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Results
Other: AECM-85-0217, Forwards Revised FSAR Section 13.2, Grand Gulf Nuclear Station Training Program, Per Generic Ltr 84-14.Changes Provide Clearer & More Accurate Description of Training Program.Fee Paid, AECM-85-0236, Provides Clarification of 850518 & 0722 Changes to FSAR in Fire Protection Area (Principally in Chapter 9) & Area of Training (Including Section 13.2 & App 9B),respectively, AECM-85-0296, Forwards Rev 4 to Plant Operations Manual,Administrative Procedures 01-S-04-2, Licensed Operator Requalification Training,Safety-Related, to Support NRC Review of Generic Ltr 84-14,per 850910 Request, AECM-86-0024, Forwards Addl Info to Complete Review of Updated FSAR Chapter 13.2 & Requalification Training Procedure & Submits Proposed Revs to Updated FSAR Section 13.2, ML20135G089
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MONTHYEARML20135G0891984-11-0505 November 1984 Rev 4 to Plant Operations Manual,Administrative Procedure 01-S-04-2, Licensed Operator Requalification Training, Safety-Related Project stage: Other AECM-85-0217, Forwards Revised FSAR Section 13.2, Grand Gulf Nuclear Station Training Program, Per Generic Ltr 84-14.Changes Provide Clearer & More Accurate Description of Training Program.Fee Paid1985-07-22022 July 1985 Forwards Revised FSAR Section 13.2, Grand Gulf Nuclear Station Training Program, Per Generic Ltr 84-14.Changes Provide Clearer & More Accurate Description of Training Program.Fee Paid Project stage: Other AECM-85-0236, Provides Clarification of 850518 & 0722 Changes to FSAR in Fire Protection Area (Principally in Chapter 9) & Area of Training (Including Section 13.2 & App 9B),respectively1985-08-14014 August 1985 Provides Clarification of 850518 & 0722 Changes to FSAR in Fire Protection Area (Principally in Chapter 9) & Area of Training (Including Section 13.2 & App 9B),respectively Project stage: Other AECM-85-0296, Forwards Rev 4 to Plant Operations Manual,Administrative Procedures 01-S-04-2, Licensed Operator Requalification Training,Safety-Related, to Support NRC Review of Generic Ltr 84-14,per 850910 Request1985-09-11011 September 1985 Forwards Rev 4 to Plant Operations Manual,Administrative Procedures 01-S-04-2, Licensed Operator Requalification Training,Safety-Related, to Support NRC Review of Generic Ltr 84-14,per 850910 Request Project stage: Other ML20137Y6991985-11-27027 November 1985 Forwards Request for Addl Info Re Review of FSAR & Response to Generic Ltr 84-14 Concerning Training Programs. Response Should Provide Changes to Updated FSAR to Meet 851231 Deadline Project stage: RAI AECM-86-0024, Forwards Addl Info to Complete Review of Updated FSAR Chapter 13.2 & Requalification Training Procedure & Submits Proposed Revs to Updated FSAR Section 13.21986-01-27027 January 1986 Forwards Addl Info to Complete Review of Updated FSAR Chapter 13.2 & Requalification Training Procedure & Submits Proposed Revs to Updated FSAR Section 13.2 Project stage: Other 1985-07-22
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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 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 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 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 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 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 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 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) 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 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 ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam 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 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 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 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 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 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 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) ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified 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 IR 05000416/19900151990-10-17017 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 ML20044B1291990-07-10010 July 1990 Advises That 900618 Rev 17 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable 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 ML20044B1161990-07-0202 July 1990 Forwards Insp Rept 50-416/90-11 on 900519-0615.Violations Noted But Not Cited 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 ML20043A3841990-05-16016 May 1990 Expresses Appreciation for Volunteering to Participate in Emergency Response Data Sys (Erds).Survey