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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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. . - . ~ . - ~ - . - _ . . . _ _ . - _ _ - - . _ . _ _ _ _ . _ . . . - ~ . _ - . - _ . - - _ . . - . . - -
. r y ,
t d a ne uNfTED STATES g
-8 y NUCLEAR RECULATORY COMM:CSION Q)
REGION ill i
g 801 WARRENVILLE ROAD LISLE, ILLINOIS 60532 4351
- Mr. Oliver D. Kingsley .
- President, Nuclear Generation Group Commonwealth Edison Company 1
- ATTN: Regulatory fservices
- i Executive Towers West 111 1400 Opus Place, Suite 500 Downers Grove,IL 60515
Dear Mr. Kingsley:
) Enclosed for your review is the Systematic Assessment of Licensee Performance r (SALP) 14 Report for the Quad Cities Nuclear Power Station covering the period October 27 L 19g6, through December 20,1997. This report will be discussed with you at a public meeting to be held at the Quad Cities Station on February 17,1998, at 1:00 p.m. During this meeting,
- you are encouraged to candidly discuss any comments you may have regarding our report.
- in accordanco with Nuclear Regulatory Commission (NRC) policy, I have reviewed the recommendations resulting from the SALP Board assessment and concur with their ratings. The i functional areas of Operations and Plant Support were rated as Category 2. The areas of ,
L Maintenance and Engineering were rated as Category 3. Although the ratings were the same as ir '9 ALP 13, it is my view that conduct of nuclear activities in connection with the Quad Cities i . facility declined from the previous assessment period. Improvement was noted in some areas;
, however, substantial problems were discovered involving implementation of the maintenance '
- ~ rule, procedures and analyses to achieve safe shutdown in the event of a fire, and the conduct of
, . hydrostatic testing of the reactor vessel. Aspec. , of each of these problems extended into each of the SALP functional areas. Further, insufficient oversight and support from both the
! - Commonwealth Edison Corporate Engineering and Quality and Safety Assurance organizations contributed to the problems.
~
l . In the area of conduct o,' plant operations, good performance continued from the last SALP
- period and was evident ti
- roughout this assessment period. Improvements which were sustained L included good performance standards, improved procedural adherence, and enhanced self-
! assessment of operations. There were, however, elements of several operational decisions L which did not reflect a strong safety focus. Conducting a pressure test after taking a unit critical rather than before, and operating without an approved shutdown analysis and supporting l procedures for coping with fires, were two of these decisions. Equipment problems that challenged operators were not resolved, in part, due to lack of aggressive action by operations to i
force resolution. There was also an increase in missed or late surveillances attributable to j- operations.
i improvement of the plant maten% undition continued, but a number of long term issues with plant equipment remained. - As an example, poor equipment performance resulted in operators F having to respond to plant transients or to manipulate reactor power levels in order to perform i repetitive maintenance. Poor implementation of the maintenance rule prevented rule-based 9802120164 980130 ADOCK 05000254 PDR O PDR ll ll llll Illi !Il ll ;/ O ps N J
___ m-_ _ _ _ _ _ _ _ _ , . . . . _ . . . . - , , , .
O. Kingsley actions from contributing to improved equipment performance. A decline in performancs with regard to surveillances and inadequate hydrostatic test inspections on Unit 2 also contributed to a Category 3 rating in Maintenance.
Substantial weaknesses in engineering performance resulted in a repeat Category 3 rating in Engineering. While some_of the engineering support to the plant continued at an improved level from the last SALP, problems were experienced with surveillance acceptance criteria, understanding and application of the design basis, operability and 10 CFR 50.5g safety evaluations, and application of the Parts Replacement Program. Significant problems in several areas, including procedures for safe shutdown in the event of a fire, implementation of the maintenance rule, and residual heat removal service water pump testing, were surfaced through -
good problem identification efforts. However, the corrective actions to completely resolve these problems were not properiy and aggressively pursued, nor wore the actions comprehensive.
Extensive NRC intervention was required to ensure the significance of the issues was understood.
Departmental self-assessment activities and assessments by the Quality and Safety Assurance organization made some positive contributionsc Self assessments in Operations and Emergency L Preparedness stood out as being the most effective. However, in some cases, resolutions were
!) narrow or not promptly implemented.
l At the SALP meeting you should be prepared to discuss our assessments and your plans to improve performance in the areas of Maintenance and Engineering. Additionally, you are
> requested to respond in writing, within 30 days after the meeting, specifically addressing corrective actions planned to improve performance in these areas.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulations, a copy of this letter, the SALP report, and your response will be placed in the NRC's Public Document Room.
