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999
Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601
SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999
Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested
SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999
Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period
ML20196F7921999-06-24024 June 1999
Forwards Meeting Summary,Nrc Meeting Handout & Licensee Handout from 990608 Meeting
ML20196E7131999-06-23023 June 1999
Forwards Insp Repts 50-254/99-09 & 50-265/99-09 on 990421-0531.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy
ML20196E4821999-06-21021 June 1999
Discusses 990617 Meeting by Region III Senior Reactor Analysts (SRA) in Cordova,Il to Meet with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999
Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630
ML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217K7011999-10-13013 October 1999
Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl
05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999
Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action
05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999
Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999
Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage
SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999
Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys
ML20211G1221999-08-27027 August 1999
Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d)
SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999
Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated
SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999
Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety
SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999
Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999
Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed
SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999
Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept
SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999
Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2
SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999
Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625
ML20196J9061999-07-0101 July 1999
Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21
ML20196J9131999-07-0101 July 1999
Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3)
ML20209B8241999-06-30030 June 1999
Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes
SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999
Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage
SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999
Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period
SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999
Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601
05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999
Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action
SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999
Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested
SVP-99-125, Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl1999-06-15015 June 1999
Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl
ML20195E3491999-06-0707 June 1999
Withdraws Util Requesting License Change for Plant Security Plan Rev.Licensee Will re-evaluate Situation & May Request Approval of Change in Future
ML20207G1451999-06-0707 June 1999
Forwards Rev 45 to Comed Quad Cities Nuclear Power Station Security Plan.Rev Includes Changes Listed.Security Plan Is Withheld from Public Disclosure Per 10CFR73.21
ML20195D6351999-06-0404 June 1999
Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs
SVP-99-105, Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 9905291999-05-20020 May 1999
Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 990529
ML20195B2301999-05-19019 May 1999
Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB
SVP-99-111, Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-05-17017 May 1999
Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
SVP-99-098, Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i)1999-05-17017 May 1999
Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i)
SVP-99-099, Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval1999-05-13013 May 1999
Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval
SVP-99-096, Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 19991999-05-12012 May 1999
Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 1999
