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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G4511990-11-21021 November 1990 Forwards List of Unimplemented GSIs at Facility,Per Generic Ltr 90-04.Timely Completion Requested IR 05000416/19900221990-11-15015 November 1990 Forwards Insp Rept 50-416/90-22 on 901022-26.No Violations or Deviations Noted.W/O Encl ML20058E8921990-10-30030 October 1990 Forwards Insp Rept 50-416/90-20 on 900915-1019.No Violations or Deviations Noted ML20058B4321990-10-25025 October 1990 Grants 900709 Request for Relief from Requirements for Leakage Testing of RCS in ASME Code,Section Xi.Se Encl ML20062B1681990-10-19019 October 1990 Approves Scheduled Implementation of Dcrdr Mods by 920731 (Fifth Refueling Outage) ML20062B1701990-10-19019 October 1990 Confirms That Util Actions in Comply W/Generic Ltr 89-04 Guidance Re Inservice Testing Programs ML20058B0771990-10-17017 October 1990 Ack Receipt of 901002 Responses Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/90-15 ML20062B3281990-10-15015 October 1990 Advises That 900924 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2, Part 2 'Vendor Interface for Safety-Related Components,' Acceptable ML20058A5711990-10-12012 October 1990 Forwards Insp Rept 50-416/90-18 on 900917-21.No Violations or Deviations Noted ML20062B6991990-10-12012 October 1990 Requests Completion of Analyses of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20058A2471990-10-11011 October 1990 Forwards Insp Rept 50-416/90-16 on 900827-31.No Violations or Deviations Noted ML20059N4931990-10-0101 October 1990 Informs That Util Responses to Generic Ltr 88-01 Acceptable, W/Exception to Responses Re Tech Spec Changes.Safety Evaluation & Technical Evaluation Rept Encl ML20059L3891990-09-0606 September 1990 Forwards Insp Rept 50-416/90-15 on 900721-0817 & Notice of Violation.Nrc Believes Negative Trend in Area of Attention to Detail Needs to Be Addressed ML20056B3431990-08-20020 August 1990 Forwards Insp Rept 50-416/90-13 on 900709-13.Violations Noted But Not Cited ML20058P8081990-08-15015 August 1990 Discusses Util 891221 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Recommends That Testing of MOVs in-situ Be Performed Under Design Basis Conditions ML20059A0751990-08-0606 August 1990 Advises That Rev 9 to Operational QA Manual,GGNS-TOP-1A, Acceptable,Per ML20058L5941990-07-31031 July 1990 Advises That 900717 Rev 17 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20058M4181990-07-25025 July 1990 Forwards Insp Rept 50-416/90-12 on 900616-0720.No Violations or Deviations Noted ML20055G5221990-07-18018 July 1990 Forwards Safety Evaluation Concluding That Procedures Generation Package Must Be Revised by Addressing Both Programmatic Improvements & Results of EOP Insp ML20055G5301990-07-17017 July 1990 Forwards Fr Notice of Withdrawal of Applications for Amend to License NPF-29 to Delete Certain Test,Vent & Drain Valves from Tech Spec Table 3.6.4-1 ML20055G0321990-07-16016 July 1990 Forwards Safety Evaluation Re Criticality Analysis of Fuel in Spent Fuel Racks Including Effect of Boraflex Gaps Which Could Occur Up Through Cycle 4.Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 ML20055F9051990-07-16016 July 1990 Forwards Safety Evaluation Supporting Criticality Analysis for Cycle 5 Fuel in Spent Fuel Storage Racks IR 05000416/19900081990-07-12012 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/90-08 ML20055E5691990-07-0505 July 1990 Grants 900426 Application for Withholding of ANF-90-060(P), Criticality Safety Analysis for Grand Gulf Spent Fuel Storage Racks W/ANF-1.4 Fuel Assemblies, Per 10CFR2.790(b)(5)) ML20055H4391990-07-0505 July 1990 Ack Receipt of Providing Scenario for Emergency Preparedness Exercise Scheduled for Wk of 900827 ML20055E8871990-07-0202 July 1990 Forwards Notice of Withdrawal of Util 900504 Application for Amend to License NPF-29,extending Implementation Date for Amend 65 to License,Per 900606 Request ML20055F2061990-06-29029 June 1990 Advises That 900618 Rev 3 to Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20058K5161990-06-28028 June 1990 Advises That Units 1 & 2 Transferred to Project Directorate IV-1,effective 900604 ML20055E2441990-06-21021 June 1990 Grants 880630 Request to