|
---|
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 ML20055H4391990-07-0505 July 1990 Ack Receipt of Providing Scenario for Emergency Preparedness Exercise Scheduled for Wk of 900827 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)) 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 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
[Table view] |
Text
, .
d L 4 f .' .
~
[
August 31, 1989 System Energy Resources Inc.
ATTH: Mr. T. H. Cloninger Vice President,' Nuclear Engineering and Support P. O. Box 23054 Jackson, MS 39205 Gentlemen:
SUBJECT:
REQUALIFICATION PROGRAM EVALUATION In a telephone conversation between Mr. D. Bottemiller, Simulator Supervisor, and Mr. George Hopper, Principal Examiner, arrangements were made for an evaluation of the.requalification program and licensed personnel at the Grand Gulf Nuclear Station. The evaluation visit is scheduled for the weeks of November 13 and 27, 1989. For this visit, the NRC examiners will administer the operating and written examinations.
The NRC examiners will discuss with the appropriate facility personnel and operators the schedule and the process for these examinations. For the examiners to adequately prepare for this visit, it will be necessary for the facility to furnish the approved items listed in Enclosure 1, " Reference Material Requirements" by September 15, 1989. Mr. Bottemiller has been advised of our reference material requirements and where they are to be sent.
NRC reserves the right to postpone NRC administered requalification examinations if the facility generated materials are inadequate for examination preparation.
It is requested that an employee be provided to complete the examination team. The employee shall be an active (per the requirements of 10 CFR 55.53(e) or (f)) SR0 from the Grand Gulf Operations Department. If desired by the facility, and agreed to by the Chief Examiner, an additional employee from the Training Department may be a member of the examination team. This employee shall preferably be an active (per the requirements of 10 CFR 55.53(e) or (f)) SRO, but may be a facility or INP0 certified instructor. These individuals must not be scheduled for an NRC administered examination during this visit, or participate as instructors once selected.
The facility representatives will be required to certify that they did not knowingly compromise any pnrtion of the examination.
I The facility representatives shall be restricted (1) from knowingly I communicating by any means the content or scope of the exam to unauthorized l persons and (2) from participating in any facility programs such as !
instruction, examination, or tutoring in which an identified requalification i examinee (s) will be present. These restrictions shall apply from a date to be determined by the Chief Examiner.
8909120255 890EG1 PDR ALOCK 05000416 \'\
V FDC ut
]
l System Energy Resources, Inc. 2 August 31, 1989 i
i In addition to these two individuals, the assignment of a simulator operator f is requested 28 days prior to the scheduled examination date. The simulator operator will be under examination security restrictions similar to those above. His/her restrictions shall apply from a date to be determined by the Chief Examiner. l The facility management is responsible for providing adequate space and accommodations to properly develop and conduct the examinations. Addition-ally, in order to ensure an efficient and effective examination, day-shift time on the facility's simulator device must be allocated for both the development and administration periods. Enclosure 2, " Administration of Requalification Examinations," describes our requirements for developing and conducting the examinations. Mr. Bottemiller has also been infonned of these requirements. Also, a facility operations management representative should observe the simulation facility examination process at the site.
Enclosure 3 contains the "NRC Rules and Guidance for Examinees"The thatfacility will be in effect during the administration of the written examination.
management is responsible for erisuring that all operators are aware of these rules.
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, includirg gathering, xeroxing, and mailing the required material. Send comments regarding this burden estimate or any other aspect of tnis 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 on the evaluation process, please contact Mr. Charles A. Casto, Chief, Operator Licensing Section 1, at 404/331-5554.
Sincerely, (original signed by T. A. Peebles)
Thomas A. Peebles, Chief Operations Brar.ch Division of Reactor Safety ,
Enclosures:
- 1. Reference Material Requirements
- 2. Administration of Requalification Examinations
- 3. NRC Rules and Guidance for Examinees cc w/encls: (See page 3)
. System Energy Resources, Inc. 3 August 31, 1989 .
- i cc w/encls:
M. Shelley, Training Superintendent C. R. Hutci.inson, General Manager State of Mississippi bec w/encis:
L. Kintner, NRR F. Cartrell, DRP G. Hopper, DRS C. Christensen, Grand Gulf Senior Resident Inspector Document Control Desk
)
i i
RII RII RII RII i l
h) SY GHopper C asto Pee les BMichael:btm 8/>>/89 8/;3/89 8/73/89 8/3[/89 I
i
r:
. ~.
ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS
- 1. For the written examination, the following items must be provided to the NRC 60. days' prior to the examination date:
Proposed ' R0 and SRO requalificatian written e amination test items.
(A minimum of 350:per section of the examination.)
Since the written examination is open reference, examination items must meet the following:
- a. Items that require only memorization or recall are not permitted.
- b. Items should require that the examinee comprehend, interpret, integrate,.or apply available information.
- c. Items should contain situations, aspects, or conditions that do not duplicate lesson plans or references.
- d. Items should require examinees to locate and use references.
The . written' examination will be composed of two sections, each designed to be completed in 1-1/2 hours. Each section will be separate.