05000254/LER-1999-001, Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions1999-05-12012 May 1999
Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions
ML20206F5381999-04-30030 April 1999
Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape
SVP-99-108, Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 9903301999-04-30030 April 1999
Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 990330
SVP-99-036, Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions1999-04-29029 April 1999
Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions
SVP-99-088, Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B1999-04-29029 April 1999
Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B
ML20205T1141999-04-22022 April 1999
Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP
ML20206B2471999-04-20020 April 1999
Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412
SVP-99-065, Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License1999-04-14014 April 1999
Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License
SVP-99-058, Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations1999-04-14014 April 1999
Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations
SVP-99-063, Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval1999-04-0909 April 1999
Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval
JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999
Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick
SVP-99-057, Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re1999-04-0505 April 1999
Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re
ML20205K5841999-03-31031 March 1999
Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
SVP-99-062, Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-03-31031 March 1999
Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20065D0511990-09-17017 September 1990
Forwards Objectives & Scope of 901205 Emergency Plan Exercise
ML20064A7091990-09-14014 September 1990
Forwards Endorsement 133 to Nelia Policy NF-187 & Endorsement 116 to Maelu Policy MF-54
ML20059F4891990-09-0404 September 1990
Forwards Listing of Changes,Tests & Experiments Completed During Month of Aug 1990 for Plant
ML20059B9721990-08-28028 August 1990
Forwards Reactor Head & Upper Shell Insp Plan,Per 900419 Meeting.Insp Plan Does Not Encompass Uppermost shell-to- Shell Weld Due to Technological Limitations
ML20059F0311990-08-27027 August 1990
Provides Schedule for Completion of Installation of Mods to Plants Reactor Water Level Instrumentation,Per Generic Ltr 84-23.Penetrations Will Be Installed During Outage 13 for Dresden & During Outage 12 for Quad-Cities
ML20059E9531990-08-27027 August 1990
Forwards Summary of Fabrication History for Upper Reactor Vessel,Per 900419 Technical Meeting.Summary Indicates That Fabrication Mismatches,Considered to Be Significant for Development of Insp Plan,Identified at head-to-flange Weld
ML20059C7201990-08-23023 August 1990
Forwards Effluent & Waste Disposal Semiannual Rept,Jan-June 1990 Gaseous Effluents-Summation of All Releases & Rev 8 to Quad-Cities Station Process Control Program for Processing of Radioactive Wet Waste
ML20058P3481990-08-0909 August 1990
Forwards Summary of Fuel Performance,End of Cycle 10,May 1990. No Leakage or Fuel Failure Noted
ML20058M8221990-08-0707 August 1990
Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions
ML20058M8041990-08-0606 August 1990
Advises That W/Completion of Operator Training Program,Plant SPDS Meets Requirements Delineated in NUREG-0737,Suppl 1
ML20058M8591990-08-0606 August 1990
Forwards Rept of Metallurgical Exam That Revealed No Evidence of Defects,Porosity or Slag in Weld Overlay. Rept Responds to IGSCC Insp Performed on Facility IGSCC Susceptible Piping
ML20058M4101990-08-0101 August 1990
Forwards Listing of Changes,Tests & Experiments Completed During Month of Jul 1990 for Plant
ML20058M8291990-07-31031 July 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements of Corrective Actions. Status of Implementation of Generic Safety Issues Encl
ML20055J1631990-07-26026 July 1990
Forwards Reactor Containment Bldg Integrated Leak Rate Test Quad-Cities Nuclear Power Station Unit 2,900427-28, & Related Apps Describing Type a Test,Per 10CFR50,App J, Section V.B.1.Next Test Scheduled for Fall 1991
ML20055H7631990-07-25025 July 1990
Forwards Financial Info Re Decommissioning of Plants
ML20055G6331990-07-18018 July 1990
