|
---|
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 ML20248G1701989-09-28028 September 1989 Forwards Insp Repts 50-254/89-19 & 50-265/89-19 on 890821-25.No Violations Noted 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 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 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 ML20246H5721989-08-29029 August 1989 Confirms 890831 Meeting W/Util to Discuss Plant Performance Issues 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 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 ML20245K0681989-06-28028 June 1989 Forwards Safety Insp Repts 50-254/89-14 & 50-265/89-14 on 890605-09.No Violations Noted 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 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 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 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
[Table view] |
Text
s u -(-
4 L .
AU G - 9 1989 -l Docket No. 50-254 l Docket No. 50-265 I- ' Commonwealth Edison Company ATTN: Mr. Cordell Reed E
Senior Vice President
. Post Office Box 767 Chicago, IL 60690
Dear Mr. Reed:
SUBJECT:
OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS
. In a telephone conversation between Mr. Jeff Neal, and Mr. Michael E. Bielby, Sr. ,
arrangements were made for the administration of examinations at the Quad Cities Nuclear Power Station.
The written and oral examinations are scheduled for the week of November 13, 1989.
In order for us to meet this schedule, it will be necessary for the facility to furnish the approved reference material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations" at least 60 days prior to the examination date. Any delay in receiving approved properly bound and indexed reference material will result in a delay in administering the examinations. Mr. ' Jeff Neal has been advised of our reference material requirements, the number of reference material sets that are required, and the examiners' names and addresses where each set is to be mailed.
The facility management is responsible for providing adequate space and accommodations in order to properly conduct the written examinations.
Enclosure 2, " Requirements for Administration of Written Examinations,"
describes our requirements for conducting these examinations. Mr. Jeff Neal has also been informed of.these requirements.
Enclusure 3 contains the Rules and Guidelines that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all applicants are aware of these Rules.
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for Facility Review of Written Examinations." Mr. Jeff Neal has been informed of
'these requirements.
8908170599 090809 %
PDR ADOCK 05000254 y PNV
\\
/Eht
.4-Commo_nwealth Edi, son Company 2 MO ~ 9 1999 -
L ' All reactor operator and senior reactor operator: license applications should be submitted at least'60 days prior to the first examination dates so that
.we will be able to review the training and experience of the applicants, process the medical certif.ications,.and prepare final examiner assignments after applicant eligibility has been' determined.~ If the applications are not: received at least 30 days prior.to the examination dates, it is'likely that a postponement will be necessary.
.This request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing and mailing-the required material. Send. comments regarding this burden estimate or any other' aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555; and to the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington, D.C. 20503.
.Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Michael E. Bielby, Sr. at (312) 790-5586.
Sincerely,
, . L AD Di C3HH C. W P Geoffrey C. Wright, Chief Operations Branch
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines For Written Examinations
- 4. Requirements for Facility Review of Written Examinations See Attached Distribution RIII RIII ' {I(
WF6' M41 MJ Bielby/cg Jor@da) Wri ht N1 %
c_ 7
,, e *
' ~
Commonwealth Edi, son Company' 3 Distribution cc w/ enclosures:
<T. Kovach,. Nuclear Licensing Manager R. L. Bax, Station Manager DCD/DCB (RIDS)
Licensing Fee Management Branch.
Resident Inspector,-RIII Richard Hubbard LJ. W. McCaffrey, Chief, Public.
' Utilities Division J. Neal;. Plant Training-Managar
-cc w/o enclosures:
T.'Ross, Project Manager, NRR K. E. Perkins, Branch Chief, OLB J. J. Harrison, Section Chief, DRP 1
i.
L' .-- _ _ ____-____-___-- -
g , ,
n ENCLOSURE 1 l-L REFERENCE. MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR.
OPERATOR LICENSING' EXAMINATIONS
- 1.' Existing learning objectives, Job Performance Measures and lesson plans
.(including training manuals, plant orientation manual, system j ' descriptions,.. reactor' theory, thermodynamics, etc. )
l' A copy of the facility Job and Task Analysis'(JTA), specifying the knowledge _s and abilities required of an operator at the facility. Each particular knowledge and/or ability will include an importance rating correlating. it to ensuring the health' and the safety. of the public. If.
a JTA'is not furnished, the Knowledges and Abilities Catalog for Nuclear
~
Power P.lant Operators,'NUREG-1122 (1123) will be used to establish H content validity for the examination.
