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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
[Table view] |
See also: IR 05000254/1999001
Text
o
E '
.
June 14, 1999
l
.
Mr. Oliver D. Kingsley
l President, Nuclear Generation Group
1
Commonwealth Edison Company
ATTN: Regulatory Services
Executive Towers West 111
1400 Opus Place, Suite 500
Downers Grove,IL 60515 .
1
l
SUBJECT: NOTICE OF VIOLATION (QUAD CITIES INSPECTION
REPORT 50-254/99001(DRP); 50-265/99001(DRP))
Dear Mr. Kingsley:
This will acknowledge receipt of your letter dated May 12,1999, in response to our
letters dated February 17,1999, and April 1,1999, transmitting a Notice of Violation associated
with inspection Report 50-254/98023(DRP); 50-265/98023(DRP) and an additional example of
that violation associated with inspection Report 50-254/99001(DRP); 50-265/99001(DRP). We
1
have reviewed your corrective actions and have no further questions at this time. These
corrective actions will be examined during future inspections.
Sincerely,
/s/ M. A. Ring
Mark Ring, Chief
Reactor Projects Branch 1
Docket Nos. 50-254; 50-265
License Nos. DPR-29; DPR-30
See Attached Distirbution
DOCUMENT NAME: G:\ quad \qua98023.ty
To receive a copy of thle document, indicate in the box 'C' = Copy without attachrnent/ enclosure 'E' = Copy with attachrnent/ enclosure
"N" = No copy
OFFICE Rlli ,
Al l l l
NAME Ring:coM
DATE 06/M/99
OFFICIAL RECORD COPY
9906180186 990614 9
PDR ADOCK 05000254
G PM g
a
,
.
1
O. Kingsley -2-
l
ec: D. Helwig, Senior Vice President
H. Stanley, PWR Vice President j
.;
i C. Crane, BWR Vice President
R. Krich, Vice President, Regulatory Services
- DCD - Licensing I
J. Dimmette, Jr., Site Vice President
G. Barnes, Acting Quad Cities Station Manager
C. Peterson, Regulatory Affairs Manager
cc w/Itr did 5/12/99: M. Aguilar, Assistant Attorney General <
State Liaison Officer, State of Illinois
State Liaison Officer, State ofIowa
Chairman, Illinois Commerce Commission
W. Leech, Manager of Nuclear
MidAmerican Energy Company
Distribution w/ltr dtd 5/12/99:
Project Mgr., NRR
J. Caldwell, Rlli
B. Clayton, Rill
SRI Quad Cities
DRP
DRS
RlliPRR
PUBLIC IE-01
Docket File
GREENS
ff
390015
' "
i.o m m onsse.uoi a r..n i .,nn u m
tjuad Enses t cocrannu 'ian .n
22 in auc,oi w enue s..o
( '4 H dO% J. ll. (>l 212 'I til
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COITtEd i
SVP-99-096
May 12,1999
)
U. S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, D C 20555
Quad Cities Nuclear Power Station, Unit 1 and 2
Facility Operating License Nos. DPR-29 and DPR-30
NRC Docket Nos. 50-254 and 50-265
Subject: Supplemental Reply to Notice of Violation 50-254/98023-01 Concerning
the Out-of Service Program
References: (1) Letter from S. A. Reyr. olds (USNRC) to O. D. Kingsley (Comed),
dated February 17,1999," Notice o' Violation and Ouad Ci'ies !
Inspection Report 50-254/98023(DRP); 50-265/98023(DRP)"
(2) Letter from J. P. Dimmette, Jr.(Comed), SVP 99-055 to USNRC,
dated March 19,1999," Response to Notice of
Violation 50-254/98023-01 Concerning the Out-of-Service
Program"
(3) Letter from S. A. Reynolds (USNRC) to O. D. Kingsley (Comed),
dated April 1,1999," Quad Citics Inspection Report
50-254/99001(DRP); 50-265/99001(DRP)"
i
Enclosed is a supplement to the Commonwealth Edison (Comed) Company reply to
Notice of Violation (NOV) 50-254/98023-01 issued to Quad Cities Nuclear Power
Station and transmitted in Reference (1). The reply to the specific violation was
included in Reference (2).
As discussed in Reference (3), Comed is supplementing the reply to NOV
50-254/98023-01 to discuss a February 18,1999, Out-of-Service (OOS) error. This
supplement discusses the reason for the OOS error and commits to further corrective
actions from that event. This reply also provides a status of previous commitments and
describes new initiatives to improve performance with regard to the OOS process and
human performance in general.
U/W 18 y)ge
s i nn.,m t..mium f
,.
.