Responds to Generic Ltr 89-06 Re SPDS to Meet Requirements of Suppl 1 to NUREG-0737.SPDS Lesson Plan Incorporated Into Initial License Class Training Program
ML17202L2861990-07-0202 July 1990
Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary.
ML20055D4741990-06-29029 June 1990
Forwards Annual FSAR Update for Quad-Cities Station
ML20055D4341990-06-29029 June 1990
Forwards Comm Ed Rept on Evaluation of Cracking in Quad- Cities Unit 2 Reactor Head, Per Commitment Made at 900419 Meeting W/Nrr.Rept Concludes That Cracks Caused by Interdendritic Stress Corrosion Cracking Mechanism
ML20055C8551990-06-15015 June 1990
Forwards Special Neutron Attenuation Test for High Density Spent Fuel Racks (Wet), Final Rept.Rept Provides Results of Neutron Radioassay Measurement Program Conducted During Fall,1989 Refueling Outage
ML20043D7661990-06-0404 June 1990
Responds to J Lieberman 900501 Ltr Re Rl Dickherber. Confidence in Dickherber Performance in Future for Nonlicensed Duties Can Be Based Upon Demonstrated Record of Good Past Performance
ML20043D7691990-06-0404 June 1990
Responds to 900501 Ltr Re Work Hours for Dickherber.During Outage,Dickherber Worked Extended Hours Traditionally Associated W/Refueling Activities
ML20043G4251990-06-0202 June 1990
Forwards Listing of Changes,Tests & Experiments Completed During May 1990
ML20043D3201990-06-0101 June 1990
Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20043B6681990-05-22022 May 1990
Forwards Proposed Changes to SER Re Hot Shutdown Repairs in Event of Fire,Per 10CFR50,App R Section Iii.G Covering Spurious Operations & High Impedance Faults & Electrical Isolation Deficiency
ML20043A4681990-05-10010 May 1990
Forwards Proposed Changes to 880721 SER Re App R Section Iii.G Exemption for Fire Zones 1.1.1.1S & 1.1.1.2,southern & Northern Torus Level in Unit 1 Reactor Bldg Column & Unit 1 Reactor Bldg Elevations 623 Ft & 647 Ft
ML20042H0011990-05-0303 May 1990
Forwards Listing of Changes,Tests, & Experiments Completed During Apr 1990
ML20042G3501990-05-0202 May 1990
Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-254/90-02 & 50-265/90-02.Corrective Actions:Continuous Fire Watch Initiated & Training Conducted on Procedure Rev
ML20042F1181990-05-0101 May 1990
Advises of Listed Value for Secondary Containment,Per NRC Request for Addl Info Re LER 50-254/87-025.Value Based on Info Contained in Plant FSAR
ML20042F0691990-05-0101 May 1990
Responds to Generic Ltr 83-28,Item 4.5.3 Re Reactor Protection Sys on-line Functional Test Intervals.Endorses Two BWR Owners Group Topical Repts NEDC-30844 & NEDC-30851P Generic Evaluations
ML20042F1221990-05-0101 May 1990
Forwards Preliminary Rept of IGSCC Insp Results.Flaw Indication Detected in Weld Overlay Matl of Weld 02J-S3 & Removed by Boat Sample & Std Weld Overlay Thickness Restored.Final Rept Will Be Forwarded within 30 Days
ML20042E4491990-04-11011 April 1990
Forwards Request for Rev to Previous NRC Exemption Approval on 860625 Re Combustible Load Values
ML20042F0351990-03-23023 March 1990
Forwards Part 3 of 1989 Operating Rept.W/O Rept
ML19330D5161990-03-14014 March 1990
Advises That Revs to Inservice Testing Program & Implementation Procedures Will Be Completed by 900629,per Generic Ltr 89-04
ML20012C0721990-03-0808 March 1990
Comments on SALP Board Repts 50-254/89-01 & 50-265/89-01 for Oct 1988 to Nov 1989.Util Appreciates NRC Recognition of Overall Improvements in Areas of Operation & Emergency Preparedness & Good Performance in Area of Security
ML20012B5921990-03-0202 March 1990
Forwards Listing of Changes,Tests & Experiments Computed During Month of Feb 1990 for Plant
ML20006F3361990-02-0808 February 1990
Responds to NRC Ltr 900110 Ltr Re Violations Noted in Insp Repts 50-254/89-25 & 50-265/89-25.Corrective Actions:Safety Evaluations Submitted Via 900116 Ltr & Table of Content Will Be Completed for 1989 FSAR Update to Be Submitted by 900630
ML20012A9551990-02-0808 February 1990
Responds to Violations Noted in Insp Repts 50-254/89-26 & 50-265/89-26.Corrective Action:Procedure Qis 47-1 Revised to Include Requirement That Equalizing Valve Be Open During Isolation of Transmitter
ML20011E7131990-02-0606 February 1990
Forwards Reactor Containment Bldg Integrated Leak Rate Test,Quad Cities Nuclear Power Station,Unit 1,891114-15. Next Type a Test Scheduled for Fall 1990
ML20006E1721990-02-0202 February 1990
Forwards Listing of Changes,Tests & Experiments Completed During Jan 1990,including Items Completed in 1989. Interlocks Installed on Refuel Bridge Fuel Handling Machine to Prevent Raising Hoist While Hoist Loaded