'All Job Performance Measures (JPMs) used to ascertain the competence of the' operators in performing tasks within the control room complex and, as o identified in the facility JTAs,.outside of the control room, i.e., local operations.
Training materials should' include all substantive written material used for preparing applicants for initial R0 and SR0 licensing. The written material-should include learning objectives and the details presented during;1ectures, rather than outlines. Training materials should be identified by~ plant and unit, bound, and indexed.. FAILURE TO PROVIDE COMPLETE, PROPERLY BOUND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE-PRESIDENT 0F. NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING-THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. . Training materials which include the following should be provided:
- System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system.
- - Complete and operationally useful descriptions of all safety-system interactions and, where available, B0P system interactions under emergency and abnormal conditions, including consequences of
- anticipated operator _ error, maintenance error, siid equipment failure.
.______.__________m__._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
ENCLOSURE 1 (Cont'd)
- Training material used to clarify and strengthen understanding of emergency operating procedures.
- Comprehensive theory material that includes fundamentals in the area of theory of reactor operation, thermodynamics, heat transfer and fluid flow, as well as specific application to actual in plant components. For example, mechanical theory material on pumps should include pump theory as well as descriptions of how these principles actually apply to major plant pumps and the systems in which they are installed.(i.e., Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps, Feedwater pumps and Emergency Feedwater pumps).
Reactor Theory material should include descriptions that draw explicit ties between the fundamentals and the actual operating limits followed in the plant (i.e., reactor theory material should contain explanations how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
- 2. Complete Procedure Index (including surveillance procedures, etc.)
- 3. All administrative procedures (as applicable to reactor operation or safety)
- 4. All integrated plant procedures (normal or general operating proc H ures)
- 5. Emergency procedures (emergency instructions, abnormal or special procedures)
- 6. Standing orders (important orders that are safety-related and may supersede the regular procedures)
- 7. Surveillance procedures (procedures that are run frequently, i.e. , weekly)
- 8. Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate)
- 9. Annunciator / alarm procedures
- 10. Radiation protection manual (radiation control manual or procedures)
- 11. Emergency plan implementing procedures
- 12. Technical Specifications (and interpretations, if available) for all units for which licenses are sought.
- 13. System operating procedures l
- 14. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams 2
L
> -b ENCLOSURE 1 (Cont'd)
- 15. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility
- 16. Questions and answers specific to the facility training program which may be used in the written or operating examinations (voluntary by facility licensee)
- 17. Additional material required by the examiners to develop examinations that meet the requirements of these Standards and the regulations.
The above reference material should be approved, final issues and should be so marked. If a plant has not finclized some of the material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is available and that agreement has been reached with the licensee for limiting changes before the administration of the examination. All procedures and reference material should be bound with appropriate indices or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material could result in cancellation or rescheduling of the examinations.
3
ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A single room shall be provided for administration of the written examina-
. tion. -The location of this room and supporting restroom facilities shall be,such as to prevent contact with all other facility and/or contractor
. personnel-during the written examination. If necessary, the facility should make arrangement for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the licensee.
l 2. Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. Minimum spacing should be one applicant per table, with a three foot space between tables.
- 3. Suitable arrangements shall be made by the facility if the applicants are to have lunch, coffee or other refreshments. These arrangements shall comply with Item 1 above and shall be reviewed by the examiner and/or proctor.
- 4. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each applicant's use in completing the examination. The examiner shall distribute these pads to the applicants.
- 5. Applicants may bring pens, pencils, calculators or slide rules into the examination room. Only black ink or dark pencils should be used for writing answers to questions.
- 6. The licensee shall provide one set of steam tables for each applicant.
The examiner shall distribute the steam tables to the applicants. No wall charts, models, and/or other training materials shall be present in the examination room. No other equipment or reference material shall be allowed unless provided by the examiner.
L _-_ - -_-- - - -
7
. . j i
r ,
ENCLOSURE 3
- PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS 4
- 1. _ Check identification badges.
- 2. Pass out examinations and all handouts. Remind applicants not to review examination until' instructed to do so.-
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
During the administration of this. examination the following rules apply:
L Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given' assistance in completing the examination. This must be done after you complete the examination.
