ML20006C176
Letter Sequence Other | |
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MONTHYEARML20006C1761990-02-0101 February 1990
[Table View]Accepts Util 891030 Response to Generic Ltr 89-16 Re Intention to Install Hardened Wetwell Vent at Plant by 930101,per BWR Owners Group Design Criteria to Be Approved by NRC Project stage: Other 1990-02-01 |
ML20006C176 | |
Person / Time | |
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Site: | Quad Cities |
Issue date: | 02/01/1990 |
From: | Ross T Office of Nuclear Reactor Regulation |
To: | Kovach T COMMONWEALTH EDISON CO. |
References | |
GL-89-16, TAC-74879, TAC-74880, NUDOCS 9002070035 | |
Download: ML20006C176 (4) | |
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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
[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 ML20217F6321999-10-0707 October 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations 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 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 ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted 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 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 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 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 ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 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 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) 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 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 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-99-122, 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-99-103, 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 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 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 05000254/LER-1999-002, Forwards LER 99-002-00 IAW 10CFR50.73(a)(2)(iv).Listed Commitments Contained in LER1999-06-18018 June 1999 Forwards LER 99-002-00 IAW 10CFR50.73(a)(2)(iv).Listed Commitments Contained in LER 1999-09-09 Category:NRC TO UTILITY MONTHYEARML20062G0401990-11-21021 November 1990
[Table view]Advises That fitness-for-duty Insp Scheduled for Wk of 910122-25.Written Policies/Procedures Will Be Reviewed ML20062G6911990-11-19019 November 1990 Advises That Schedule to Conduct Type a Containment Integrated Leak Rate Test for Fall 1990 Complies W/ Requirements of App J,Section III.A.6 & Applicable Tech Specs,Per Util ML20058E8171990-10-31031 October 1990 Requests Submittal of Review Re Adequacy of Initial Investigation of Allegation RIII-90-A-0002 within 30 Days ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058E6891990-10-26026 October 1990 Forwards Mgt Meeting Repts 50-254/90-19 & 50-265/90-19 on 900925.Meeting to Discuss NRC Concerns Re Containment Performance Testing at Plant ML20059N6801990-10-0505 October 1990 Forwards Insp Repts 50-254/90-14 & 50-265/90-14 on 900805- 0915 & Notice of Violation ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059J6371990-09-13013 September 1990 Forwards Enforcement Conference Repts 50-254/90-16 & 50-265/90-16 on 900905 & Notice of Violation.Technical Oversight in Case Indicates Need for Greater Care & Attention to Detail by Personnel ML20028G7711990-08-23023 August 1990 Forwards Resident Inspector Safety Insp Repts 50-254/90-12 & 50-265/90-12 on 900617-0804.No Violations Noted ML20059B6351990-08-23023 August 1990 Confirms 900911 Meeting W/Util in Glen Ellyn,Il to Discuss Rebaseline Program for Facility Updated Fsar.Discussion Should Include Progress & Overall Elements of Program ML20059A1771990-08-15015 August 1990 Forwards Safety Insp Repts 50-254/90-10 & 50-265/90-10 on 900605-0802.Violations Noted.Enforcement Conference Will Be Held in Region III Ofc W/Util ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20055F9191990-07-17017 July 1990 Forwards SER Confirming Util Responses to NRC Bulletin 88-010 & Suppl Re molded-case Circuit Breakers.Util Use of Replacement Breakers Until Fully Qualified Breakers Can Be Installed Acceptable Based on 891120 & 29 Submittals ML20055G4581990-07-13013 July 1990 Forwards Safety Insp Repts 50-254/90-11 & 50-265/90-11 on 900611-14.No Violations Noted