Designed to Provide Hardware,Communications,Data Point & Administrative Info for Design of Plant ERDS Encl.W/O Encl ML20043B2421990-05-15015 May 1990 Forwards Notice of Denial of 860902 Applications Filed by Licensees to Amend License NPF-29 & CPPR-119 to Delete Antitrust License Conditions ML20042G5451990-05-0909 May 1990 Forwards Insp Rept 50-416/90-07 on 900416-20.No Violations or Deviations Noted IR 05000416/19900031990-05-0707 May 1990 Ack Receipt of 900430 Response Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/90-03 ML20043A0191990-05-0202 May 1990 Forwards Insp Rept 50-416/90-05 on 900326-30.Violations Noted But Not Cited ML20042F2351990-04-26026 April 1990 Forwards Insp Rept 50-416/90-06 on 900317-0413.Violations Noted But Not Cited ML20042E7641990-04-24024 April 1990 Provides Info Re Interpretation of Bioassay Measurements to Assess Intakes of Radioactive Matls ML20042E7371990-04-16016 April 1990 Forwards Requalification Exam Rept 50-416/OL-89-01 Administered During Wks of 891113 & 27 ML20034A1601990-04-0606 April 1990 Forwards Insp Rept 50-416/90-04 on 900319-22.No Violations or Deviations Noted ML20033G8721990-04-0505 April 1990 Requests Addl Info Re 900216 Request to Defer Installation of post-accident Neutron Flux Monitor to Meet Requirements of Reg Guide 1.97,including Justification Section & NSHC Analysis ML20042E1131990-04-0202 April 1990 Forwards Insp Rept 50-416/90-03 on 900217-0316 & Notice of Violation ML20012E5731990-03-29029 March 1990 Forwards Request for Addl Info Re Licensee 890619 Request to Change Tech Spec for Standby Liquid Control Sys for Response by 900530 ML20042D6771990-03-20020 March 1990 Presents NRC Understanding of Current Status of Unimplemented USIs at Facility,Per Generic Ltr 89-21 ML20033F8381990-03-19019 March 1990 Forwards Exam Rept 50-416/OL-89-02 Administered on 891218-22 ML20012C5871990-03-16016 March 1990 Forwards SER Re Facility Piping Support Calculations for safety-related Piping,Per 890320-23 & 0724-29 Audits.No Significant Safety Concern for Existing safety-related Piping Sys Noted ML20012C3491990-03-0202 March 1990 Forwards Insp Rept 50-416/90-02 on 900120-0216.No Violations or Deviations Noted ML20006G1251990-02-21021 February 1990 Forwards SER Accepting Util 890109,0228 & 1013 Responses to Generic Ltr 88-11,proposing pressure-temp Limits for RCS for Reactor Heatup,Cooldown,Leak Tests & Criticality for 10 Efpy.Revised Limits Requested within 60 Days of Ltr Receipt ML20011E7851990-02-14014 February 1990 Forwards Request for Addl Info on Implementation of Generic Ltr 87-09 Re Sections 3.0 & 4.0 of STS on Applicability of Limiting Conditions for Operation & Surveillance Requirements.Response Requested by 900330 ML20006E1461990-02-13013 February 1990 Forwards Safety Evaluation Approving Licensee 880722 Request for Deviation from Reg Guide 1.97 Re Using Recommended Drywell Pressure Instrument W/Range of -5 Psig to 3 Psig 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 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 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 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 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 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 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 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 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 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 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 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 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
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o UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION 7,,
E WASHINGTON, D. C. 20555 k.
ev 2 Docket No:
50 416 Mr. Jackson B. Richard Senior Vice President, Nuclear Mississippi Power and Light Company P.O. Box 23054 Jackson, Mississippi 39205
Dear Mr. Richard:
SUBJECT:
GRAND GULF NUCLEAR STATION (GGNS) UNIT 1 - TRAINING PROGRAM By letter dated July 22, 1985, Mississippi Pcwer and Light Company submitted proposed changes to the Final Safety Analysis Report (FSAR)
Section 13.2 " Training" and the training requirerents in Appendix 9B " Fire Protection Program." By letter dated September 11, 1985, the licensee submitted the GGNS Licensed Operator Requalification Training Procedure.
This information was submitted for review prior to updating the FSAR and in response to Generic Letter Pa-14, " Replacement and Requalification Training Programs."
The NRC staff has reviewed these submittals and finds that additional information is needed to complete its review. The staff's request for additional information is enclosed.