ML20006C5071990-01-30030 January 1990
Identifies Schedular Change for Completion of Corrective Actions Associated W/Human Engineering Deficiencies 159,187 & 489 Re Escutcheon Plates for Control Switches Which Need Replacement.Plates Will Be Replaced During Outages
ML20006C7401990-01-22022 January 1990
Advises of Receipt of Accreditation Renewal by INPO in Sept 1989 for Operator Requalification Training Program,Per Generic Ltr 87-07 Requirements & Informs That Programs Developed Using Systematic Approach to Training
ML19354E8591990-01-16016 January 1990
Responds to NRC 891128 Ltr Re Violations Noted in Insp Repts 50-254/89-17 & 50-265/89-17.Corrective Actions:Procedure NSWP-E-01, Electrical Cable Installation Insp, Will Be Revised to Enhance Human Factor Aspect
ML19354D8131990-01-11011 January 1990
Forwards Corrected App C to Monthly Operating Rept for Dec 1989 for Quad Cities Units 1 & 2
ML20005F6441990-01-0303 January 1990
Forwards Listing of Changes,Tests & Experiments Completed During Dec 1989.Summary of Safety Evaluations Being Reported in Compliance w/10CFR50.59 & 10CFR50.71(e) Also Encl
ML20005E1691989-12-22022 December 1989
Forwards Rev 22 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facility.Rev Withheld (Ref 10CFR73.21)
ML20043A5741989-12-21021 December 1989
Responds to NRC 891124 Ltr Re Violations Noted in Insp Repts 50-254/89-23 & 50-265/89-23.Corrective Actions:Compressed Gas Cylinder Bottles Secured W/Chain & Fire Marshall Will Increase Tours of Plant Re Transient Combustible Matl
ML20005E1211989-12-18018 December 1989
Forwards Final Rept of Fall 1989 IGSCC Insp Plan,Discussing Items Such as Overlay Repair on Weld 02G-S4,mechanical Stress Improvement & Piping Mods
ML19332G3401989-12-0808 December 1989
Forwards Response to Generic Ltr 89-21, Implementation Status of USI Requirements. Actions to Resolve USI A-9 Re ATWS Will Be Completed in June 1990 & USI A-42 Re Pipe Cracks in BWRs Will Be Completed in Dec 1990
ML19332F9091989-12-0101 December 1989
Forwards Listing of Changes,Tests & Experiments Completed During Nov 1989
1990-09-04
[Table view] |
Text
_ _ _
/~,.
. , Commonwealth Edison
( ') 1400 Opus Place
v ): Downers Crove, Illin:Is 60515 i
l August 7, 1990 I
Dr. Thomas E. Hurley Office of Nuclear Reactor Regulations l U.S. Nuclear Regulatory Commission ;
Hashington, DC 20555 i
Attn: Document Control Desk ,
l j Subje' Quad Cities Nuclear Power Station Units 1 and 2 1 Response to Generic letter 90-04, Request for Information on the Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition Of Requirements or Corrective Actions liRC Docket Numbers 50-254 and 50-265
Reference:
(a) J.G. Partlow letter to all holders of Operating Licenses dated April 25, 1990 l (b) T.J. Kovach to T.E. Murley letter dated .
l June 28, 1990 1 (c) R. Stols to T.E. Murley letter dated
! July 31, 1990 l
Dear Dr. Murley:
l Reference (a) requested that the current implementation status of all 1 I
generic safety issues (GSI) identified in Generic Letter 90-04 be provided to l the Staff by June 29, 1990. Reference (b) requested that the deadline for the submittal be extended to July 31, 1990.
Reference (c) provided the status of the generic safety issue l implementation. In that submittal, Commonwealth Edison provided additional information beyond the guidance contained in the generic letter. The NRR staff requested that some of the information which was provided in reference ,
(c) be further eFpanded. The attached provides the requested information. .
1 If there are any questions or comments regarding this submittal, .
please direct them to me at (708) 515-7283.
Very truly yours, 88' I 88 Rit Stols "O Nuclear Licensing Administrator Rd l oo
~ @,@ Attachment j g
orc cc: A. Bert Davis-Regional Administrator L.N. Olshan-Project Manager I
d 0t RE'a T. Taylor-Senior Resident Inspector g
- /sc1:10152:1 ,
L
., . , . _ _ . - - , . . r. _ , . _ _
m
.FACII.ITY NAME: Quad Cities ^~~ ,
' DOCKET NO.: ' 254 (Unit 11. 265 (Unit 21 .I
'ICENSEE:.
L _Cgasmonwealth Edison !,
e-STATUS Of LICENSEE IMPLEPENTATION OF GENERIC SAFETY ISSUES RESOL'KD WITH IMPOSITION OF REQUIREMENTS OR t.umu1VE ACTIONS SSI/fMPA No.) TITLE APPLICA8ILITY STATUS C0peOITS 40 (B065) Safety Concerns Associated With All BWRs C Letters dated 01/19/32, 01/25/82 and 02/23/82 from T. J. Rausch Pipe Breaks In The 8Wi Scram System to D. G. E nanhut provided the plant specific response to NUREG 0803. GL 81-34 evaluations, inspections,'and analyses were canyieted with no further action required.