ML20059M8791990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043E6391990-06-0707 June 1990 Forwards Fr Notice of Withdrawal of Application for Amend to Facility Ols,Per 900530 Telcon ML20043F7741990-06-0505 June 1990 Advises That 900412 Rev 58 to QA Topical Rept CE-1-A, Satisfies Requirements of 10CFR50,App B & Acceptable ML20043C5541990-05-29029 May 1990 Confirms Plan to Conduct Mgt Meeting on 900531 to Discuss General Topics of Mutual Interest ML20043B4701990-05-23023 May 1990 Advises of Written & Operating Exams During Requalification Program Evaluation Scheduled for Wk of 900910.Facility Should Furnish Approved Items Listed in Encl Ref Matl Requirements, 60 Days Prior to Exam Date ML20043B2811990-05-22022 May 1990 Provides Written Approval for 900519 Request for Temporary Waiver of Compliance & Emergency Tech Spec Change to Exclude Eight Containment Pathways from Requirement to Perform App J Type C Testing ML20043A6581990-05-17017 May 1990 Forwards SER Supporting Util 850823 & 900501 Responses to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability, On-Line Functional Testing of Reactor Trip Sys ML20043A8271990-05-15015 May 1990 Forwards Safety Insp Repts 50-254/90-06 & 50-265/90-06 on 900318-0428 & Notice of Violation ML20042G7621990-05-0909 May 1990 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 900606.Map of Area Including Time & Location Where Exams Will Be Administered Also Encl ML20042G8721990-05-0909 May 1990 Forwards FEMA Final Rept Re Performances of State & County Emergency Responders During 1988 Emergency Preparedness Exercise at Plant.Facility Offsite Radiological Emergency Preparedness Considered Adequate ML20042G1161990-05-0404 May 1990 Accepts Util 891027 60-day Response to Generic Ltr 88-20, Individual Plant Exams. NRC Anticipates That Any Possible Addl Analysis or Reporting Requirements,Such as External Events,Will Not Have Adverse Effect on Util Schedule ML20042E8851990-05-0101 May 1990 Informs That Rl Dickherber Submitted Answer to Orders Issued to Util & Dickherber on 900413.Requests Util Provide Views Re Adequacy of Company Controls for Work Hours in View of Info Provided by Dickherber at Page 13 of Answer ML20042E7621990-04-27027 April 1990 Requests Schedule for Meeting Commitments,Including Results of Fracture Mechanics Analyses,Results of Boat Sample Metallurgical Exams & Plan for Future Insp for All BWRs That May Be Susceptible to Cracking within 7 Days of Ltr Date ML20042E8941990-04-20020 April 1990 Forwards Safety Insp Repts 50-456/90-11,50-457/90-14, 50-454/90-13,50-455/90-12,50-237/90-14,50-249/90-13, 50-373/90-07,50-374/90-08,50-254/90-07,50-265/90-07, 50-295/90-10 & 50-304/90-11 on 900220-0404 ML20034B6541990-04-12012 April 1990 Forwards Exam Rept 50-254/OL-90-01 Administered During Wk of 900319 ML20042E4211990-04-10010 April 1990 Forwards Safety Insp Repts 50-254/90-05 & 50-265/90-04 on 900326-30.No Violations Noted ML20033G9731990-04-0404 April 1990 Forwards Safety Insp Repts 50-254/90-02 & 50-265/90-02 on 900128-0317 & Notice of Violation ML20012F3771990-03-30030 March 1990 Forwards Safety Insp Rept 50-265/90-05 on 900220-0322.No Violations Noted ML20012F5801990-03-23023 March 1990 Forwards Safeguards Insp Repts 50-254/90-04 & 50-265/90-03 900312-16.No Violations Noted ML20012A0231990-02-27027 February 1990 Informs of Organizational Changes within Div of Reactor Projects,Project Directorate III/2.Change Reassigned Project Managers to Listed Facilities ML20011F5931990-02-23023 February 1990 Forwards Order Modifying Licenses DPR-29 & DPR-30,to Immediately Remove Rl Dickherber from Licensed Activities, Per 10CFR50.Action Taken Because of Willful Violation of Commission Requirements Re Improper Movement of Fuel ML20006E7791990-02-13013 February 1990 Forwards Safety Insp Repts 50-254/89-28 & 50-265/89-28 on 891217-900127.Notice of Violation Will Not Be Issued to Encourage & Support Licensee Initiatives for Self Identification & Correction of Problems ML20006E1511990-02-12012 February 1990 Advises That 891201 Rev 57 to QA Topical Rept CE-1-A Consistent W/Provisions of 10CFR50.App B & Acceptable ML20011E5351990-02-0606 February 1990 Confirms Plans Discussed Between R Stols & D Jones to Have Meeting at Plant on 900222 to Present Initial SALP 8 Rept ML20034B5851990-02-0202 February 1990 