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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:NRC TO UTILITY
MONTHYEARML20062G0401990-11-21021 November 1990 Advises That fitness-for-duty Insp Scheduled for Wk of 910122-25.Written Policies/Procedures Will Be Reviewed ML20062G6911990-11-19019 November 1990 Advises That Schedule to Conduct Type a Containment Integrated Leak Rate Test for Fall 1990 Complies W/ Requirements of App J,Section III.A.6 & Applicable Tech Specs,Per Util ML20058E8171990-10-31031 October 1990 Requests Submittal of Review Re Adequacy of Initial Investigation of Allegation RIII-90-A-0002 within 30 Days ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20058E6891990-10-26026 October 1990 Forwards Mgt Meeting Repts 50-254/90-19 & 50-265/90-19 on 900925.Meeting to Discuss NRC Concerns Re Containment Performance Testing at Plant ML20059N6801990-10-0505 October 1990 Forwards Insp Repts 50-254/90-14 & 50-265/90-14 on 900805- 0915 & Notice of Violation ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20059J6371990-09-13013 September 1990 Forwards Enforcement Conference Repts 50-254/90-16 & 50-265/90-16 on 900905 & Notice of Violation.Technical Oversight in Case Indicates Need for Greater Care & Attention to Detail by Personnel ML20059B6351990-08-23023 August 1990 Confirms 900911 Meeting W/Util in Glen Ellyn,Il to Discuss Rebaseline Program for Facility Updated Fsar.Discussion Should Include Progress & Overall Elements of Program ML20059A1771990-08-15015 August 1990 Forwards Safety Insp Repts 50-254/90-10 & 50-265/90-10 on 900605-0802.Violations Noted.Enforcement Conference Will Be Held in Region III Ofc W/Util ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20055F9191990-07-17017 July 1990 Forwards SER Confirming Util Responses to NRC Bulletin 88-010 & Suppl Re molded-case Circuit Breakers.Util Use of Replacement Breakers Until Fully Qualified Breakers Can Be Installed Acceptable Based on 891120 & 29 Submittals ML20055G4581990-07-13013 July 1990 Forwards Safety Insp Repts 50-254/90-11 & 50-265/90-11 on 900611-14.No Violations Noted ML20059M8791990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248J2381989-10-0303 October 1989 Forwards Safety Evaluation Accepting Util Insp,Repairs & Mitigation of Welds Susceptible to IGSCC Performed During Spring 1988 Refueling Outage for Unit 2 ML20248E1041989-09-28028 September 1989 Informs That Licensee Proposed Type a Test Schedule for Plant Complies W/Requirements of 10CFR50,App J,Section III.a/6 & Applicable Tech Spec & Acceptable ML20248G1701989-09-28028 September 1989 Forwards Insp Repts 50-254/89-19 & 50-265/89-19 on 890821-25.No Violations Noted ML20247N8631989-09-19019 September 1989 Advises That Safeguards Regulatory Effectiveness Review Scheduled for Wk of 891113-17 at Plant Site.Internal & External Security Groups Will Require Escort from Security Dept ML20246Q0401989-09-0101 September 1989 Forwards Complete Unannounced Drill Evaluation of Implementation of State & Local Radiological Emergency Response Plans, Conducted on 890510.Due to Document Reproduction Error,Only Portions Submitted w/890804 Ltr ML20246H5721989-08-29029 August 1989 Confirms 890831 Meeting W/Util to Discuss Plant Performance Issues ML20246K6861989-08-29029 August 1989 Advises That Util 890829 Emergency Tech Spec Change Request Re RHR Loop B HX to Be Fed from RHR C & D Svc Water Pumps Via Crosstie Line Until 891101 Acceptable ML20246K9851989-08-28028 August 1989 Forwards Safety Insp Repts 50-254/89-16 & 50-265/89-16 on 890625-0819 & Notice of Violation ML20246K5861989-08-25025 August 1989 Forwards Safeguards Insp Repts 50-254/89-18 & 50-265/89-18 on 890814-18.No Violations Noted ML20246F6221989-08-23023 August 1989 Concludes That Proposed Insp Plan,W/Exception of Weld 02M-S3,meets Guidelines of Generic Ltr 88-01 & Acceptable. NRC