Section'A, " Plant Operations," will be administered on a static simulator; Section B, " Limits and Controls," will be administered in a classroom setting. Section A is designed to evaluate the operator's knowledge of plant: systems, integrated plant operations, and instrumentation and controls. In addition, ' recognition of Technical Specification LCOs and the operator's ability to diagnose postulated events should be evaluated.
Section B of the written examination is designed to evaluate the ability of the operator to analyze a given set of conditions and determine the proper procedural and/or administrative guidance.
- 2. All reference material and objectives for the proposed test items.
For the simulation facility, the following items must be provided to the NRC 60 days prior to the examination date:
a.. A minimum of 15 scenarios.
The_ scenarios should sample areas such as LERs, emergency and abnormal procedures, and design and procedural changes that exercise the crew's ability to use facility procedures in accident prevention and mitigation. .The scenarios should evaluate each crew member as appropriate to his/her license, and shall exercise their ' abilities in the use of Emergency Operating Procedures, Technical Specifications, and the
- Emergency Plan. The scenario's net time (not including time spent on briefings, setup or simulation facility problems) should average 50 minutes, based upon real time performance.
. = _ _ _ _ - _ - - _ _
l Enclosure 1 2 1
For the plant walk through examination, the following items must be provided to the NRC 60 days prior to the examination date:
- a. A list of systems and topics appropriate to the plant walk through examination that were covered during the two-year requalification cycle and are important to safety. All reference material required to support an examination on these topics should be provided.
- b. Seventy five (75) job performance measures.
These performance measures should be both in plant and control room operator functions that are required for the safe operation of the facility. They shall include acceptable performance criteria.
- c. Any additional reference material required for examination preparation will be requested by the examination team.
- 3. A sampling plan shall be provided by the facility which indicates the relative emphasis of topics which were included in the last two years of requalification training.
- 4. All Requali'ication Training material shall be provided by the facility.
Emergency, abnormal, normal, administrative and surveillance procedures, to the extent that they are applicable to licensed operators, shall also
~
be provided.
. i l.
i ENCLOSURE 2 ADMINISTRATION OF REQUALIFICATION EXAMINATIONS
- 1. Approximately twenty percent of the facility licensed operators shall be selected for evaluation. Normally the crew currently in the requalifica- z tion cycle 'will be selected. A random sample without replacement will be '
used to preclude a satisfactory operator from being subject to reexamina-tion by the NRC during the term of the license. The sample will include.
other shift (s) made up of licensed personnel who are not routinely .
performing shift duties. i
- 2. The simulator and a simulator operator (s) will be provided for examination development. The date(s) and duration of time needed to develop the examinations will be agreed upon by the Chief Examiner and the facility.
- 3. The reference material used in the simulator will be reviewed by the Chief Examiner. No material will be used that is solely used for training.
- 4. A single room shall be provided for completing Section B of the written examination. The location of this room and supporting rest room facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the examination.
- 5. Minimum spacing is required to ensure examination integrity as determined by the chief examiner. Minimum spacing should be one examinee 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.
- 6. Copies of reference material for Section B of the written examination will be available to each examinee. The reference material will be reviewed by the Chief Examiner and will consist of Technical Specifications, operating / abnormal procedures, administrative procedures, Emergency Plans as available to the plant operators.
- 7. Video taping capabilities may be utilized. The facility should contact the Chief Examiner for restrictions related to its usage.
- 8. Since common tasks and detailed systems knowledge will be probed during the walk through portion of the operating test, operators will be requested not to discuss the walk through with other examinees until after the complete examination has been administered.
- 9. An attempt will be made to distinguish between R0 and SR0 knowledge and abilities to the extent that such a distinction is supported by the facility training materials.
L ENCLOSURE 3 NRC RULES AND GUIDANCE FOR EXAMINEES
- 1. Use black ink or dark pencil DNLY to facilitate legible reproductions.
- 2. Print your name in the blank provided on the cover sheet of the examination.
- 3. Fill in the date on the cover sheet of the examination, if necessary.
- 4. Answer each . question on the examination. If additional paper is required, use only the lined paper provided by the examiner.
- 5. Use abbreviations only if they are commonly used in facility literature.
- 6. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 7. Show all calculations, methods or assumptions used to obtain an answer to a mathematical problem, whether asked for in the question or not.
- 8. Unless solicited, the location of references need not be stated.
- 9. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWERS BLANK.
- 10. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only.
- 11. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
- 12. Rest room trips are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise.
- 13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
- 14. Each section of the examination is desityned to take approximately 90 i
minutes to complete. You will be given two hours to complete each I
section for a total of four hours.
l l
1 l
l
(( . .
p J .
Enclosure 3 2 lm, f
- 15. Due to the existence of' questions that will require all- examinees to refer to the same indications or controls, particular care must be taken to maintain individrvi examination security and avoid any possibility of compromise or appearance of cheating.
- 16. When you are finished and have turned in 'your completed examination, the proctor will provide guidance on leaving the examination area.
- 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.
I 1
l 1
-- - -_-__ - -- ___-_-__ _ _ - _ _ _ _ - _ _ _