Withhold GE MDE-80-0485, Tech Spec Improvement Analysis for Reactor Protection Sys for Grand Gulf Nuclear Station,Units 1 & 2, Per 10CFR2.790 ML20059M8491990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248C9051989-09-26026 September 1989 Forwards Insp Rept 50-416/89-20 on 890828-0901.No Violations Noted ML20247N2171989-09-18018 September 1989 Requests Radius & Thickness (Rt),(Rt)Ndt Values for Reactor Vessel Flange Matl & Upper Shelf Energy Values for Matls,Per Generic Ltr 88-11,by 891015 ML20247G6681989-09-12012 September 1989 Forwards Insp Rept 50-416/89-19 on 890715-0825 & Notice of Violation ML20247G6571989-09-0808 September 1989 Advises That Rev 19 to Emergency Plan Consistent W/Planning Stds of 10CFR50.47(b) & Requirements of App E to 10CFR50 ML20247D8591989-09-0101 September 1989 Ack Receipt of 890821 & 25 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps ML20247A9331989-08-31031 August 1989 Advises That Requalification Program Evaluation Scheduled for Wks of 891113 & 27.Facility Should Furnish Approved Items Listed in Encl 1 Ref Matl Requirements by 890915 ML20246G3541989-08-25025 August 1989 Forwards Requests for Addl Info Re Gaps in Boraflex of High Density Spent Fuel Racks.Response Requested by 891015 ML20246N0771989-08-23023 August 1989 Requests That Util Provide Ref Matls for Reactor Operator & Senior Reactor Operators Licensing Exams Scheduled for Wk of 891218.Info Must Reach NRC by 891012.Related Exam Requirements Info Encl ML20246D7961989-08-21021 August 1989 Forwards Safety Evaluation Granting Util 880524 Requests for Relief from Certain Requirements in ASME Code,Section XI Re Inservice Insp Program IR 05000416/19890101989-08-21021 August 1989 Ack Receipt of Informing NRC of Action Taken to Correct Violations Noted in Insp Rept 50-416/89-10 IR 05000416/19890141989-08-15015 August 1989 Ack Receipt of 890712 & 13 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-14. Implementation of Corrective Actions Will Be Examined During Future Insps IR 05000416/19890161989-08-15015 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-16. Implementation of Corrective Actions Will Be Examined During Future Insps ML20245K2511989-08-11011 August 1989 Advises That 890609 Rev 8 to Operational QA Program Consistent w/10CFR50.54(a) & Acceptable ML20245J7961989-08-0202 August 1989 Forwards Insp Rept 50-416/89-18 on 890710-14.No Violations or Deviations Noted ML20247P6571989-07-31031 July 1989 Provides Evaluation of Util Proposed Revised PASS Test Procedure,Per .Util Commitments to Document Changes to PASS Sampling Program Acceptable ML20248C9371989-07-28028 July 1989 Forwards Insp Rept 50-416/89-17 on 890616-0714 & Notice of Violation IR 05000416/19890081989-07-25025 July 1989 Ack Receipt of 890621 & 28 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/89-08 ML20247G6771989-07-21021 July 1989 Forwards SER Accepting Licensee Commitment to Install ex-core Neutron Flux Monitoring Instrumentation Meeting Requirements of Reg Guide 1.97,Rev 2,prior to Restart Following Fourth Refueling Outage ML20247G7311989-07-20020 July 1989 Denies 890706 Request for Extension Re Payment of Invoices. Suggests That Util Pay Outstanding Balances & Any Amount Determined to Be Overpayment Will Be Refunded by NRC ML20247L1081989-07-18018 July 1989 Forwards Info Documenting Info Received Between Region II & Concerned Individual.No Attempt Made to Ascertain Accuracy of Info Supplied by Individual.Requests Findings within 45 Days.Encl Withheld (Ref 10CFR2.790(a)(6) & (7)) 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5811999-06-30030 June 1999 Advises That Version of Info Submitted in 990504 Application & Affidavit Re Engineering Rept ME-98-001-00,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 as Amended ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20195G3811999-06-0909 June 1999 Ack Receipt of ,Which Transmitted Emergency Plan Procedure 10-S-01-1,Rev 103,under Provisions of 10CFR50, App E,Section V ML20195G2971999-06-0909 June 1999 Ack Receipt of Re Emergency Plan Procedure 10-S-01-1,rev 104.No Violations Identified & Changes Subject to Insp to Confirm Effectiveness ML20195G3511999-06-0909 June 1999 Ack Receipt of 980831 & 1022 Ltrs,Which Transmitted Changes to Grand Gulf Emergency Plan,Rev 36 & 37,under Provisions of 10CFR50,App E,Section V ML20207D3351999-05-27027 May 1999 Forwards Insp Rept 50-416/99-05 on 990321-0501.