Recommends That Util Ultrasonically Examine Weld 02M-S3 ML20246D3261989-08-16016 August 1989 Advises That Task Activities Re Util 890331 Application for Amend to License Terminated,Per Licensee Withdrawal Request. Amend Would Allow cross-connecting Independent Loops of RHR Svc Water Sys ML20245J2531989-08-0909 August 1989 Informs That Written & Oral Operator Licensing Exams Scheduled for Wk of 891113.All Reactor & Senior Reactor Operator License Applications Should Be Submitted at Least 60 Days Prior to Exam Dates in Order to Review Applicants ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20248D8641989-08-0404 August 1989 Forwards FEMA Transmitting FEMA Exercise Rept for Plant May 1989 Exercise.No Deficiencies Noted.Nine Areas Requiring Corrective Action Identified.Nrc Expects That Util Will Devote Attention to Resolve Concerns ML20247K3131989-07-21021 July 1989 Advises That 890608 Rev 7b to Annex of Generating Station Emergency Plan Consistent W/Requirements of 10CFR50.54(q). Rev 7b Consists of Table of station-specific Emergency Action Level ML20247C4151989-07-19019 July 1989 Forwards Safety Insp Repts 50-254/89-12 & 50-265/89-12 on 890514-0624.Discrepancy Identified Re Functional Descriptions of Certain Drywell Valves Currently Stated in Updated FSAR ML20246C3411989-07-0505 July 1989 Forwards Safety Insp Repts 50-254/89-13 & 50-265/89-13 on 890522-0608.No Violations Noted ML20245K0681989-06-28028 June 1989 Forwards Safety Insp Repts 50-254/89-14 & 50-265/89-14 on 890605-09.No Violations Noted ML20245K9011989-06-28028 June 1989 Forwards Requalification Exam Rept 50-254/OL-89-02 on 890511-13 & 15-16 for Units 1 & 2.Programmatic Weaknesses Identified ML20246A1311989-06-28028 June 1989 Forwards Safety Insp Repts 50-254/89-15 & 50-265/89-15 on 890619-21.No Violations Noted ML20245K5501989-06-23023 June 1989 Requests Addl Info Re Valves Addressed by BWR Owners Group Per IEB-85-003.Info Requested within 1 Month of Ltr Date ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20244B8171989-06-12012 June 1989 Ack Receipt of & Check for $75,000 in Payment for Civil Penalty IR 05000254/19880111989-06-0808 June 1989 Informs That Revised Commitment Dates Re Violations Noted in Insp Repts 50-254/88-11 & 50-265/88-12 Acceptable ML20244D5741989-06-0707 June 1989 Comments on Review of Revs 5 & 6 to Plant Updated Fsar. Response That Addresses NRC Conclusion & Specific Findings Requested within 90 Days.Response Should Also Detail Scope & Schedule of Proposed Corrective Actions.Findings Encl ML20248B8791989-06-0606 June 1989 Forwards Safety Evaluation Concluding That Insps,Repairs & Mitigations Performed During Reload 9/Cycle 10 Outage Met Guidelines of Generic Ltr 84-11.Util Should Incorporate Weld Repairs & Exams in Unit Igssc Insp Plan ML20247H5271989-05-22022 May 1989 Forwards Safety Insp Repts 50-254/89-10 & 50-265/89-10 on 890402-0513.No Violations Noted ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met ML20245L8211989-05-0303 May 1989 Forwards Order Imposing Civil Monetary Penalty in Amount of $75,000.Reduction of 50% of Proposed Civil Penalty Appropriate After Reconsideration of Escalation & Mitigation Factors ML20246H6601989-04-26026 April 1989 Advises That NRC Considers Util 880517 Amend Request to Revise Requirements Associated W/Rod Block Monitor Withdrawn,Per Recent Meeting ML20247D6961989-04-26026 April 1989 Forwards Notice of Denial of 871116 Application for Amend to License DPR-29 Recirculation Jet Pump Flow Instrumentation ML20245J3611989-04-26026 April 1989 Advises That 880816 Request for Amend to Revise Reporting Requirements for Fire Suppression Sys Considered Withdrawn. Requests That NRC Be Notified within 10 Days of Receipt of Ltr If Info Not Correct ML20244D3581989-04-13013 April 1989 Forwards Insp Repts 50-254/89-04 & 50-265/89-04 on 890205-0401.No Violations Noted ML20244C9881989-04-11011 April 1989 Forwards FEMA Transmitting Rept of 880831 Offsite Radiological Emergency Response Plan Exercise.All Eight Deficiencies Identified by FEMA Corrected ML20247M8821989-04-0303 April 1989 Ack Receipt of 890222 Payment of Civil Penalty in Amount of $50,000,per NRC 890123 Order ML20246P6401989-03-22022 March 1989 Forwards Exam Rept 50-254/OL-89-01 of Exam Administered on 890206-10 1990-09-25