Sections II, III.A, III.B and III.C of the enclosure provide comments and reauests for additional information regarding the proposed revisions to the FSAR. Since the updated FSAR, including the proposed revisions, is scheduled to be submitted December 1, 1985, it will not be possible to complete our review of the proposed revision in tine to change the updated FSAR subnittal. Therefore, your letter responding to the er. closed request should provide changes to the updated FSAR. Until the staff has completed its evaluation of the proposed FSAR revisions, the GGNS training program should continue to follow the current FSAR criteria and commitments.
In order to meet our present review schedule, you are requested to provide a response to the Enclosure Sections II, III.A, III.B and III.C by December 31, 1985. The response to Enclosure Section III.D, which contains requests for information regarding the requalification training program, snould be provided after INP0 accreditation has been obtained and a revised training procedure acceptable to INP0 has been developed. The revised requalification training procedure should also be submitted.
0512110121 851127 PDR ADOCK 05000416 V
PDR
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Mr. Jackson B. Richard,
If you cannot meet this date, please advise the NRC Project Manager, L. L.
JKintner within 7 days of receipt of this letter.
The reporting and/or recordkeeping requirerrents contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
. Sincerely, Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
See next page
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Local PDR BWRDP4 Reading OELD Edordan BGrimes JPartlow LKin'tner MDuncan-ACRS (10)
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Mr. Jackson.B. Richard
-?-
If you cannot meet this date, please advise the NRC Project Manager, L. L.
Kintner within 7 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, Of1B clearance is not required under P.L.96-511.
Sincerely, Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing Encicsure:
As stated cc w/ enclosure:
See next page
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Mr. Jackson'B. Richard Mississippi Power & Light Company Grand Gulf Nuclear Staiton cc:
Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise Carter, Child, Steen and Caraway Attorney General P.O. Box 651.
Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell Mr. Oliver D. Kingsley, Jr.
and Reynolds Vice President, Nuclear Operations 1200 17th Street, N.W.
Mississippi Power & Light Company Washington, D.
C..
20036 P.O. Box 23054 i
Jackson, Mississippi 39205 Mr. Ralph T. Lally Manager of Quality Assurance Office of the Governor Middle South-Services, Inc.
State of Mississippi P.O. Box 61000 Jackson, Mississippi 39201 New Orleans, Louisiana 70161 Attorney General Mr. Larry F. Dale, Directo-Gartin Building Nuclear Licensing and Safety Jackson, Mississippi 39205 Mississippi Power & Light Company P.O. Box 23054 Mr. Jack McMillan, Director Jackson, Mississippi 39205 Solid Waste Mississippi State Board of Health Mr. R. W. Jackson, Project Engineer 880 Lakeland i
Bechtel Power Corporation Jackson, Mississippi 39206 15740 Shady Grove Road Gaithersburg, Maryland 20760 Alton B. Cobb, M.D.
State Health Officer Mr. Ross C. Butcher State Board of Health Senior Resident Inspector P.O. Box 1700 U.S. Nuclear Regulatory Commission Jackson, Mississippi 39205 Route 2, Box 399
- Port Gibson, Mississippi 39150 President Claiborne County Board of. Supervisors Regional Administrator, Region II Port Gibson, Mississippi 39150
.U.S. Nuclear _ Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. J. E. Cross, General Manager Grand Gulf Nuclear Station Mississippi Power & Light Company P.O. Box /56 Port Gibson, Mississippi 39150 me.
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ENCLOSURE GRAND GULF NUCLEAR STATION 1
REVISED FSAR SECTION 13.2
'l REQUEST FOR ADDITIONAL INFORMATION I.
Introduction i
In a July 22, 1985, letter, Mississippi' Power and Light Company (MP&L) submitted a revised FSAR Section 13.2, Grand Gulf Nuclear Station (GGNS)
Staff Training Program. This submittal was in response to Generic Letter 84-14. An early review was requested to assure this section would be incorporated in the December 1,1985, updated FSAR.
In addition to the revised Section 13.2, the July 22, 1985, submittal contained a summary l
description of Section 13.2 changes and an evaluation of the safety significance of the FSAR changes; changes to the training requirements in FSAR Appendix 9.B Fire Protection Program, and a summary description and evaluation of the safety significance of changes to Appendix 9B.