Should you have any questions conceming the SALP Report, we would be pleased to discuss them with you.
j Sincerely,
/ t
]% %J
_ . Bill Beach Regional Administrator
- Docket Nos. 50-254; 50-265
Enclosure:
SALP 14 Report No. 50-254/97001; 50-265/97001 See Attached Distribution 1
b
O Kingsley ,3, cc w/ encl: M. Wallace, Chief of Staff D. Helwig, Senior Vice President G. Stanley, PWR Vice President J. Perry, BWR Vice President D. Farrar, Regulatory Services Manager
- 1. Johnson, Licensing Director .
DCD - Licensing E. Kraft, Jr., Site Vice President D. Cook, Quad Cities Station Manager C. C. Peterson, Regulatory Affairs Manager Richard Hubbard Nathan Schloss, Economist Office of the Attomey General State Liaison Officer Chairman, !!!inois Commerce Commission W. D. Leech, Manager of Nuclear MidAmerican Energy Company
O. Kingsley actions from contubuting to improved equipment performance. A decline in performance with regard to surveillances and inadequate hydrostatic test inspections on Unit 2 also contributed to a Category 3 rating in Maintenance.
Substantial weaknesses in engineering perlormance resulted in a repeat Category 3 rating in Engincsring. While some of the engineering support to the plant continued at an improved level from the last SALP, problems were experienced with surveillance acceptance criteria, understanding and apolication of the design basis, operability and 10 CFR 50.59 safety evaluations, and application of the Parts Replacement Program. Significant problems in several areas, including procedures for safe shutdown in the event of a fire, implementation of the maintenance rule, and residual heat removal service water pump testing, were swfaced through good problem identification efforts. However, the corrective actions to completely resolve these problems were not properly and aggressively pursued, nor wrs me actions comprehensive.
Extensive NRC intervention was required to ensure the signiWiu of the issues was understood.
Departmental seif assessment activities and assessments by the Quality and Safety Assurance organization made some positive contributions. Self assessments in Operations and Emergency Preparedness stood out as being the most effective. However, in some cases, resolutions were narrow or not promptly implemented.
At the SALP meeting you should be prepared to discuss our assessments and your plans to improve performance in the areas of Maintenance and Engineering. Additionally, you are requested to respond in wiiting, within 30 days after the meeting, specifically addressing corrective actions planned to improve performance in these areas.
In accordance, with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter, the SALP report, and your response will be placed in the NRC's Public Document Room.
Should you have any questions conceming the SALP Report, we would be pleased to discuss them with you.
Sincerely,
/s/ A. Bill Beach A. Bill Beach Regional Administrator Cocket Nos. 50-254;50-265
Enclosure:
SALP 14 Report No. 50-254/97001; 50-265/97001 See Attached Distribution DOCUMENT NAME: G:\SALP\QUA97001.SLP SEE PREVIOUS CONCURRENCES To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE Rlli Rlll Rlli Rlli l Rlli l 0 RUls NAME RLerch:dp MRing RCapra JJacobson GGrant A8e8 DATE 01/ /98 01/ /98 01/ /98 01/ /98 01/ /98 01/30/98 0FFICIAL RECORD COPY N
[.
O. Kingsley ;
i i actions from contributing to improved equipmerd performance. A decline in perfomance with regard to surveillances and inadequate hydrostatic test inspections on Unit 2 also contributed to a &;;-:-ry 3 rating in Maintenance.
l Substantial weaknesses in engineering performance resulted in a repeat Category 3 rating in Engineering. While some of the engineering support to the plant continued at an improved level i from the last SALP, problems were experienced with surveillance acceptance criteria,
, understanding and application of the design basis, operability and 10 CFR 50.5g safety - 1 l evaluations, and application of the Parts Replacement Program. Significant problems in several areas, including procedures for safe shutdown in the overd of a fire, implementation of the maintenance rule, and residual heat removal service water pump testing, were surfaced through good problem identification efforts. However, the corrective actions to completely resolve these problems were not property and aggressively pursued.
Departmental self-assessment activities and assessments by the Quality and Safety Assurance organization made some positive contributions. Ostf-assessments in Operations and Emergency l Preparedness stood out as being the most effective. However, in some significant cases, i resolutions were narrow or not promptly implemented.
l At the SALP meeting you should be prepared to discuss our assessments and your plans to
- improve performance in the areas of Maintenance and Engineering. Additionally, you are requested to respond in writing, within 30 days after the meeting, specifically addressing
! corrective actions planned to improve performance in these areas.
\
! In accordance with Section 2.700 of the NRC's " Rules of Practice," Part 2, Title 10, Code of
- Federal Regulations, a copy of this letter, the SALP report, and your response will be placed in l the NRC's Public Document Room.