[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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A U G 0 9 198 5 Docket No. 50-254 Docket No.50-26R Commonwealth Edison Company ATTN: Mr. Cordell Reed Vice President Post Office Box 767 Chicago, IL 60690 Gentlemen:
In our letter to you dated January 11, 1985, we stated that the Federal Emergency Management Agency (FEMA) was performing an evaluation regarding the deficiency in the State of Illinois. This evaluation was being conducted to determine what effect, if any, the deficiency had on the overall status of offsite preparedness. Our letter further indicated that we would determine an appropriate course of action under our regulations for your Quad Cities facility after receiving this FEMA evaluation. The deficiency for Illinois had been characterized as one affecting public health and safety.
We have received the attached FEMA evaluation, dated June 21, 1985, regarding the overall status of offsite preparedness. This evaluation is based on the enclosed corrective actions submitted by the State of Illinois to correct the deficiency affecting public health and safety. The FEMA evaluation states that in view of the demonstrated capability by the State of Illinois to successfully initiate timely EBS notification in conjunction with stren activation at the LaSalle exercise in October 1984, and after reviewing the State's schedule of corrective actions, it is FEMA's opinion that there is reasonable assurance that the health and safety of the public can be protected in the event of a radiological emergency at the Quad Cities Nuclear Generating Station.
Based on this FEMA evaluation, we conclude that the deficiency affecting public health and safety which we identified to you in our January 11, 1985 letter has been satisfactorily corrected, and no further action under our regulations is warranted.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosures will be placed in the NRC's Public Document Room.
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Commonwealth Edison Company 2 AUG 0 9 '^95 Should you have any questions regarding this letter, please contact Mr. M. Phillips of my staff at (312) 790-5530.
Sincerely, b
W. D. Shafer, Chief Emergency Preparedness and Radiological Protection Branch Attachments: As stated cc w/ enclosure:
D. L. Farrar, Director of Nuclear Licensing N. Kalivianakis, Plant Manager DMB/ Document Control Desk (RIDS)
Resident Inspector, RIII Phyllis Dunton, Attorney General's Office, Environmental Control Division D. Matthews, EP8, 0IE 08/07/85
f"T'bg Federal Emergency Management Agency
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Washington, D.C. 20472 JUN 2 l 1985 D MEMORANDUM FOR: Edward L. Jordan Director fh 7,4 Division of Emergency Preparedness $fbR and Engineering Response Office of Inspection and Enforcement MC64 '
U.S. N clear e latory Commission FROM: ard Krimm p ,.
Assistant Associate Director ""' 3 Office of Natural and Technological Hazards Programs
SUBJECT:
Illinois Schedule of Corrective Actions for Deficiencies Identified During the Quad Cities Nuclear Power Plant (NPP)
Offsite Radiological Emergency Preparedness (REP) Exercise Conducted on August 28-29, 1984 Attached is the schedule of corrective actions submitted by the State of Illinois for the deficiencies noted in the Final Report for the Quad Cities Nuclear Power Plant Offsite REP Exercise conducted on August 28-29, 1984.