READ THE FOLLOWING INSTRUCTIONS:
- 1. Restroom trips are to be limited and only one applicant at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 2. Use black ink or dark pencil only to facilitate legible reproductions.
- 3. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 4. Fill in the date on the cover sheet of the examination (if necessary).
- 5. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 6. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 7. Print your name in the upper right hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
-- ._____________.____w
l, _
m; ...
. ENCLOSURE 3.(Cont'd)
- 8. Before you-turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
l ' 9. If you are using separate sheets, number each answer as to category and L. number (i.e., 1.04,6.10) and skip at least 3 lines between answers to allow space for grading.
- 10. Write "End of Category " at the end of your answers to a category.
- 11. Start each category on a new page.
- 12. Write "Last Page" on the last answer sheet.
- 13. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition.
error resulting in an incorrect answer. Write it out.
.14. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
- 15. Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
- 18. If the intent of a' question is unclear, ask questions of the examiner only.
- 19. When turning in your examination, assembla the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper. 1 1
- 20. To pass the examination, you must achieve an overall grade of 80% or ;
greater and at lease 70% in each category.
- 21. There is a time limit of (6) hours for completion of the examination.
(Or some other time if less than the full examination is taken).
I 2
l
- .
- e, : "+- .
. ENCLOSURE 3 (Cont'd).
- 22. .When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area
'while the examination.is still in progress, ycur license may.be<
denied or revoked.
l 3
@l X L't
- n ..;
[ '
, ENCLOSURE 4
,. 'FiEQUIREMENTS FOR FACILITYLREVIEW 0F WRITTEN EXAMINATIONS L - At the option .of'the Section Chief, .thei facility may review.the written examination up to two weeks prior to:its administration.. This review may-take place at the facility or in-the Regional office. The Chief Examiner will coordinate the details of the' review with the facility. An NRC examiner will always.be present during the review.
. Whenever this option of examination review is utilized, the facility s
reviewers will sign the following statement prior to being allowed access
' to the ' examination. < The~ examination or written notes will NOT be retained by the' facility.
, .a. . Pre-Examination Security Agreement I agree that I will not kncwingly divulge any information
- concerning the replacement,(or initial) examination scheduled
- . for. to.any unauthorized persons. -I-understand that I am not to participate in any instruction involving those reactor operator or-senior reactor operator applicants scheduled to
,: be administered the above replacement (or initial) examination
~from now until after the examination has been administered.
I understand that violation of this security agreement could result'in the examination being voiced.
In addition, the facility staff reviewers will. sign the following statement'after-the written examination has been administered.
- b. Post-Examination Security Agreement-I did not, to the best of knowledge, divulge any information concerning the written examination administered on to any unauthorized persons. I did not participate in providing any instruction to those reactor operator and senior reactor operator applicants who were administered the examination
~
.from the time that I was allowed access to the examination.
u- w 11
- 2. .Regardless of whether the above examination review option is exercised, immediately following the administration of the written examination, the facility staff shall be provided a marked-up copy of the examination and the answer key. The copy of the written examination shall include pen and ink changes made to questions during the examination administration.
If the facility did not review the examination prior to its administration, they will have five (5) working days from the day of the written examination to submit fermal comments. If the facility reviewed the examination prior to'its administration, any additional comments must be given to an examiner prior to his/her leaving the site at the end of the-week of the written examination administration. In either case, the comments will be addressed to the responsible Regional Office by the highest onsite level of corporate management for plant operations, e.g. ,
Vice President for Nuclear Operations. A copy of the submittal will be forwarded to the Chief Examiner, as appropriate. Comments not submitted within the required time frame will be considered for inclusion in the grading process on a case-by-case basis by the Regional Office Section Chief. Should the comment submittal deadline not be met, a long delay in grading the examinations may occur.
- 3. The following format should be adhered to for submittal of specific comments:
- a. Listing of NRC Question, answer and reference
- b. Facility comment / recommendation
- c. Reference (to support facility comment)
NOTES: 1. No change to the examination will be made without submittal of a reference to support the facility comment. Any supporting documentation that was not previously supplied, should be provided.
- 2. Comments made without a concise facility recommendation will not be addressed.
l 1
l 2
_ - _ _ -