New SDV was installed as required per IEB 30-17: M-4-1-81-021 Completed 08/07/84; additional work completed 03/19/86,'11/20/89.
M-4-2-81-421 Completed 05/01/85.
41 (B058) BWR Scram Discharge Volume (SDV) All BWRs C Initial procedure changes were completed between 07/80 and Systems 07/81. New SDV was installed as follows:
M-4-1-81-021 Completed 08/07/84; additional work completed 03/19/86. 11/20/89.
M-4-2-81-021 Completed 05/01/85 Modification-related procedure changes were completed between 05/85 and 07 *85. R. F. Heishman letter to-C. Reed dated 10/15/80 (Inrpection report 50-254/80-19, 50-265/80-21) documented the MRC Resident Inspector's review of IEB 80-14 No items of noncompliance were-identified.
43 (B107) Reliability of Air Systems All Plants I CECO will issue letter providing the status of the required actions for GL 88-14 by 98/15/99.
ID153 2.2.a _ _ c . _-_ ,_ _ _ _ . . _ , _ . . . ~ . . . . ...,._.__,u _.- _._ ___
' APPLICABILITY STATUS COMPOITS GSI/(MPA No d HILf.
- M. H. Richter letter to NRC dated 01/29/90 provided the
-51 (L913) Improving tr.e Reliability of All Plants I schedule for implementation (dates are based on currently Open-Cycle Service water Systems scheduled start dates of refueling outage):
Intake inspection prior to Q1211.11/90 (both units)
Biocide addition mod . Q1R12. 03/92; Q2R11, 09/91 Loop A test /insp. Q1R11, 11/90; Q1R13, 10/93, Q2R11, 09/91; Q2R13, 09/94 Loop B test /insp. Q1R12. 03/92; Q2R12. 03/93 E/C inspection, 01R11, 11/90: Q2R11, 09/91 Corrosion coupons 01R12. 03/92: Q2R11. 09/91 Design Review Q1R11, 11/90 (both units)
Maintenance Review Q1R11, 11/90 (both units)
Inspection Report 50-254/83 4 8; 50 4 65/83 4 7 documented the Resident Inspector's review of IEB 81-03 inspection and testing programs. No concerns were identified. This issue was reviewed again at Region III's request (I.R. 50-254/84-14; 50 4 65/84-12). No items of noncompliance or deviations were found.
- 2 -
-ID153 c := 15:5
k~-a_g.9 --
'GSI/(MPA No.1 ~ TITLE- APPLICABILITY STATUS C(poesTS 67.3.3 (A017) ; Improved Accident Monitoring All Plants- I RG 1.97 ' Letter dated 08/16/86 from T.'Ross'to M.E. Bliss accepted CECO response to R.G. 1.97 with the exception of wi6e range neutron monitoring.
..Five items which have not been completed were identified during the condwet of IR 50-254/88027; 50-265/88828 dated 12/13/88.
Wide Range Nettron Monitoring System This item is currently being negotiated with NRR by SWt E. Reference letter from T. Kovech to T. Muriey dated June 26, 1990.
Range and Taps for Rx Level Instruments This issue is under review by MRR.
Separation of Stfety and Non-Safety Related Equipment M-4-1(2)-88 101 is currently scheduled to be completed by the end of 01R11 (11/90) on Unit One-and the end of 02R11 (9/91) on Unit Two.
Torus Temperature Recorder Minor Design Change 4-1(2)-90-041 is currently scheduled for 01R11 (11/96) and 02R11 (9/91).
Labeling Identification of R.G.1.97 Instrumentation
, The review of labeling identification is scheJuled to be cougpleted by Septe&r, 1990.
3-ID153
^
- GSI/(MPA No.) . TITLE APPLICABILITY STATUS CDP 9ENTS 75 (8076)- Item 1.1 - Post-Trip Review All Plants C Station implementing procedure for post-trip review was issued (Program and Description and Procedure) in Novembe'. 1983. MRC accepted the reponse in letter dated 07/30/85 from D.B. Vassallo to D.L. Farrar.