I Based on our review of the revised FSAR, we conclude that GGNS training programs are in a transition period evolving from initial licensing and plant start-up to long term replacement and retraining programs. During this transition period, GGNS will be preparing for accreditation-by INP0 in accordan' e with the Commi;,sion Policy Statement on Training and c
Qualifications.
The current FSAR contains a number of general and specific consnitments for
-training personnel at GGNS. Attempts were made to integrate some of the FSAR comitments in the revised FSAR with the accreditation process. However, the DHFS and Region position is that the commitments are still valid and may be
-omitted only after experience has been gained with accreditation and the programs are revised based on evaluation. Our coments are divided into general and specific concerns.
II. General Comments 1.
Course Duration In the revised FSAR, MP&L has omitted individual segment duration and provided only an estimate of the total course duration. The MP&L position is that utilizing a systematic approach to training, currently advocated by the NRC, the course duration is not important if the course material has been covered and satisfactory performance demonstrated.
In general, the staff agrees with this premise; however until 10 CFR 55 is revised licensed applicants must abide by requirements in the current version of 10 CFR 55 and must submit NRC Form 398, Personal Qualifications Statement-License, which requires the number of weeks enrolled and other requirements, in each segment of the training program. Therefore, MP&L should establish individual segment " duration" for the training program. As more experience is gained by successful completion of current and future training programs, the course duration may be modified. The staff recommends that facility certification for
+
a each licensing class contain the segment course projected duration and the actual course duration in the individual's application. Please refer to specific comments for additional information.
2..
Evaluation and Criteria The revised licensed program omits methods of evaluation and passing criteria for written examinations. The simulator and in-plant training segments needs some method of evaluating student's progress and completion of each segment. Current and future programs that receive accreditation require a method of evaluation as indicated in the essential elements of acceptable training programs in the Policy Statement.
Licensed training should reference passing criteria for written examinations. Reference to NRC criteria contained in revised Section 4
f 13.2.2.1.4 is adequate.
3 3.
Commitments for Specialized Training
~
The revised FSAR does not contain the details for specialized training on Emergency Diesel Generators (EDG). These commitments were incorporated in Amendment 50 of the FSAR. Although the revised FSAR references EDG training in the licensed and nonlicensed programs, the specific details remain a MP&L commitment. We request that MP&L provide some suitable reference in order to track these commitments or restate the EDG training in the revised FSAR.
III. Specific Comments A.
Licensed Operator Training 13.2.1.1.1 Licensed Operator Training Programs GGNS has the option to license personnel as:
Operators Senior Operators
" Upgrade" Senior Operators (licensed operators at GGNS or a similar BWR)
MP&L estimate of a 42 week course for replacement operators and senior operators appears to reflect current industry practice. MP&L should evaluate the addition of an " upgrade" program for senior operators and include a coprse outline and estimate of course duration in the FSAR.
In addition, as nonlicensed programs are upgraded to include more basic theory and systems training, GGNS may be able to reduce the course durations for licensed operator training.
13.2.1.1.3 Systems Operation Training Several commitments contained in Amendment 47 should be included in the proposed revision. The commitments include:
4
" Classroom presentations for each of the GGNS systems over which the licensed control room operator has control or cognizance."
" Topics" a-j for each of the plant systems".
The reason for retaining these features in this segment is that it contains a more appropriate description of systems training for licensed personnel and that the " topics" can be compared to generic learning objectives. When GGNS is accredited and incorporates the " topics" into the training program, future FSAR revisions may delete the topics.
13.2.1.1.4 Simulator Training At the time Amendment 47 revised the GGNS FSAR, Regulatory Guide 1.149
" Nuclear Power Plant Simulators for use in Operator Training" was not referred in Section 13.2 of the FSAR. Since GGNS now has a plant referenced simulator, LP&L should follow current rulemaking which involves operator J
training and simulators and update future revisions of the FSAR when the rule becomes effective.