Forwards Initial SALP 8 Repts 50-254/89-01 & 50-265/89-01 for Oct 1988 - Nov 1989.Conduct of Nuclear Activities in Connection W/Plant Satisfactory.Overall Improvement in Performance Noted.Problems W/Procedural Adequacy Noted ML20006C1761990-02-0101 February 1990 Accepts Util 891030 Response to Generic Ltr 89-16 Re Intention to Install Hardened Wetwell Vent at Plant by 930101,per BWR Owners Group Design Criteria to Be Approved by NRC ML19354D9651990-01-18018 January 1990 Forwards Page 3 of Exam Rept 50-254/OL-89-04 for Both Units to Ensure All Parties Have Complete Rept ML20005G5711990-01-12012 January 1990 Advises That Licensee 891107 IGSCC Insp Plan for Weld Meets Guidelines of Generic Ltr 88-01 & Acceptable ML19354D9871990-01-11011 January 1990 Requests Updated Cost Estimate for Labor & Matls for Installation of Addl Circuitry at Plant Emergency Operations Facility Bldg for Contingency Telecommunications ML19354D9761990-01-10010 January 1990 Forwards Safety Insp Repts 50-254/89-25 & 50-265/89-25 on 891030-1214 & Notice of Violation.Written Response Required Re Procedure Revs,Program Enhancements & Staff Training for Rebaseline Project to Comply w/10CFR50.59(B) ML20005F1701990-01-0909 January 1990 Forwards Safety Evaluation Concluding That Use of Mobil Greases for Limitorque Actuators as Substitute for Currently Used Exxon Greases Acceptable,In Response to NRC Diagnostic Evaluation Team Aug 1986 Insp Findings ML20005F2051990-01-0808 January 1990 Forwards Reactive Insp Rept 50-254/89-27 on 891215.No Violations Noted.Nrc Concerned W/Quality of Work Performed by Contract Employees & Lack of Direct Licensee Control of Work Activities.Meeting Scheduled on 900111 W/Util ML20005F2151990-01-0808 January 1990 Forwards Safety Insp Repts 50-254/89-26 & 50-265/89-26 on 891105-1216 & Notice of Violation ML20005G4941990-01-0505 January 1990 Forwards Exam Rept 50-254/OL-89-04 Administered During Wk of 891113-17.Programmatic Concerns Noted Re Improperly Freezing Exam Matl 6 Months Prior to Exam ML20005D9731989-12-26026 December 1989 Forwards Conclusions of Regulatory Effectiveness Review (Rer) on 891113-17.Elements of Plant Safeguards Program Reviewed During Rer Generally Outstanding.Encl Withheld (Ref 10CFR73.21) ML20005G3621989-12-18018 December 1989 Forwards Revised NRC Forms 396 & 398 Re Certification of Medical Exam by Facility Licensee & Personal Qualification statement-licensee,respectively,reflecting Changes of Operator Licensing Process 1990-09-25 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217F6321999-10-0707 October 1999
[Table view]Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations 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 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 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 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 ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted 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 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 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) 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 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 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195K1411999-06-16016 June 1999 Forwards Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety ML20195J6401999-06-14014 June 1999 Discusses Licensee 990331 Remediation Plan for Welds Susceptible to Intergranular Stress Corrosion Cracking at Quad Cities Nuclear Power Station,Unit 1 & Requests Licensee Address Concerns Discussed & Propose Plan to Implement C/A ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206S3981999-05-14014 May 1999 Forwards Insp Repts 50-254/99-06 & 50-265/99-06 on 990307-0420.