The exercise report was sent to you on November 14, 1984.
As stated in my exercise transmittal of November 14, 1984, one deficiency affecting the public health and safety (Category A) was identified during the course of the exercise. The Category A deficiency (NUREG-0654 evaluation criteria E-6) for the State of Illinois, was due to the State's failure to order activation of the EBS within 15 minutes of the decision to alert the public. The sirens were sounded within 15 minutes. However, 26 minutes elapsed before the initial instructional message was announced (simulated) on the EBS station.
It was also stated in my November 14, 1984, memorandun that Illinois would be required to conduct a remedial drill before January 31, 1985, to correct this deficiency. However, the requirement for a remedial drill was sub-sequently lifted because of the following two factors. First, the State of Illinois successfully demonstrated the capability to order activation of the sirens concurrently with activation of the EBS during the LaSalle exercise on October 10, 1984 Additionally, I would like to point out that Illinois also successfully demonstrated its capability to order activation of the sirens concurrently with EBS activation during the Zion exercise on March 5, 1985, and the Dresden exercise on April 23, 1985. Secondly, the State agreed, as part of their corrective actions, to meet with the County Emergency Services and Disaster Agency (ESDA) coordinators to review local plans and procedures for EBS and siren activation. This meeting took place on January 18, 1985, and was held to ensure that County officials fully understand their role in public notification, and that they will initiate EBS notification in conjunction with siren activation in the absence of a State directive to do so.
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The Federal Emergency Management Agency (FEMA) Headquarters and Region V staff have reviewed the sched11e of corrective actions submitted by Illinois; evaluated the State's capability to activate the EBS concurrent with siren activation (as successfully demonstrated during the LaSalle exercise in October 1984); and, reviewed the meeting held between Illinois and County ESDA officials. The foregoing scheduled and completed actions have been found to be adequate. In view of the demonstrated capability by the State of Illinois to successfully initiate timely EBS notification in conjunction with siren activation at the LaSalle exercise in October 1984, and after reviewing the State's schedule of corrective actions, it is our opinion that there is reasonable assurance that the health and safety of the public can be protected in the event of a radiological emergency at the Quad Cities NPP. Therefore, the approval under FEMA Rule 44 CFR 350 will remain in effect.
If you have any questions, please contact Mr. Robert S. Wilkerson, Chief, Technological Hazards Division, at 646-2861.
Attachment As Stated
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lilinois Emergency Services and Disaster Agency 110 East Adams Street, Springfield, Illinois 62706 March 11, 1985 Mr. Itallace J. Weaver, Chairman Regional Assistance Committee Federal Emergency Management Agency Region V 300 South Wacker, 24th Floor Chicago, IL 60606
Dear Mr. Weaver:
This letter responds to your letter dated January 11, 1965 relative to required corrective actions for the Quad Cities exercise deficiencies.
The acceptance by FEMA of the results of the LaSalle exercise is important as it is clearly apparent that the State of Illinois has the procedures in place to activate the EBS system concurrent with the siren system activation.
The IPPA planning team met with local ESDA coordinators at 10:00 a.m.
on January 18, 1985 and reviewed local procedures for EBS and siren activation. Plans and procedures are already in place and need only to be activated in a timely manner on direction from the State EOC. Of particular importance, is the forthcoming FEMA 43 demonstration of the Prompt Notification System and the EBS activation. This will allow both State and lecal ESDA to demonstrate these systems independently and effectively show that appropriate corrective actions have been taken.
On your last point, concerni:4g the Cuad Cities Nuclear Pewer Station News Media Center, I have been engaged in an active dialocue with Comnonwealth Edison about improving several of their News Media facilities.
I have stated that the State of Illinois will no longer participate in JPIC operations at Quad Cities in the present facility. I expect Commonwealth Edison will be taking significant measures to improve the Quad Cities facility as well as other marginal Media Centers. Your assistance and support in this area of JPIC imprevcment is appreciated.
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Charles D. JoheJ Directer .