75 (8085) Item 1.2 - Post-Trip Review - All Plants- C Procedure for SPDS was implemented in 6/85. New computer was Data and Information Capability installed by 6/84. MRC accepted the response in letter dated 03/13/86 from J.A. Zwolinski to D.L. Farrar.
75 (B077) Item 2.1 - Equipment Classification All Plants C Part 1: Verification of Safety related components was completed and Vendor Interface (Reactor and results submitted in 11/05/83 letter. MRC accepted the Trip System Components) response in a letter dated 8/19/87.
Part 2: Procedure which governs the control of vendor information was provided in letter dated 6/28/85. MRC accepted the response in letter dated 2/22/89.
75 (B086) Item 2.2.1 - Equipent Classifica- All Piants C CECO responded in letters dated 11/5/83. 2/29/84, 4/03/63, tion for Safety-Related Components 10/04/89 and 10/27/89. No new programs or controls required.
NRC acrepted response in letter dated 11/28/89.
75 (LOO 3) Item 2.2.2 - Vendor Interface All Plants I/E Clarification of MRC Staff position is provided in GL 90-03.
for Safety.Related Components CECO response will be submittee by 09/26/99.
75 (8078) Items 3.1.1 ( Post - All Plants C CECO response dated Noveu6er 5,1963 indicated no further Maintenance Testing (Reactor action required. MRC letter dated 95/31/85 from D.B. Vassa11e to D.L. Farrar accepted the response.
75 (3079) Item 3.1.3 - Post-Maintenance All Plants C Ceco response dated November 5,1963 indicated no further action Testing-Changes to Test Requirements required. NRC letter dated 09/25/85 from J.A. Zwolinski to D.L.
Farrar accepted the response.
75 (6087) Items 3.2.1 & 3.2.2 - Post-Mainten- All Plants C L respoase dated Noveu6er 5,1983 indicated no further action ance Testing ( All Other Safety- required. MRC letter dated 05/31/85 from D.B. Vassa1To to D.L.
- Related Components) Farrar accepted the response.
75 (8088) Item 3.2.3 - Post-Maintenance All Plants - C CEto response dated November 5.1983 indicated no further action Testing-Changes to Test Requirements required. MRC letter dated 09/25/D5 from J.A. Zwotinski to D.L.
( All Other Safety-Related Components) . Farrar accepted response.
- 4-ID153
3-
'fa3IMMPA No. ) TITLE APPLICA8ILITY STATUS COMENTS a.
75 (8080) Item 4.1 - Reac'.or Trip System All Plants NA GL 83-28 states this applicable to all PWRs Reliability (Vendor-Related Modifications) 75 (B081) Items 4.2.1 & 4.2.2 - Reactor Trip All PWRs MA System Reliability - Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (8082) Item 4.3 - Reactor Trip System All W and B&W NA Reliability - Design Modifications Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (8090) Item 4.3 - Reactor Trip System All W & B&W NA Reliability - Tech Spec Changes Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (8091) Item 4.4 - Reactor Trip System All B&W Plants NA Reliability { Improvements in Maintenance and Test Procedures for B&W Plants) 15 (0092) Item 4.5.1 - Reactor Trip System All Plants C Item 4.5.1: CECO responded to this issue in letters dated Reliability - Diverse Trip Features November 5,1983 and June 1,1984. The following (System Functional Testing) tests / modification were implemented:
Back-up scram valve testing: Completed 8/84 SDV Water high level:
t M-4-1-81-021: Completed 6/84: M-4-2-81-021: Completed 5/85 Modification-related procedures were implemented by 7/85 RPS EPA: Completed 9/85 NRC letter dated 5/31/85 from D.B. Vassallo to D.L. Farrar accepted response.
ZD153
- , ., ~. ,, ,- ,. , , . - . , , . - , , , . - .