May 12,1999
U. S. Nuclear Regulatory Commission
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Comed is committing to the following additional actions in response to the February 18,
1999, OOS error:
- The expectation for operating components froin standard locations will be included
in OAP 0300-02, " Conduct of Shift Operations," by June 11,1999. A Daily Order
Book entry has communicated to Operations personnel the expectation to operate
components from the standard location whenever possible. If circumstances
prevent operating a component from the standard location, the standard location
must be checked to verify that operation of the component is not prohibited.
- QCAP 2200-03, " Planning, Scheduling Operating Cycle Work," will be revised by
June 11,1999, to ensure that appropriate reviews are documented for priority A
and B1 schedule additions to verify that plant conditions support the activity. The
expectation has been reinforced with the Operations planning group that their
review of the daily schedule (including work additions) ensures the plant lineup is
correct for the performance of each scheduled task.
Any other actions described in the submittal represent intended or planned actions by
Comed. They are described for information and are not regulatory commitments.
Should you have any questions concerning this letter, please contact Mr. Wally Beck,
Acting Regulatory Assurance Manager, at (309) 654-2241, extension 3100.
Respectf y,
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el P. Dimmette, Jr.
Ite Vice President
Quad Cities Nuclear Power Station
Attachment: Supplemental Response to NOV 50-254/98023-01
cc: Regional Administrator-NRC Region til
NRC Senior Resident inspector-Quad Cities Nuclear Power Station
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Att:chment
SupplImental RIply t3 NOV 50-254/98023 01 ;
Page 1 of 4
In Reference (3) the NRC noted that, if necessary, our response to NOV 50-254/98023-01
should be modified to include corrective actions sufficient to address the Out-of-Service (OOS)
tagging errors identified in Reference (3).
On February 18,1999, during the performance of a logic test surveillance Operations personnel
operated a breaker that was OOS to protect equipment. The test procedure had recently been
revised and had been added to the schedule without recognizing that the revised test would
require manipulation of a component that was OOS. During the performance of the surveillance,
the critical task coordinator and an electrician correctly identified the breaker cubicle for 2-1001-
47, RHR Shutdown Cooling Outboard Suction isolation Valve, but did not notice an OOS card
hanging from the breaker handle. The electrician opened the cubicle door, obscuring the OOS
card and proceeded to install jumpers as directed by the surveillance. After the jumpers were
installed, an operator was dispatched to assist and was requested to close the breaker per the
surveillance. The operator verified that he was on the correct component by checking the label
on the cubicie door, however, the jumpers that had just been installed prevented the door from
fully closing and the OOS card on the breaker handle remained obscured. The operator then
operated the breaker from inside the cub.Je. After the breaker was operated, the critical task
coordinator saw the OOS card and directed the operator to reopen the breaker. The root
causes of this event were inattention to detail, inadequate precautions established for operating
components from non-standard locations (inside the cubicle), and inadequate review of the
schedule to determine that the OOS needed to be cleared to perform the test.
In the response to NOV 50-254/98023-01, Comed discussed that previous corrective actions to
correct OOS problems had not been fully effective. Previous corrective actions for OOS l
problems were focused on individual events and departments and did not fully take into account 1
the broader issues of human performance. Human performance problems were due to a lack of
adequate management oversight and reinforcement of the standards and expectations at the
lowest levelin the organization.
Two new initiatives will supplement the plans previously discussed in the March 19,1999, letter
to improve human performance at Quad Cities.- One initiative is the establishment of a
multidiscipline Human Performance High Impact Team whose chartered purpose is to prevent
human error through education, behavioral changes, and program and process improvements.
This team includes individuals at various levels from various departments throughout the
station, who will work to !dentify and understand human performance issues and solutions and
will facilitate change throughout the station to improve human penormance. On April 6,1999, 1
the BWR Vice President and Quad Cities Site Vice President approved the Human Performance ;
High Impact Team Charter.
The second initiative is rigorous implementation of the new Nuclear Generating Group (NGG)
Self-Assessment Procedure to improve Quad Cities self-criticism and the effectiveness of
processes and corrective actions. On April 14,1999, the Acting Station Manager approved a
plan for implementation of the NGG Self-Assessment Procedure. This included the designation
of two Self-Assessment t_ine Managers who will work with Line Manager Department Heads to
- implement an improved Self-Assessment Program at Quad Cities Nuclear Power Station. The
first quarter 1999 Quarterly Self-Assessment, performed in accordance with the new NGG j
Self Assessment Procedure, is scheduled to be complete by June 1,1999. The second quarter l
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- 1999 Quarterly Self-Assessment is scheduled to be complete by July 17,1999.
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' SupplImentIl RIply to NOV 50-254/98023-01
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-CORRECTIVE ACTIONS THAT HAVE BEEN TAKEN TO AVOID FURTHER VIOLATION
The following corrective actions were discussed in the March 19,1999, letter to the NRC and
were completed prior to the issuance of that letter.