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Federal Emergency Management Agency Region V 300 South Wacker. 24th Floor, Chicago,IL 60606 (312) 353-1500 January 11, 1985 Mr. Charles D. Jones Acting Director Illinois Emergency Services and Disaster Agency 110 East Adams Street Springfield, Illineis 62706
Dear Mr. Jones:
This letter is in response to your proposed corrective actions dated December 17, 1984 and my conversations with both you and David Wise of your staff concerning the deficiencies cited for the August 28-29, 1984, Quad Cities radiological emergency preparedness exercise. As a result of the conversations, I have amended the required corrective actions for rLe Qvad Cities exercise deficiencies. The State of Illinois is to longer required to conduct a remedial exercise to correct the category A deficiency to NUREG-0654 criteria element E.6. 1 This amendment to the required corrective action is based on two factors.
First, during the Quad Cities exercise the sirens were activated in a timely fashion. The deficiency arose because the State of Illinois did not order the activation of the EBS concurrent with the order to activate the sirens. The State of Illinois did sucessfully demonstrate this capability at the LaSalle exercise last October and will demonstrate it again at both of the upcoming exercises: Zion in March and Dresden in April. This constitutes sufficient corrective action on the part of the State of Illinois.
The second factor concerns the ability of local government to activate EBS in conjunction with siren activation in the absence of the State's order to do so. Since David Wise has agreed to address this issue during his January 18, 1985 meeting with local governments affected by the Quad Cities NPS in Illinois, this will be more productive and effective than a single issue remedial exercise. P2 ease provide me with a report of the January 18 meeting for eur records by February 8, 1985.
With respect to the remainder of your corrective actions, they are approved contingent on the above with one condition. The State of Illinois should actively participate with Commonwealth Edison Company in the planning and establishment of the Quad Cities Nuclear Power Station News Medip Center.
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s If you have any questions, please call me at (312) 886-9530. I am providing a copy of this letter to my Headquarters Office for transmittal of your schedule of corrective actions to the NRC.
Sincerely, Q h e,c
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- Wallace J. aver, Chairman Regional Assistance Committee cc: Mr. David Wise
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- lilinois Emergency Services and Disaster Agency 110 East Adams Street, Springfield, Illinois 62706 December 17, 1984 Mr. Wallace Weaver Chief, Technical Hazards Branch Region V. Federal Emergency Management Agency 300 South Wacker Drive Chicago, Illinois 60606
Dear Mr. Weaver:
Please disregard our correspondence to you dated December 14, 1984 and replace it with the attached Proposed Corrective Action Response. Infor-mation regarding the proposed corrective action for Item 0.4.c. was inadvertently omitted.
Sincerely, x avid
' m-s_.Q L. Wise A
Senior Associate Director DLW/AH/lh enci cc: Gordon Wenger
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UTILITY: Quad Cities Nuclear Poveer Station Illinole 111. Summon'y Listing of Deficiencies (State) August 28-29. 1984 A. (Oste)
Illiness Deficiencies Affecting Public Health and Safety .
(Ceesmalay)
NUMC Merret'ive Stateseet Itee Corrective Action Scheduled actus!
of Defleiency~ Froposed Date Date E.6. It took 26 minutee from the time Procedures are developed and . 1/85 the state decided to activate training will be enhanced to the strees to siert the public ensure efficient timely notifi-until the tattist instructiomet cation, and this capability will. ~ ',
message wee provided to the Ess. be demonstrated during the
, remedial drill.
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UTILITY: gad Cities helear Power Station
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Illinola III. Summary Lleting of Deficiencies (State) Aamust 28-29. 198 5.
Other Deficiencies (Date)
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(Commualty)
NUSEC Marrattwe Statement Corrective Action Scheduled Actua*
Ites of Deficiency Proposed Date Date A.2.a. Information on the cause of the incident Proper procedures are developed Next scheduled at the plaat was not diesentasted to and will be implemented to demonstrate exercise the REAC or Rock toland County. the controlled dissemination of this information through the DNS and State l ESDA representatives assigned to the l C.3.a. h News Media Center facility is county E0C's. j limited la space and furnishings.