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206S1131999-05-13013 May 1999 Informs That on 990505 NRC Staff Held Planning Meeting for Plant to Identify Insp Activities at Facility Over Next 6 to 12 Months ML20206S1561999-05-12012 May 1999 Informs of Plans to Conduct Public Meeting on 990608 in Rock Island,Il to Present Planned Changes to NRC Regulatory Processes & Pilot Plant Program for Quad Cities Station ML20206N9621999-05-11011 May 1999 Forwards Insp Repts 50-254/99-08 & 50-265/99-08 on 990419-23.No Violations Noted.Insp Examined Efforts in Addressing Actions Requested in NRC GL 96-01, Testing of Safety Related Logic Circuits ML20206P8511999-05-11011 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions Will Be Examined During Future Insp ML20206P6811999-05-11011 May 1999 Confirms Discussion Between Members of Staff to Have Mgt Meeting at Qcs on 990608 in Training Bldg,Meeting Open to Public.Purpose of Meeting to Discuss Qcs Performance Described in PPR ML20206F3221999-05-0404 May 1999 Second Final Response to FOIA Request for Documents.Forwards Documents Listed in App B Maintained in PDR Under Request Number 99-134.Documents in App C Being Released in Part (Ref FOIA Exemptions 6) ML20206Q5701999-05-0303 May 1999 Informs That on 990420-21 NRC Senior Managers Met to Evaluate Nuclear Safety Performance of Operation Reactors, Fuel Cycle Facilities & Other Matl Licenses ML20206E0621999-04-30030 April 1999 Refers to Ceco Which Committed to Perform Future FW Nozzle Insps in Accordance with BWROG Alternate BWR FW Nozzle Insp Requirements Rept.Informs of Misunderstanding Re Condition 6 Implications in SER Which Approved Rept ML20205T4281999-04-22022 April 1999 Informs That Encl FEMA Correspondence Was Received on 990322,transmitting FEMA Evaluation Rept for 981007 Annual Medical Drill Conducted at Rock Island County for Quad City Nuclear Power Station.No Violations Were Noted ML20205Q5191999-04-16016 April 1999 Forwards SER Concluding That Quad Cities Nuclear Power Station,Unit 1 Can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205P4641999-04-15015 April 1999 Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP ML20205P0591999-04-14014 April 1999 Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely ML20205N9541999-04-0909 April 1999 Forwards Insp Repts 50-254/99-03 & 50-265/99-03 on 990308-12.No Violations Noted.Longstanding Materiel Condition Issues Continue to Be Problem,However Progress Had Been Made in Listed Areas ML20205J5691999-04-0707 April 1999 First Partial Response to FOIA Request for Documents. Documents Listed in App a Being Released in Their Entirety ML20205F8031999-04-0202 April 1999 Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants ML20205J2891999-04-0101 April 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990121-0306.Violations Identified Involving Failure to Follow Station Procedures for Use of Shutdown Cooling & Failure to Follow Station out-of-svc Tagging Procedures ML20196K9001999-03-31031 March 1999 Forwards Radiation Protection Insp Repts 50-254/99-07 & 50-265/99-07 on 990309-12.No Violations Were Identified.Insp Consisted of Review of Solid Radwaste Processing & Control Program & Radioactive Matls Shipping Program ML20205G5811999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990201 to Develop Integrated Understanding of Safety Performance. Overall Performance of Plant Acceptable.Plant Issues Matrix & Insp Plan Encl ML20204E0611999-03-18018 March 1999 Discusses Review of Rev 8Q to Portions of Plant Emergency Plan Site Annex ML20207L7511999-03-15015 March 1999 Informs That Staff Offers No Objections to Util 990121 Change to Licenses DPR-29 & DPR-30,App a TSs Bases Sections 3/4.10.K & 3/4.10.L.Changes Clearly Identifies That RHR Scs Not Designed to Be Throttled Sufficiently to Maintain Rc ML20204B0921999-03-12012 March 1999 Discusses Closeout of NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Hrps, for Plant,Units 1 & 2 1999-09-09 |
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' UNITED STATES'-
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' NUCLEAR REGULATORY COMMISSION
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' WASHINGTON. D. C. 20066
,W February 1,1990 i
.x Docket Nos. 50-254 and 50-265 Thomas J. Kovach 4
Nuclear Licensing Manager I
Commonwealth ~ Edison Company-Suite 300 U
OPUS West III
-1400 OPUS Place Downers Grove, Illinois 60515 1
Dear Mr. Kovach:
SUBJECT:
MARK I CONTAINMENT HARDENED WETWELL VENT GENERIC LETTER 89-16 (TAC NOS 74879 AND 74880)
Reference:
(a) LetterfromM.H. Richter (Ceco)toU.S.NRCdated October 30, 1989 InresponsetoGenericLetter(GL)89-16,CommonwealthEdisonCnmpany'(CECO) d notified the Nuclear Regulatory Comission (NRC) of its intention to install a-i
~hardenedwetwell'ventattheQuadCitiesNuclearPowerStation(QCNPS), Units a
1 and'2.