Should you have any questions concoming the SALP Report, we would be pleased to discuss l them with you.
I Sincerely, j /s/ A. Bill Beach i' A. Bill Beach L Regional Administrator Docket No. 50-254 l Docket No. 50-265
Enclosure:
SALP 14 Report
- No. 50-254/g7001; 3
50-265/g7001 SEE PREVIOUS CONCURRENCES '
See Attached Distnbution DOCUMENT NAME: G:\SALP\ QUAG 7001.SLP To receive a copy of this document, indicate in the box: "C" = Copy without
, attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy l OFFICE Rlli l Rlli l Rlli l Rlli l Rlli l Rlli i NAME RLerch:dp MRing RCapra JJacobson GGran@le ABeach l DATE 01/ /98 01/ /98 01/ /98 01/ /98 01/hMV 01/ /98
~~
OFFICL4L RECORD COPY l
1
)
O. Kingsley of the maintenance rule prevented rule based actions from contributing to improved equipment performance. A decline in performance with regard to surveillances and inadequate hydrostatic test inspection on Unit 2 also contributed to a Category 3 rating in Maintenance.
Substantial weake. esses in engineering performance led to a repeat Category 3 rating in Engineering. While some of the engineering support to the plant continued at an improved level from the last SALP, problems were experienced with battery testing acceptance criteria, understanding and application of the design basis, operability and 10 CFR 50.59 safety evaluations, and applicatlon of the Parts Replacement Program fw the emergency diesel generator air start motors. Significant problems in several areas, including procedures for safe shutdown in the event of a fire, implementation of the maintenance rule, and residual heat removal service water pump testing, were surfaced through good problem identificatio,e efforts.
However, the corrective actions to completely resolve these problems were not properly and aggressively pursued.
Departmental self assessment activities and assessments by the Quality and Safety Assurance organization made positive contributions, particularly in the identification of problems. However, in some significant eases, resolutions were narrow or not promptly implemented. Self-assessments in Operations and Emergency Preparedness stood out as being the most effective.
At the SALP meeting you should be prepared to discuss our assessments and your plans to improve performance in the areas of Maintenance and Engineering. Additionally, you are requested to respond in writing, within 30 days after the meeting, specifically addressing corrective actions planed to improve performance in these areas.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter, the SALP report, and yout response will be placed in the NRC's Public Document Room.
Should you have any questions conceming the SALP Report, we would be pleawd to discuss them with you.
Sincerely,
/s/ A. Bill Beach A. Bill Beach Regional Administrator Docket No. 50-254 Docket No. 50-265
Enclosure:
SALP 14 Report No. 50-254/97001; 50-265/97001 See Attached Distribution DOCUMENT NAME: G:\SALP\QUA97001.SLP To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE Rlli f Rlli F Rlli C Rlll , ( ,. - Rlli Rlli NAME RLerch:d6h6 MRincDfhl RCapra @di JJacobs% D GG- ABeach DATE 01/n/98 01/W/98 01/D/98 01M /98) V 01/ /98 01/ /98 0FFICIAL RECORD COPY l
l O. Kingsley .3- .l l
1 cc w/ encl: M. Wallace, Chief of Staff D. Helwig, Senior Vice President G. Stanley, PWR Vice President J. Perry, BWR Vice President D. Farrar, Regulatory Services Manager
- 1. Johnson, Licensing Director DCD- Licensing E. Kraft, Jr., Site Vice President D. Cook, Quad Cities Station Manager C C. Peterson, Regulatory Affairs-Manager Richard Hubbard
.Nathan Schloss, Economist Office of the Attomey General-State Liaison Officer Chairman, Illinois Commerce Commission W. D. Leech, Manager of Nuclear MidAmerican Energy Company INPO '
Distribution Chairman Jackson Commissioner Dicus Commisslor.or Diaz Commissioner McGaffigan L. Callan, EDO J. Lieberman, Director, Office of Enforcement R. Zimmerman, Associate Director for Projects, NRR B. Sheron, Acting Associate Director for Technical Review, NRR E. Adensam, Acting Director, Division of Reactor Projects lil/lV, NRR GALP Program Manager, NRR (2 copies)
DRP Division Directors RI, Rll, RIV
.J. Caldwell, Rlil R. Capra, NRR
. R. Pulsifer, NRR TSS, Rlli Docket File DRP PUBLIC IE-40 SRI Quad Cities CAA1 (E-Mail)
RillPRR Rill Enf. Coordinator DRS (2) '
DOCDESK (E-Mail)
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