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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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AUG 041989 Docket No. 50-254-Docket No. 50-265 Commonwealth Edison Company -
ATTN: Mr. Cordell Reed Senior Vice' President Post Office Box.767 Chicago, IL 60690 Gentlemen:
We have received the enclosed Federal Emergency Management Agency (FEMA) letter, dated June 27,,1989, which transmitted the FEMA Region VII Exercise Report for the May 1989 exercise at the Quad Cities Nuclear Generating Station.
No deficiencies were identified regarding the activities of emergency response personnel. representing.the. State of Iowa and Clinton and Scott Counties.
However,' nine Areas Requiring Corrective Actions (ARCAs) were identified by FEMA Region VII. Based on the status of corrective actions, FEMA has concluded
-that offsite radiological emergency preparedness remains adequate to provide. .
reasonable assurance that appropriate measures can be taken by State'and county officials to protect public health and safety in portions of the State of Iowa in the vicinity of the Quad Cities Station.
We understand that the successful completion of corrective actions on. items identified by FEMA involves actions by organizations other than Commonwealth Edison Company. Nevertheless, we expect that your staff will continue to devote the attention necessary to resolve these offsite emergency planning concerns.
.If you have any questions, please have your staff contact Mr. T. Ploski of my staff at (312) 790-5529.
Sincerely, 7
B908110155 ADOCK890804 05000254, ?w PDR ,
p PNU5,
. Ro er G ger, Chief Reactor Programs Branch
Enclosure:
As stated j See Attached Distribution N' RII RIII,, RIII RII II
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Commonwealth Edison Company 2 MG 04 M9 Distribution cc w/ enclosure:
T. Kovech, Nuclee.c Licensirig M:r,ager R. L. Bax, Station Manager DCD/DCB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Richard Hubbard J. W. McCaffrey, Chief, Public Utilities Division l
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Washington, D.C. 20472 O O JN 27 IRB Mr. Frank J. Congel Director, Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Hr. Congel:
Enclosed is a copy of the report for the unannounced drill conducted for the Quad Cities Nuclear Power Station on May 10, 1989. The report dated June 20, 1989, was prepared by the Federal Emergency Management Agency (FEMA) Region VII staff. The State of Iowa and the Counties of Clinton and Scott participated in this drill. The scope of this drill was limited to demonstrating the ability of State and local governments to fully activate Emergency Operations Centers (EOC's) and to mobilize all staff that report to the EOC's.
There were no deficiencies identified during the drill.
However, nine Areas Requiring Corrective Action (ARCA's) were identified. Five were cited at the State Emergency Operations Center (SEOC) . Two ARCA's were identified at the State Forward Command Post (FCP) . An ARCA was identified for both Clinton and Scott Counties due to the improper use of a primary communication system between the SEOC, FCP and County EOC's. A final ARCA was related to the Scott County Radiological Emergency' Plan. The Assistant to the Director acted as an alternate for the Director during the drill.
However, the plan does not account for this individual assuming this position. A summary of the ARCA's is located in Section 3 of the report; they are explained in detail in Section 2. Plan revisions are to be provided by the State and the appropriate objectives regarding the ARCA's cited at the May 10, 1989, drill will be included for demonstration at the next exercise, currently scheduled for December 5, 1990.
Based on the status of corrective actions, FEMA considers that offsite radiological emergency preparedness is adequate to provide reasonable assurance that appropriate measures can be taken offsite to protect the health and safety of the public living in the vicinity of the site in Iowa, in the event of a radiological emergency. Therefore, the approval of the ~offsite plans for the State of Iowa, site-specific to
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the Quad Cities Nuclear Power Station granted under 44 CFR 350 on March 26, 1986, continues to be in effect.
We have also enclosed a copy of the FEMA semorandum, dated March 20, 1989, transmitting to the NRC the August 31, 1988, exercise report in which we provided reasonable assurance for the health and safety of the public living in the .
vicinity of the Quad Cities Nuclear Power Station. We would like to clarify that our statement of reasonable assurance in that memorandum was meant to specifically address only the population which is living in the vicinity of the site in Iowa.
If you have any questions, please feel free to call me on 646-2871.
Sincerely, h, V Dennis H. Kwiatkowski Assistant Associate Director office of Natural and Technological Hazards I
Enclosures !
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x s O O UNANNOUNCED DRILL EVALUATION OF THE IMPLEMENTATION OF STATE :
AND LOCAL RADIOLOGICAL EMERGENCY RESPONSE PLANS CONDUCTED MAY 40, 1989 for the QUAD CITIES NUCLEAR POWER STATION Naar Cordova, Rock Island County, Illinois Commonwealth Edison, Licensee
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PARTICIPANTS:
State of Iowa Clinton County
, Scott County r , o, ,
JUNE 20, 1989
, !. L-prepared by Federal Emergency Management Agency Region VII .