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A6961999-05-21021 May 1999 Forwards Insp Rept 50-416/99-06 on 990419-23.No Violations Noted.Determined That Fire Protection Program Was Implemented IAW Requirements of License & GL 86-10.One Unresolved Item Noted Re fire-induced Failures on Equipment ML20206U3851999-05-18018 May 1999 Forwards Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A7561999-05-17017 May 1999 Ack Receipt of Which Transmitted Exercise Scenario for Emergency Plan Exercise Scheduled for 990623. Some Parts of Exercise Scenario Package Not Submitted & Being Developed ML20206N3921999-05-11011 May 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20206K1261999-05-0707 May 1999 Informs That on 990407 NRC Administered Gfes of Written Operator Licensing Exam.Facility Did Not Participate in Exam.Copy of Master Exam with Answer Key Encl.Without Encl ML20206E0571999-04-29029 April 1999 Discusses EOI 960418 Request for License Amend for GGNS That Would Permit Addl Method of Fuel Movement & Loading in Core When Control Rods Removed.Determined That Insufficient Info Provided to Permit Completion of Review ML20206B0951999-04-23023 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/99-01 & NOV .Reply Found to Be Responsive to Concerns Raised in Nov.Implementation of C/As Will Be Reviewed in Future Insps ML20206B3601999-04-23023 April 1999 Forwards Insp Rept 50-416/99-04 on 990131-0320.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206E7661999-04-19019 April 1999 Submits Summary of 990415 Meeting Conducted in Port Gibson, Mi Re Results of Plant Performance Review Completed on 990211 & Transmitted on 990319.List of Attendees Encl ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls IR 05000416/19980131999-04-0606 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/98-13 .Discussions on 990330 Resulted in Addl C/A Commitments to Address Violation Re Onsite Investigation ML20205J1051999-03-29029 March 1999 Forwards Objectives for Plant,Unit 1 1999 FEMA Emergency Plan Exercise Scheduled for 990623 ML20205E8701999-03-19019 March 1999 Advises of Completion of Plant Performance Review on 990211 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Isolated Examples of Failure to Follow Procedures Noted ML20207L3621999-03-0303 March 1999 Advises That Effective 990217,NRC Project Mgt Responsibilities for Grand Gulf Nuclear Station Transferred to Sp Sekerak 1999-09-09
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4 August 23, 1989 System Energy Resources, Inc.
ATTN: Mr. T. H. Cloninger Vice President, Nuclear Engineering and Support P. O. Box 23054 Jackson, MS 39205 Gentlemen:
SUBJECT:
REACTOR OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In' a telephone conversation between Mr. D. Bottemiller, Simulator Supervisor, and Mr. G. Hopper, NRC Region II Operator Licensing Section, arrangements were made for administration of the replacement , examinations at the Grand Gulf Nuclear Station.
The written examinations are scheduled for the week of December 18, 1989. The simulator / operating examinations are scheduled for December 19 - 22, 1989, at the Grand Gulf simulation facility. The plant oral examinations are scheduled for December 19 - 22, 1989.
In order for us to meet the above 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 Examination," by October 12, 1989. Any delay in receiving approved, properly bound and indexed reference material, or the submittal of inadequate or incomplete reference material will result in the examinations being rescheduled.
Mr. Bottemiller has been advised of our reference material requirements 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. Bottemiller has also been informed of these requirements.
'In addition, to better document simulator examinations, the Chief Examiner will have the facility simulator operator record prespecified plant conditions (i.e., plant pressure, temperature, pressurizer level, etc.), for each simulator scenario. The candidate will be responsible for providing this information, along with any appeal of his simulator operating examination.