APPLICABILITY STATUS ComENTS GSX/fMPA No.) TITLE Items 4.5.2 & 4.5.3 - Reactor Trip All Plants C Ites 4.5.2:
75 (B093) CECO responded to this issue in letters dated Noveseer 5,1983 System Reliability - Test Alterna- and June 1, 1984. Testing of the backup scram valve was tives and Intervals (System functional Testing)
, tiated in 8/84. NRC letter dated 2/03/89 from T.M. Ross to H.E. Bliss accepted this response.
Item 4.5.3:
Plant specific analysis was performed in August,1985.
Endorsement of BWROG generic analysis (NEDC 30844 and NEDC 30851 P) was provided in letter from R. Stols to T.E. Murley dated May 1, 1990.
All BWRs C Comunitments required by IEB 82-03 (including Rev. 1),
86 (8084) long Range Plan for Dealing IEB 83-02, and G.L. 84-11 are complete. Those coeuritments which with Stress Corrosion have been superseded by GL 88-01 are also complete.
Cracking in BWR Piping IEB 82-03: Actions complete 12/82 IEB 83-02: Actions complete 2/84 (U1)
GL 84-11: Actions complete 7/84 (U1); 5/85 (U2)
(Inspections continued as required until superceded by IED 88-01.)-
All PWRs NA 93 (8098) Steam Binding of Auxiliary Feedwater Pumos All PWRs NA 99 (L817) RCS/RHR Suction Line Valve Interlock on PwHs Auxiliary Feedwater System ANO-1&2, Rancho NA 124 Reliability Seca, Prairie Island 1&2, Crystal River-3, Ft. Calhoun C Safety-related hydraulic snubbers replacement (with mechanical A-13 (8017) Snubber Operability Assurance - All Plants snubbers) was completed in 1985 as required by IEB 79-14.
Hydraulic Snubbers Hydraulic snubbers wre removed from Tech Specs by Amendments 115 (Unit 1) and 111 (Unit 2) approved by SER dated 02/22/89.
ID153
. . , _ . . . . . _ . _ . . . - . . = . , , .
p o .. " *
- GSIM MPA No.) . TITLE APPLICABILITY STATUS COP 9ENTS
, a A-13 (0022) Snubber Operability Assurance -
All Plants C Requirements for snubber operability, inspections, testing, and Mechanical-5nubbers monitoring are defined in Technical Specification 3.6.I/4.6.I.
Procedure (QTS 180-2) for mechanical snobber inspection was created in 05/82. - Procedure '(QAP 3~,0-6) nich reflects current Inservice Testing . Program requirements . for standard snobber testing methods was created in 06/89. In-place inservice
- testing of snubbers is MA to Station.
A-16 (D012) Steam Effects on BWR Core Oyster Creek NA Spray Distribution & NMP-1
'A-35 (8023) Adequacy of Offsite Power Systems All Plants C Second level undervoltage (degraded voltage) relays were installed under following modifications:
M-4-1-80-015 Completed 05/05/84 M-4-2-80-415, Completed 02/10/84 M-4-1-412-029. Completed 05/01/84 PS-4-2-82-029, Completed 12/20/83
- M-4-1/2-82-429. Completed 05/05/84 Changes were incorporated into Technical Specification Table 3.2-2. Table 4.2-1, 4.9. A.1, and 4.9.E.2.
B-10 Behavior of BWR Mark II: Containments All BWR Mark III MA Quad Cities is a Mark I Plant.
j- Plants 8-36 Develop Design. Testing and Mainten- mil Plants with NA Quad Cities received its operating licenses in 1972.
ance Criterie for Atmosphere Cleanup OL Applications System Air filtration and Adsorption After 4/1/80 Units for Engineered Safety Features Systems and for Normal Ventilation Systems B-63 (B045) Isolation of low Pressure Systems All Plants NC W.F. Naughton letter to D.G. Eisenhut dated 03/14/80 transmitted Conr,ected to the Reactor Coolant the requested information. Response was provided for GL 87-06 System Pressure Boundary by M.S. Turbak letter to NRC dated 06/11/87. No further actions were required.
.7.-
ID153
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