911 Walnut, Room 200 '~.
Kansas City, Missouri 64106 Jerone,D. Overstreet, Regional Director .
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4 CONTENTS I
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ABBREVIATIONS AND ACRONYMS...................................iii j DRILL
SUMMARY
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. I 1 INTRODUCTION.............................................. 1 1.1 Drill Background..................................... 1 1.2 Drill Evaluators..................................... 2 1.3 Evaluation Criteria.................................. 2 1.4 Drill Objectives..................................... 2 1.5 Drill Scenario....................................... 3 1.6 State and Local Resources............................ 3 2 DRILL EVALUATION.......................................... 5 2.1 Iowa Operations...................................... 5 2.1.1 State Emergency Operations Center............. 5 2.1.2 State Forward Command Post..................., 7 2.1.3 Field Team Coordination / Field Monitoring Teams 9 2.1.4 Dose Assessment............................... 10 2.2 County Operations.................................... 10 2.2.1 Clinton County Emergency Operations Center... 10 2.2.2 Scott County Emergency Operations Center..... 12
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SUMMARY
OF AREAS REQUIRING CORRECTIVE ACTIONS............. 13
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- ,, ABBREVIATIONS AND ACRONYMS l
ARC American Red Cross ARCA Area Requiring Corrective Action ARFI Area Recommended for Improvement CCEOC Clinton County Emergency Operations Center CFR Code of Federal Regulations
'DNR Department of Natural Resources DOC Department of Commerce
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DOC Department of Corrections DOE Department of Energy DOI Department of Interior DOT Department of Transportation DPH Department of Public Health
(' DSD Disaster Services Division EBS Emergency Broadcast System EOC Emergency Operations Center EPA Environmental Protection Agency EPZ Emergency Planning tone r
FEMA Federal Emergency Management Agency i
FCP Forward Command Post h HHS/FDA Health and Human Services / Food and Drug Admini-stration HHS/PHS Health and Human Servicss/Public Health Service KI . Potassium Iodide NARS Nuclear Accident Reporting System .
NRC ' Nuclear Regulatory Commission j
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, DRILL CUMMARY
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The purpose of an exercise, or in this case a drill, is to determine the ability of appropriate off-site agencies to respond to an cmergency covered by State and local Radiological Emergency Response Plans. The scope of this drill was limited to demon-strating the ability of State and local governments to fully ac-tivate Emergency Operation Centers (EOC's), and to mobilize all staff that report to the EOC's. The evaluation of such an effort will, of necessity, tend to focus on the negative aspects of the exercise, on inadequacies in planning, preparedness and perfor-mance.
This focus of attention on the negative should not be taken to mean that there were not positive accomplishments, as well.
Indeed, there were; however, in the interest of brevity, only inadequacies will herein be summarized.
FEMA classifies exercise or drill inadequacies as deficien-cies or areas requiring corrective action. Definitions of these categories folicw.
Deficiencies are demonstrated and observed inadequacies that would cause a finding that off-site emergency preparedness was not adequate to provide reasonable assurance that appropriate C protective measures can be taken to protect the health and safety of the public living in the vicinity of a nuclear power facility in the event of a radiological emergency.
Areas reauirina ec yective action are demonstrated and ob-served inadequacies er dcate and local government performance, and although their correction is required, they are not consid-ered, by themselves, to adversely impact public health and
. safety. -
In addition, FEMA identifies areas recommended for imorove-mant, which are problem areas observed during an exercise that are not considered to adversely impact public health and safety. __
i While not required, correction:. of..these would enhance an organization's level of emergency preparedness.
There were no deficiencies identified during this drill.
However, nine areas requiring corrective Lction were identified.
Five were cited at the State Emergency Operations Center (SEOC) .
as follows:
- Due to technical complications, the Nuclear Accident Reporting System (NARS) failed to operate properly. The SEOC could not be contacted for notification of the Alert classification level utilizing this system.
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h 1 INTRODUCTION
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1 1.1 PRILL BACKGROUND On December 7, 1979, the President directed the Federal Emergency Management Agency (FEMA) to assume lead responsibility.
for all off-site nuclear planning and-response.
FEMA's responsibilities in radiological emergency planning for fixed nuclear facilities include the following:
- Taking the lead in off-site emergency planning and in the review and . evaluation of radiological emergency response plans developed by State and local governments.
