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| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 5 | | | page count = 5 |
| | | project = TAC:MA4174 |
| | | stage = Other |
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| The purpose of this letter is to inform you that we find acceptable your assessment of the two old and one new flaw indications on the recirculation system piping. We agree with your ! | | The purpose of this letter is to inform you that we find acceptable your assessment of the two old and one new flaw indications on the recirculation system piping. We agree with your ! |
| assessment that the plant can be safely operated for the next operating cycle of 24 months with indications present. | | assessment that the plant can be safely operated for the next operating cycle of 24 months with indications present. |
| In a letter dated November 24,1998, Commonwealth Edison Company (Comed) stated that | | In a {{letter dated|date=November 24, 1998|text=letter dated November 24,1998}}, Commonwealth Edison Company (Comed) stated that |
| ! seven welds were found with indications during this outage (Q1R15), four of which were new , | | ! seven welds were found with indications during this outage (Q1R15), four of which were new , |
| indications. Welds 02AD-F12 and 02AS-S4 with indications identified the last outage showed ! | | indications. Welds 02AD-F12 and 02AS-S4 with indications identified the last outage showed ! |
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MONTHYEARML20196F5221998-12-0202 December 1998 Informs That NRC Finds Util Assessment of Two Old & One New Flaw Indications on Recirculation Sys Piping Acceptable.Nrc Agrees with Assessment That Plant Can Be Safely Operated for Next Operating Cycle of 24 Months with Indications Present Project stage: Other 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 Project stage: Approval 1998-12-02
[Table View] |
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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:OUTGOING CORRESPONDENCE
MONTHYEARML20217F6321999-10-0707 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 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 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 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 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 ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted 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 ML20207H6171999-06-14014 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-254/99-01 & 50-265/99-01,per 990217 & 0401 Ltrs Which Transmitted NOV Associated with Insp Repts 50-254/98-23 & 50-265/98-23 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 1999-09-09
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.-. . . ~.. - . -.- .- .- - - . -. _
_ ratg h)-2SY i
g & UNITED STATES
. g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 f a f
December 2, 1998 i
Mr. Oliver D. Kingsley, President Nuclear Generation Group {
Commonwealth Edison Company Executive Towers West til 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
EVALUATION OF INDICATIONS ON RECIRCULATION SYSTEM PIPING - QUAD CITIES NUCLEAR POWER STATION, UNIT 1 (TAC NO. MA4174)
Dear Mr. Kingsley:
The purpose of this letter is to inform you that we find acceptable your assessment of the two old and one new flaw indications on the recirculation system piping. We agree with your !
assessment that the plant can be safely operated for the next operating cycle of 24 months with indications present.
In a letter dated November 24,1998, Commonwealth Edison Company (Comed) stated that
! seven welds were found with indications during this outage (Q1R15), four of which were new ,
indications. Welds 02AD-F12 and 02AS-S4 with indications identified the last outage showed !
no change in flaw size and their previous flaw evaluation continues to be applicable. One new indication on weld 02BS-F4 was found this outage that did not meet the criteria of Section XI of l the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),1989 Edition, for continued operation without evaluation. Comed has determined this weld to be acceptable and provided flaw evaluations justifying continued operation. The flaw .
evaluation was performed in accordance with the methodology and acceptance criteria i specified in subarticle IWB-3640 of Section XI, ASME Code,1989 Edition. The remaining four indications on welds 02AD-F8,02BS-F7,02AS-F9 and 02BS-F14, each had a weld overlay repair applied in accordance with ASME Code Case N-504,"Altemative Rules for Repair of Class 1, .?, and 3 Austenitic Stainless Steel Piping,Section XI, Division 1." In telephone discussions on November 19,24, and 30, the NRC staff discussed these indications and your assessment of them.
Our conclusion that continued operation is acceptable for the next operating cycle of 24 months is based on your acceptable fracture mechanics analysis, upon your inspection data that show that the two flaw indications have existed since the previous outage without any apparent change in size or location, and the application of weld overlay repairs on the remaining four flawed welds. We also note that Comed will reclassify all 28-inch diameter recirculation system welds in Unit 1 that were treated with the Induction Heating Stress improvement process (IHSI) ,
i
\
9812070059 981202 7 Q(C ,o i
PDR ADOCK 05000254 P PDR W FM CENTE3 08PY
'.A ,
c O. Kingsley from Category C to Category D as defined in Generic Letter 88-01 and continue to inspect the remaining welds treated with the IHSI process to the Category D frequency. Our complete safety evaluation will be transmitted in a letter to follow.