Therefore, the facility training staff should retain the simulator examination scenario information until all candidates taking the examination have passed the operating examination, accepted the denial of their license, or had their appeals completed.
890908o031 890823 ADOCK 05000416 $
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se System Energy Resources, Inc. - 2 August 23, 1989-
- Enclosure 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 candidates are aware of these Rules.
All completed reactor operator and senior reactor operator license application-information should be submitted at least 30 days before the first examination
. dates so that we will be able to review the; training and experience of the
-candidates, process the medical certifications, and prepare final examiner-assignments after candidate eligibility has been determined.
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 Servic'es, Office of Information Resources Management, U. S. Nuclear Regulatory Commission, Washingtonm D. C. 20555; and to the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington, D. C.
20503.
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 Examination." Mr. Bottemiller has been informed of these requirements.
Thank you - for your consideration .in this matter. . If you have any questions regarding . the examination procedures and requirements, please contact Mr. Charles A. Casto, Chief, Operator Licensing Section 1, at 404/331-5554.
Sincerely, (original signed by Frank Jape)
Thomas A. Peebles, Chief Cperations Branch Division of Reactor Safety
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 cc w/encls:
M. Shelley, Training Superintendent C. R. Hutchinson, General Manager State of Mississippi
' System Energy Resources, Inc. 3 August 23, 1989 bec w/encls:
L. Kintner, NRR F.. Cantrell, DRP <
G. Hopper, DRS C. Christensen, Grand Gulf Senior Resident Inspector Document Control Desk RII RII RII RII b
BMichael:btm AV GHopper dW CCaYto h
TPeebles 8/J)/89 8/33 / 89 8/p3/89 ,Jpj /89 l-L _- -
- r T
ENCLOSURE 1 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 descriptions,reactortheory, thermodynamics,etc.).
A copy of the facility Job and Task Analysis (JTA), specifying the knowledges ' 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 Plant Operators, NUREG 1122 (1123) will be used to establish 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 identified in the facility JTAs, outside of the control room, i.e., local operations.
Training materials shall include all substantive written material used for preparing applicants for initial R0 and SR0 licensing. The written material shall include learning objectives and the details presented during lectures, rather than outlines. Training materials shall be identified by plant and unit, bcund, 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 OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERI AL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTP0NED. Training materials which include the following shall be l provided:
1 L - 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 l interactions and, where available, B0P system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
5 >
' Enclosure 1 -2 4
-: : Comprehensive theory material that includes fundamental's 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 shall 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 shall include descriptions _ that-draw explicit ties between the fundamentals. and the actual operating
~
limits followed in the plant. (i.e., reactor theory . material .shall contain explanations how principles relate to the actual curves ~used by operators to verify shutdown margin or calculate an ECP).
!2. Complete Procedure' Index (alphabetical by subject).
3.. All administrative: procedures . (as applicable to reactor operation or
. safety).
- 4. All integrated plant procedures. (normal or general operating procedures).
- 5. instructions, abnormal or special Emergency procedures . ) procedures (emergency
-6. Standing orders (important orders that are safety-related and may-supersede the regular procedures).
'7. . Fuel-handling and core-loading procedures.
-8. Annunciator procedures-(alarm procedures, including set points).
9.. Radiation protection' manual (radiation control manual or procedures).
- 10.- Emergency plan implementing procedures.
11.. Technical Specifications..
- 12. -System operating procedures.
- 13. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams.
- 14. Technical Data Book, and/or picnt curve'information as used by operators and facility precautions, limitations, and set points (PLS) for the facility.
- 15. Questions and answers that the facility licensee has prepared and which may be used in the written or operating examinations.
. 16.- The following on the plant reference simulation facility:
- a. List of all readily available initialization points. j l
-. i c' .
'u- Enclosure 1 3
- b. List of,all preset malfunctions with a clear identification nur;her.
The list should include cause and effect information. Specifict11y, forL each malfunction, a concise description of the expected result, or range of results, that'will occur upon implementation should be provided. .' Additionally,.an indication of which annunciators are to be initially expected should be given.
- c. _ A description of simulator capabilities for valves, breakers,-
indicators, and alarms.