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- Determining whether such plans can be implemented on the ba-sis of observation and evaluation of exercises of the plans conducted by State and local governments.
- Coordinating the activities of the following Federal agen-cies with responsibilities in the radiological emergency planning process:
- U.S. Department of Commerce (DOC)
- U.S. Ns". ear Regulatory Commission (NRC)
'(' - U.S. Environmental Protection Agency (EPA)
- U.S. Department of Energy (DOE)
- U.S. Department of Health and Human Services (HHS) 1
- U.S. Food and Drug Administration (FDA)
- U.S. Public Health Service (PHS)
- U.S. Department of Transportation (DOT)
- U.S. Dipartment of Agriculture (USDA)
- U.S. Department of the Interior (DOI)
I Representatives of these' agencies serve.as members of the Regional Assistance Committee (RAC), which is chaired by FEMA.
Formal submission of the radiological emergency response plans for the Quad Cities Nuclear! Power Station (QCNPS) to the RAC by the State of Iowa and affectea local jurisdictions was followed by a critique and evaluation of these plans.
An unannounced radiological emergency preparedness drill was conducted for the Quad Cities Nuclear Power Station (QCNPS) on May 10, 1989, between the hours of 0930 and 1230, to assess the capability of. State and local emergency preparedness organiza-tions to fully activate their facilities, mobilize their response staff, and complete the notification of all participating organi-zations during a radiological emergency at the Commonwealth Edison's Quad Cities Nuclear Power Station. The plans evaluated 5
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In this drill only Objective Number 36, regarding unannounce,d and off-hours drills and exercists, was in-a new objective fs tended for demonstration and evaluation.
portion was tested, as the off-hours portion had Only the unannounced been demon-J strated during a previous full-scale exercise.
The term unannounced" refers to a drill or exercise which is held without the time and date being made known to the re-sponders. For purposes of evaluating response capabilities, it is deemed appropriate to inform responders that an unannounced drill will be held during a particular week, keeping the date and time confidential until off-site notification prompts the re-sponders to activate.
This evaluation concerns a drill, and as such, required ,a specific, limited degree of response.
The drill was to include the activation of the State Emergency Operations Center (EOC), both Clinton and Scott County EOC's, and the State Forward Command Post (FCP) . The State dose essessment and radiological field team coordination functions were also to be activated and report to the appropriate locations. Two radiological field monitoring teams were to accompany the field team coordinator. Other field personnel who deploy from EOC's were to report to their appropriate EOC's to
( establish their readiness, but were not required to then deploy to their assigned locations.
Each of the above facilities were to establish communications with other organizational EOC's. When all appropriate staff at each facility had been mobilized and the appropriate notification to other organizations completed, the drill was to terminate.
1.5 DRILL SCENARIO -
a . a.. r At 0920 an Alert was -declared due to the required shut down of the QCNPS Unit 1 reactor'because of the unavailability of backup equipment required by technical specifications. At 0938 off-site notification : occurred. -
1.6 STATE AND LOCAL RESOURCES Listed below are organizations that planned to participate: .,
State of Iowa
- 1. Iowa Disaster Services Division
- 2. Iowa State Department of Public Health
- 3. Iowa National Guard
- 4. Iowa Department of Public Safety (Iowa Highway Patrol)
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g 2 DRILL EVALUATION
.C 2.1 IOWA STATE OPERATIONS 2.1.1 giate Emereenev onorations center (BEOC)
Objective to be demonstrated: 36.
Objective Number 36, ability to carry out emergency. response
) functions (i.e., activate EOC's, mobilize staff that report- to
! the. -EOC's, establish communications linkage and complete
- telephone call down) during an unannounced drill, was not adequately demonstrated.
l An inadequacy was identified as the Nuclear Accident Reporting System (NARS) failed to operate properly during 'the notification of the Alert emergency classification level. Due to technical complications, the State Emergency Operations Center (SEOC) could not' he contacted by the utility utilizing this system. The SEOC was eventually contacted at 0938 over the commercial telephone line. However, the NARS technical failure was not- corrected during this drill and thus precluded a full demonstration of the system. Based on the above, the technical problem must be corrected and this communication system be demon-( strated during the next scheduled exercise.