Sincerely,
, 2 Robert M. Pulsifer, Project Manager Project Directorate 111-2 Division of Reac+or Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. 50-254 cc w/enci: See next page r
4 O. Kingsley December 2, 1998 from Category C to Category D as defined in Generic Letter 88-01 and continue to inspect the remaining welds treated with the IHS! process to the Category D frequency. Our complete safety evaluation will be transmitted in a letter to follow.
Sincerely, 1
l ORIG. SICJMD BY l Robert M. Pulsifer, Project Manager l Project Directorate 111-2 l Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation 1
Docket No. 50-254 l
cc w/ encl: See next page DISTRIBUTION:
pmu PUBLIC PDill-2 r/f EAdensam, EGA1 SRichards I CMoore RPulsifer OGC,015B18 ACRS, T2E26 MRing, Rill ESull1 van DOCUMENT NAME: G:\PD3-2\CM\ QUAD \QC4174.LTR Ta receive a copy of this document,indiceteAthe tpx: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy l OFFICE PM:PDill-2 C 1A:$ 11- 2 6EMCB fa D:PDill-2 C4 NAME RPULSIFER:C ONIOORE ESULLIVAN fGb SRICHARDS 5tF l DATE 12/ / /98 12/ 1 /98 g j2/ / /98 /) 12/ 2.198 j OFFICIAL RECORD COPY !
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O. Kingsley . . Quad Cities Nuclear Power Station . !
Commonwealth Edison Company Units 1 and 2 i
cc:
e l Michael 1. Miller, Esquire Vice President- Law and i l Sidley and Austin. Regulatory Affairs One FL3t National Plaza l MidAmerican Energy Company 1 Chicago, Illinois 60603 One River Center Place .
.106 E. Second Street Commonwealth Edison Company P.O. Box 4350 Quad Cities Station Manager Devenport, Iowa 52808 1 22710 206th Avenue N. i Cordova, Illinois 61242-9740 Document Control Desk-Licensing !
Commonwealth Edison Company !
U.S. Nuclear Regulatory Commission 1400 Opus Place, Suite 400 ;
Quad Cities Resident inspectors Office Downers Grove, Illinois 60515 i 22712 206th Avenue N.
Cordova, Illinois 61242 ' Mr. David Helwig l- Senior Vice President t L
Chairman Commonwealth Edison Company !
l Rock Island County Board Executive Towers West lli f of Supervisors 1400 Opus Place, Suite 900 1504 3rd Avenue Downers Grove, IL 60515 i Rock Island County Office Bldg. :
Rock Island, Illinois 61201 Mr. Gene H. Stanley PWR's Vice President Illinois Department of Nuclear Safety Commonwealth Edison Company ,
Office of Nuclear Facility Safety Executive Towers West lll !
1035 Outer Park Drive 1400 Opus Place, Suite 900 !
Springfield, Illinois 62704 Downers Grove,IL 60515 1
Regional Administrator Mr. Steve Perry U.S. NRC, Region lli BWR's Vice President 801 Warrenville Road Commonwealth Edison Company l Lisle, Illinois 60532-4351 Executive Towers West 111 .
1400 Opus Place, Suite 900 l l William D. Leach Downers Grove,IL 60515 Manager- Nuclear L MidAmerican Energy Company Mr. Dennis Faner l 907 Walnut Street Regulatory Services Manager l- P.O. Box 657 Commonwealth Edison Company l Des Moines, Iowa 50303 Executive Towers West lli 1400 Opus Place, Suite 500 Commonwealth Edison Company Downers Grove, IL 60515 Site Vice President- Quad Cities 22710 206th Avenue N.
Cordova, Illinois 61242-9740 l
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li O. Kingsley Quad Cities Nuclear Power Plant .
I Commonwealth Edison Company Units 1 and 2 Ms. Irene Johnson, Licensing Director p Nuclear Regulatory Services l Commonwealth Edison Company l Executive Towers West 111 l 1400 Opus Place, Suite 500 l- Downers Grove,IL 60515 Commonwealth Edison Company Reg. Assurance Supervisor- Quad Cities L
22710 206th Avenue N.
Cordova, Illinois 61242-9740 Mr. Michael J. Wallace Senior Vice President Commonwealth Edison Company Executive Towers West lil 1400 Opus Place, Suite 900 Downers Grove,IL 60515 l
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