- d. _W here the! capability exists, an explanation of the ability to vary the severity.' of a particular malfunction should be provided, i.e. ,
ability. to vary the size of a given LOCA or steam leak, or the ability to cause'a slow failure of a component such es a feed pump, turbine Lgenerator or major valve (e.g., drifting shut of 'a main -
feedwater control valve).-
- e. .An identification of modeling conditions / problems that may impact ~
the examination.
- f. Identification of any known-' Performance Test Failures not yet completed.
- g. Identification of significant differences between the simulator and the reference plant's control room.
- h. Copies of facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR), and containment challenges (BWR) shall be provided.
- i. Simulator instructors manual.
- j. Description of the scenarios used for the training class (voluntary bylicensee).
- 17. Surveillance procedures (procedures that are frequently run, i.e., weekly ordaily).
- 18. 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 If a plant has not finalized some of the material, the Chief Examiner
- l. marked.
L- 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 indexes or tables of contents so that they can be used efficiently. Failure to provide complete, properlypbound and indexed plant reference material will result in the material being returned and could result in cancellation or rescheduling of the examinations.
b L ____
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ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. - A singlet room shall .be provided for completing the written examination.
The110 cation of.thisTroom and supporting restroom facilities shall be such as to Lprevent contact with a11' other facility and/or contractor
- personnel during- the duration of the written examination. If'necessary, the facility should make' arrangements for the use of. a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility- of. the : licensee.
.2. ' Minimum spacing is required to ensure examination integrity.as determined by : the ; Chief Examiner. . Minimum spacing should be one candidate per table, . with' a 3-foot' space between tables. No wall charts, models,
.and/or other training materials shall be present in the examination room.
'3.; Suitable arrangements shall be made by the facility if the candidates are These arrangements shall to have lunch, coffee, or other refreshments.
comply with ' Item 1 above. These arrangements shall be reviewed by the examiner. and/or proctor.
- 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working days to provide formal written comments with supporting documentation on the, examination and answer key to the Chief Examiner or to the Regional Office Section Chief.-
- 5. :The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each candidate's use in completing the examination. The examiner shall distribute these pads to the candidates. All reference material needed to complete the examination shall be furnished by the examiner. Candidates can bring pens, pencils, calculators, or slide rules into the examination room, and no other equipment or reference material shall be allowed.
, 6. Only blank. ink or dark pencils should be used for writing answers to questions.
- 7. 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 L the examination room. No other equipment or reference material shall be
! allowed unless provided by the examiner.
l .. 4 l i
- f 1
ENCLOSURE 3 PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
- 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:
- 1. 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.
t N.{ , ',[
- f. .
g ..
L Enclosure 3 2
- 8. Before you turn in your. examination, consequently number each answer t . sheet,' including.any additional pages inserted when writing your answers on the examination question page.
. 9; _'If you are using separate sheets.. number each answer as to category and l numberL(i.e., 1.04,6.10) and skip at least 3 lines between answers to alinw space for grading..
- 10. Writh "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.
P 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 LAND 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, assemble the completed examination with examination questions, examination aids, and answer sheets. In addition, turn in all scrap paper.
.20. To pass the examination, you must achieve an overall grade of 80 percent or greater and at least 70 percent in each category.
21p 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).
122. 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, your license may be denied or revoked.
ENCLOSURE 4 REQUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS
- 1. At the option of the Chief Examiner, the 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 reviewers will sign the following statement prior to being allowed access to the examination. The examination or wr:tten notes will not ' by retained by the facility.
- a. Pre-Examination Security Agreement I agree that I will not knowingly 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 voided.
Signature /Date 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 my 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 i
operator and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination.
Signature /Date l.
L_ -- ___ __ _
j
. Enclosure 4 2
- 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 administra-tion, they will have five (5) working days from the day of the written examination to submit formal 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 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 wit,out submittal of a reference to support the facility comment. Any supporting documentation that was not previously supplied, should be 4 provided.
- 2. Comments made without a concise facility recommendation will not be addressed.
- 4. A two-hour post examination review may be held at the discretion of the Chief Examiner. If this review is held, the facility staff should be infonned that only written comments that are properly supported will be considered in the grading of the examination.
l
-,_v4-__.-. .. . __________ _ _ - _ . _ _