At 0942, the dispatcher began notifying the appropriate organizations to report to the SEOC. The notification procedure was completed at 0959, with full staffing and SEOC activation achieved at 1054. All appropriate staff were notified and mobili~ zed pursuant to the plan. However, an inadequacy was identified as the Iowa Disaster Services Division (DSD) failed to notify the Forward Command Post (FCP) of the Alert classification level in a timely manner. The. Iowa DSD was notified of the Alert i at 0938. However, the FCP was not- subsequently notified until 1015 when the Iowa State Highway Patrol representative arrived at This delay occurred in'part because the the SEOC. State Plan fails to specify who is responsible for the initial notification
- to .the FCP of emergency classification levels and to provide instructions to begin activation of the facility. The initial contact with the FCP by the Iowa State Highway Patrol representative was with the expec already been alerted and begun activation,tation . The State that the PlanFCP musthad be amended to reflect this responsibility.
The Iowa DSD representatives who would normally report to the Clinton and Scott County Emergency Operations Centers, Forward Command Post, Emergency Operations Facility, and the Joint Public Information Center, all reported to the SEOC.
During this drill, these representatives were not required to ,
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.( 2. The Iowa Disaster Services Division (DSD) failed to notify -
the Forward Command Post (FCP) of the Alert classification level in a timely manner. The Iowa DSD was notified of the Alert at 0938. However, the FCP was not subsequently noti-fled until 1017 when the Iowa State Highway Patrol represen-tative arrived at the SEOC. This delay occurred in part l because the State Plan fails to specify who is responsible l for the initial notification to the FCP of emergency clas-sification lovels and to provide instructions to begin acti- I vation of the facility. The State Plan must be amended to reflect this responsibility. (NUREG-0654, F.1.e.)
- 3. 'The Iowa State Highway Patrol representative who reported to the Clinton County Emergency Operations Center (CCEOC) did not have dosimetry. As the CCEOC is located in the plume emergency planning zone, dosimetry is required for all emergency workers who report to this facility. This must be demonstrated during the next r;cheduled exercise.
(NUREG-0654, K.3.a.)
- 4. The State Plan is inconsistent regarding what organizations will report to the SEOC. For example, page II-13 indicates that the Department of Commerce and Capitol Security will on page II-10,
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report to the SEOC. However, these organizations are not included. A similar problem exists with the Department of Corrections. The State notification procedures require this organization to report to the SEOC.
However, the plan, in some cases, does not. The appropriate plan amendments must be made to correct the aforementioned concerns. (NUREG-0654, E.2.)
- 5. The State Plan does not indicate how dosimetry is distributed to the State Highway Patrol representatives who enter the EPZ. Therefore, the State Plan must be amended to indicate where the dosimetry (self reading and permanent) is stored and how it is distributed to the Iowa State Highway Patrol. This amendment must also include all organizations Tr i assigned to the State FCP who ;may enter the emergency planning zone. (NUREG-0654, K.3.a.)
2.1.2 State Forward Command Post fFCP)
Objective to be demonstrated: 36.
Objective Number 36, ability to carry out emergency response functions (i.e., activate EOC's, mobilize staff that report to the EOC's, establish communications linkage and complete telephone call down) during and unannounced off-hours drill or exercise, was not adequately demonstrated. -
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(CCEOC) .;and instructed to report to his respective depart-ment, per the Clinton County Plan. These inconsistent in-q(' -l structions may have contributed to the failure to report to the FCP. Based on the above, the inconsistency between the .
State and local plans must be resolvsd and the appropriate amendments made. (NUREG-0654, E.2.)
'7. The State Forward Command Post (FCP) staff was not aware of the. procedures for establishing. the administrative conference line between the SEOC, County EOC's, and FCP.. As a result, the activation of this primary communication system was delayed for thirty-four-minutes. The. appropriate training.must.be provided and the activation of this system must be demonstrated during the next scheduled exercise.
(NUREG-0654, F.1.d.) -
2.2.3 Field Team coordination / Field Monitorine Teams
- Objective to be demonstrated: 36.
Objective' Number 36, ability to' carry ou't emergency response functions'(i.e., activate EOC's,. mobilize staff that report. to the EOC's, establish communication, linkage and complete telephone call down) during an unannounced off-hours drill or exercise, was fully demonstrated.
Field Team Coordination was performed at the Clinton County Emergency Operations Center (CCEOC) by staff from the University Hygienic . Laboratory (UHL) located in Iowa City, Iowa. The field team- coordinator and two radiological field teams were deployed during this drill. At 0950, the UHL was contacted by the State Department of Public Health and instructed to mobilize to the CCEOC. Per documentation provided by the field team coordinator, operational. checks were made of the field monitoring instruments which were subsequently loaded into two vans; both teams departed
. at 1055. The UHL staff ultimately arrived at Clinton County at
- 1232. , ,,
In addition to the radiological nonitoring equipment, both primary and backup communication systems utilized by the field team coordinator and the radiological field monitoring teams were
. transported to the county. Cosmun'ications were established between the field team coordinator and the dose assessment staff located at -the SEOC in Des Moines, Iowa. Tne field . team coordinator also transported the computer, software, and the standard operating procedures and other instructions / manuals required for this function.