. . On January 29,1999, a new policy, OCPP 0110, " Event Review Board," was implemented
to formalize the Senior Management Review of Human Performance events.
- On February 25-26,1999, the Quad Cities Station Site Vice President and Station Manager
issued letters to all employees reinforcing the need for high standards in procedural
adherence and in the conduct of Heightened Level of Awareness briefings. This expectation
was rolled out to the management team on March 3,1999.
- On March 12,1999, stand-down meetings were conducted by Senior Management
throughout the Comed Nuclear Generation Group. The stand-down meetings addressed
the need for improved human performance and stressed the importance of personal
accountability. Additionally, individual departments met to reinforce and discuss the
standards for prevention of errors. For applicable departments, this included discussion of
proper zone of protection for OOS activities.
- On March 17,1999, INPO representatives presented a four-hour course titled " Human
Performance, a Management Perspective." This was conducted at Quad Cities Station und
attended by Senior Management and other selected station personnel.
The following corrective actions were discussed in the March 19,1999, letter to the NRC and
completed following the issuance of that letter. ;
- Prior to March 30,1999, items No. 28 and No. 29 of the Station Configuration Control Action
Plan were completed conceming refreshar training on OOS acceptance and walkdown
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safety verification checklists for maintenance personnel.
= Prior to April 9,1999, the Maintenance Manager met with and communicated with the
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department First une Supervisors (FLS) to reinforce the following:
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. Adherence to procedures
. Maintenance control of work
e Safe work practices '
j . *- Personal Accountability
. Prior to April 10,1999, the Site Vice President, Station Manager, and Operations Manager
j held accountability sessions with each Operating Shift Manager and his management crew.
The accountability sessions included discussions on adherence to standards, the need for
change, and how that change will be sustained to achieve improved operator performance.
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Supplim:ntr.1 Rrply to NOV 50-254/98023-01
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- Prior to April 10,1999, an independent multidiscipline team completed a review of previous
corrective etctions associated with station PIF's, root cause trend reports, LER's, and
responses to NOVs related to OOS problems. The review was performed to ensure
adequate implementation of previous corrective actions and compliance to the station's
OOS process prior to the Unit 1 planned outage (01PO2) beginning April 10,1999. The i
team identified that the OOS process was sound but was not properly implemented due to
personnel errors.
- On April 24,1999, Nuclear Oversight (NO) completed an assessment performed during
Q1PO2 of preparation of OOS and adherence to the OOS process. The assessors used a
combination of direct field observations and paperwork reviews and found the OOS process
and the implementation of the OOS process to be acceptable.
The following additional corrective actions were taken in respcnse to the February 18,1999,
OOS error.
- An Event Review Board was conducted for the February 18,1999, OOS error described
above.
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. On March 15,1999, the following expectation was communicated to Operations through a
Daily Order Book entry.
Always operate components from the standard location whenever possible. If
circumstances prevent operating a component from the standard location, obtain Unit j
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Supervisor permission prior to the operation and check the standard location to verify
that operation of the component is not prohibited (i.e. OOS) or restricted (i.e. Caution
Card).
. - Prior to April 2,1999, the following expectation was reinforced with the Operations planning
group.
The Operations planning group reviews the daily schedule (including work additions) to
ensure the plant lineup is correct for the performance of each scheduled task. Emphasis
will be placed on tasks that are scheduled to be performed in a different plant mode or
condition than usually performed, or a new procedure, er a procedure that has been
significantly revised and not performed since it was revised.
CORRECTIVE ACTIONS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATION
The following corrective actions were discussed in the March 19,1999, letter to the NRC and
committed to in that letter.
- The above mentioned multidiscipline team will perform a self-assessment in accordance ,
with the station's program for self-assessments in May 1999. This review will be conducted j
to ensure compliance to the station's OOS program is being properly maintained. (Action
Tracking No. 0000434903)
- An effectiveness review will be conducted by July 31,1999, to assess the effectiveness of
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corrective actions from OOS trend PIF Q1999-00045.
(Action Tracking No. 0000504901)
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Supplim ntal R: ply to NOV 50-254/98023-01
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e' NO will perform a follow up assessment in September,1999, to assess the station's I
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compliance with the OOS program and effectiveness of the corrective actions. (Action
Tracking No. 0000434905)
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The following additional corrective actions will be taken in response to the February 18,1999, '
OOS error.
. The expectation for operating components from standard locations will be included in OAP
0300-02, Conduct of Shift Operations, by June 11,1999. (Action Tracking No. 0000551401)
= QCAP 2200-03, Planning, Scheduling Operating Cycle Work, will be revised by June 11,
1999 to ensure that appropriate reviews are documented for priority A and B1 schedule
additions and the Operations planning group review expectation stated above is
documented in these reviews. (Action Tracking No. 0000551403)
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