Inl reference (a), CECO comitted to provide hardened vents at QCNPS
- by January 1,:-1993 in accordance with Boiling Water Reactors Owners Group (BWROG) design criteria to~be approved'by the NRC.
-The NRC staff reviewed reference (a), and determined that Ceco's-intentions to
^
--install a hardened wetwel1~ vent'at QCNPS under the-prov_isions of 10 CFR:50.59
.is acceptable. Since the staff views CECO's stated intentions to be a firm comitment to install the requisite modification, the NRC will not' proceed with backfit analyses for QCNPS.
If the staff's: understanding is not con-
+-
sistent with Ceco's intentions, you are requested to provide a detailed explanation to support deviations from the staff's understanding of:comit-mentsmadeninreference(a).
'The use'of results from Individual Plant Examinations (IPE) to develop f
' supplemental' criteria for the vent modification design is acceptable provided that it does not, in any way, affect the comple+. ion schedule or Ceco's o
comitment to make the requisite modifications under the provisions of j
- 10 CFR 50.59.
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- . Thomas J. Kovach February 1,1990' s
b Ceco's schedule for-completion of' hardened wetwel1~ vent modifications by.
January 1,1993 is acceptable. Any changes to this schedule must be discussed with the staff prior to their implementation, and the final schedule must not-
- extend beyond January 1993.
Sincerely,
~-
ier
. Ross, Project Manager Project Directorate III-2 Division of Reactor Projects -'III, IV, Y and Special Projects p-Office of Nuclear Reactor Regulation ec:
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.- / Mr'.1 Thoma's J. Kovach -
- Quad Cities Nuclear Power Station i
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- Consnonwealth Edison Company-Units 1 and 2-
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~cc:.
1 Mr. Stephen E. Shelton s
Vice President 1
Iowa-Illinois Gas and 1
Electric Company P. 0. Box 4350 '
~
Davenport, Iowa 52808 4
Michael I'. Miller, Esq.
i
- Sidley and Austin
One First National Plara' Chicago,. Illinois 60603
.Mr. Richard Bax=
1 5tation Manager i
Quad Cities Nuclear Power Station l'
22710 206th Avenue North 0
Cordova, Illinois 61242 L
Resident Inspector L
U. S. Nuclear Regul'atory Consnission 22712 -206th Avenue North 3
Cordova,cI111nois 61242
=
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- Chairman.
Rock Island County: Board of Supervisors 1504 3rd Avenues
' Rock Island County: Office Bldg..
. Rock Island, Illinois 61201 l
Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 i
L
-Regional' Administrator, Region III l..
U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. d4 l;
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Glen' Ellyn, Illinois-60137 4
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. February 1,(1990 ll;4
- f,ThomasJ.Kovach-r._ <
_ Ceco's schedule for completion of hardened wetwell vent modifications by January 1, 1993 is acceptable. Any changes to this schedule must be discussed-with the staff prior'to their implementation. and-the final schedule must not L
extend beyond January 1993.
Sincerely,
/
Rh 4Vf Wd Thierry M. Ross,. Project Manager-Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation L,
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