Neating and air conditioning ta a The News Media Center, although not probles. press releases had to be ideal, meets minimum requirements. This processed ta the EOF, a building concern must be directed to the utility sep. rate from the News Media Center. If corrective action is required. Press N/A releases were properly processed in EOF as this is where the PI0's' prepare all J.lo.b. h press release. prepared at the State materials.
ROC, described evacuation sectore by letter deeisaations rather than All sectors and boundary descriptions Next scheduled landmarks or boundaries. are being rewritten using geographical exercise and/or political features to identify the various portions of the EPZ and this capability will be demonstrated during the next scheduled exercise.
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i UTILITY: Quad Cities Nuclear Power Station Illinole III. Summary Listing of Deficiencies , August 28-29. 198 (State) (Dete)
- 5. Other Deficiencies s Illinois (Cessmanity)
IRiaEC Marrattwe Stateneat Corrective Action Scheduled Actua!
Ites of DefIcleocy Proposed Dete Deto 0.4.c. Protective clothing (gloves) ves not Training will be provided to Prior to used in the sachering of the milk Department of Public Health workers next exercise sample, allowing contamination of regarding proper sampling procedures.
the worker's hood by spilled allk. This training will include the use of protective gloves.
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UTILITY: Quad Cities Nuclear Power Station 1111aele III. Sumality Listing of Deficiencies .. August 28-29, 198 (State)
Rock Island County Deficiencies Affecting Public Health sad Safety
- (Ceamenity) i REIREC Marrettwe Statement Corrective Action Scheduled Item of Deficiency Actual Proposed Date Date None l
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UTILITY: Quad Cities Nuclear Pouer Stetton 111tnote III. Sueegry Liettag of Deficiencies August 28-29. 1934 (State) (Dete)
- 8. Other Deficiencies
- Rock Islead County (Commaity) '
RAleEC Herrettwo Stateneet Corrective Actica Scheduled Actual l
i Itee of Deficiency Proposed Date Date A.2.e. The times posted on the status heard Emergency workers will be further Next scheduled were the times of the posting. Instructed in proper posting procedures exercise and this capability will be demonstrated at the next scheduled exercise.
F.I.e. Information recorded on MARS message forms wee leproperly interpreted when Emergency workers will be further instructed Next scheduled posted la the Port Syrom EOc. in the proper interpretation of the informa- exercise tion that is recorded on the NARS form and this capability will be demonstrated at the L.t.~ mespital personnet did not demonstrate next scheduled exercise.
proper procedures to prevent the possible spread of conteniastion during The U.S. Department of Public Health report N/A the headling of a contaminated lajured has been provided to Commonwealth Edison patient. Company for their corrective action.
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L.4. Ambulance persemeel did not demonstrate The U.S. Department of Public Health report N/A procedures to prevent the possible has been provided to Commonwealth Edison spread of conteatnetton during the Company for their corrective action.
transport of the lajored victim.
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1 UTILITY: Quad Cities Muclear Pouer Station e
1111 mote III. Summary Listing of Deficiencies Aunust 28-29, 1944 (State)
- (Dete)
A. Deficiencies Affecting Public Health and Safety
{ (Ceemenity) ,
3RaaEC Marrative Stateneet Corrective Action Scheduled Actual I Itee of Defielency Proposed Date
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j UTILITY: Ebsed Cities Nuclear Power Stattee ,
t l Illisele III. Sueesty Listieg of Deficiencies Auavet 24-29, 1984 (State) .
(Dete)
- 3. Other Deficiencies -
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ImpeEC IIerrettee Stateneet Corrective Actise Scheduled Actual
! Item of Deficiency Proposed Date Date I.S. The etenderd message comoed e Prescripted messages for both TBA i
deficiency doctog the sheltering and evacuation have esercise due to the fact been developed and training will
, that Albesy use to se aree be enhanced to ensure proper i to be sheltered rather then understanding and utilization of i eseemeted. those messages.
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