All of the UHL staff had the appropriate dosimetry when they arrived.at the county. Since the CCEOC is located in the pluma EPZ, all emergency workers who arrive at this facility must have dosimetry. .
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arrived at this location at 1232.
The State field tocm coordinator and . field teams-The CCEOC was fully activated I
'. with all appropriate organizational staff reporting to the .
facility.
The ability to establish communications was not adequately demonstrated. An area requiring corrective action was identified as the administrative conference line (primary communication link) between the SEOC, FCP, and County EOC's was improperly used by Clinton and Scott Counties. This occurred because Clinton and Scott Counties utilized this line for. a communication link.
However, this action prevented the SEOC from establishing the ad-ministrative conference line between the State and local EOCs for twenty-four minutes.- The SEOC eventually contacted the counties -
on a separate line and instructed them to stay off the line until the conference line was estab?.ished. Based on the above, the ap-propriate training must be provided and the activation. of this system must be demonstrated during the next scheduled exercise.
With the exception of the inadequacy identified with the administrative . conference line, all appropriate communication links were fully demonstrated. The Nuclear Accident Warning System (NARS) was demonstrated successfully to th2 county.
As the CCEOC is within the plume emergency planning zone, dosimetry was required for a.11 emergency workers. All of the l county organizations who repCrted to the EOC were provided with the appropriate dosimetry. However, the Iowa State Highway Patrol officer. who responded to this facility did not have dosimetry. This concern is detailed in Section 2.1.1. of this report. ,
Summary: Objective Number 36 was not adequately demonstrated during this drill.
- - Area Recuirine corrective Action ,,
- 8. The administrative conference line (primary communication link) was improperly used by Clinton and Scott Counties.
i This occurred because Clinton and. Scott Counties utilized ---
this line for a communication' link. However, this action prevented the SEOC from establishing the administrative conference line between the aforementioned organizations for twenty-four minutes. The SEOC eventually contacted the counties on a separate line and instructed them to stay off the line until the conference line was established. The appropriate training must be provided and the activation of this system must be demonstrated during the next scheduled exercise. (NUREG-0654, F.1.d.)
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SUMMARY
OF AREAS REQUIRIN2 CORRECTIVE ACTION
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IOWA STATE OPERATIONS ;
state Emercancy Operations Center (SEOC) -
- 1. Due to. technical complications, the Nuc;. ear Accident Reporting System (NARS) failed.to operate properly during'this drill. The State Emergency Operations Center (SEOC) could not be contacted for notification of the Alert classification level utilizing this I, system. The NARS system never successfully contacted the SEOC during this exercise. Therefore, the technical correction must be made and this system demonstrated during the next scheduled exercise. (NUREG-0654, F.1.d.) i
- 2. The Iowa Disaster Services Division (DSD) failed to notify the Forward Command Post (FCP) of the Alert classification level in a timely manner. The Iowa DSD was notified of the Alert at 0938.
However, the-FCP was not subsequently notifiel until 1017 when the Iowa State Highway Patrol representative arrived at the SEOC.
This delay occurred in part because the State Plan fails to specify who is responsible for the initial notification to the FCP of emergency classification levels and to provide instructions to begin activation of the facility. The State Plan must be amended to reflect this responsibility. (NUREG-0654, F.1.e.)
- 3. The Iowa State Highway Patrol representative who reported to the Clinton County Emergency Operations Center (CCEOC) did not have dosimetry. As the CCEOC is located in the plume emergency planning zone, dosimetry is required for all emergency workers who report to this facility. This must be demonstrated during the next scheduled exercise. (NUREG-0654, K.3.m.)
- 4. The State Plan is'inednsisitent regarding what organizations will f report to the SEOC. For example, page II-13 indicates that the Department of Commerce and Capitol Security will report
~
to the SEOC. However, on page II-10, these organizations are not included. A similar problem exists, with the Department of Corrections. The State notification procedures require this organization to report to the SEOC. However, the plan, in come cases, does not. The appropriate plan amendments must be zade to correct the aforementioned concerns. (NUREG-0654, E.2.)
- 5. The State Plan does not indicate how dosimetry is distributed to the State Highway Patrol representatives who enter the EPZ.
Therefore, the State Plan must be amended to indicate where the dosimetry (self reading and permanent) is stored and how it is distributed to the Iowa State Highway Patrol. This amendment L
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