13.2.1.1.5 Plant Training We interpret the duration of this phase of the program to be a total of three months for licensed operator and senior operator candidates. Licensed candidates who are in this phase of the program should have no additional j
concurrent duties. The training need not be consecutive but may be distributed over the training cycle. This phase of the program should.
i include reactivity manipulations as required in $55.10. Refer to general comments for evaluation of in-plant training.
13.2.1.1.6 License Examination Preparation
~ refers to current-GGNS practice for hot license candidates which has been approved by Region II. As requested by Generic Letter 84-14, include the reference correspondence in your response.
- The current revision lacks provisions for retraining and the certification by the Plant Manager and Assistant Vice President-Nuclear Productio'n. These features contained in Amendment 47 should be included in the revised program.
13.2.1.1.7 Supervisory Training for Senior Operators Although the program description has been deleted, we believe the topics in Amendment 47 are appropriate. We also recommend this segment of the program be completed prior to or during the three months on shift so the candidate may h:ve the opportunity to apply this knowledge.
In addition, describe how this segment is evaluated.
13.2.1.1.9 BWR Refueling Training
~
This segment of the program should also include training for senior operators who will direct refueling activities as described in 10 CFR 50.54(m)(2)(iv).
13.2.1.1.11, 13-16 Preoperational Testing We concur that the phases of preoperational and low power testing may be deleted from the FSAR.
In FSAR Section 18.1.12, Procedures for Feedback of Operating Experience to the Plant Staff (I.C.5), MP&L developed a program to ensure operating experience would be incorporated into training and retraining programs in a timely manner. Has MP&L incorporated the operating experiences obtained during low power testing and current operations in the replacement training program? If the answer is affirmative, please provide examples.
13.2.1.1.12 Previous Nuclear Experience We concur that previous nuclear training and experience at other facilities may stafisfy the intent of portions of the programs outlined in the FSAR.
The staff recommends that MP&L review Section 5.2.1.7, " Testing in Lieu of Training" of ANSI /ANS 3.1-1981 as an alternative method to evaluate past
' experience thereby excusing individuals from segments in the program. Past experience and training of individuals are required information.in license i
applications which will be reviewed by the Region II staff. Experience criteria is contained in NUREG-1021, Rev. 1 " Operator Licensing Examination Standards".
B.
Nonlicensed Training 13.2.1.2 Training Programs for Nonlicensed Personnel In this proposed section, MP&L does not include method (s) to be used to evaluate student performance, evaluation criteria or feedback into the training program. The'NRC Policy Statement on Training and Qualifications -
indicates that trainee and program evaluation are essential element of an acceptable training program; therefore, they should be contained in the preamble to nonlicensed training and apply to all segments of nonlicensed training.
13.2.1.2.1 GGNS Management Training We recommend the following addition:
If not obtained by previous experience at GGNS, training should also include the GGNS Technical Specifications, past operating experience at GGNS and a suitable supervisory training program for this level of management.
13.2.1.2.2 Nonlicensed Operator Training Program This segment presents course outline and duration for the second level of non-licensed operators (NOB) although course and time for entry level operators (AON) is included, the segment lacks course duration for the A0N position.
In addition, MP&L should evaluate course content for nonlicensed personnel to determine if those members who are assigned to the' fire brigade have sufficient training to fulfill their role in assessment of plant safety-related systems as described in Section 98.7.1 of Appendix 98.
~
. Please refer to General Comments regarding EDG training.
13.2.1.2.1-13.2.1.2.9, Amendment 47 With regard to deleting these paragraphs in Amendment 47:
a) Why was the Station Nuclear Engineering Course deleted?
b) The revised FSAR does not include technician training in Technical Specifications, facility procedures or the emerg/Scy plan. There is no explanation why these subject areas were delettd from the FS.tR.
13.2.1.2.3-5 Revised FSAR With regard to'the revised sections:
There is no reference to training in Mitigatit; Core Damage commensurate with responsibility (Refer to Item II.B.4 of NUREG-0737 and paragraph 18.1.2.2, Amendment 49 of the GGNS FSAR).
Please refer to specialized training for EDGs.
13.2.1.2.6 Shift Technical Advisor (STA) Training Program Comparing the STA program in Amendment 47, MP&L should explain:
a) Why the original course duration of about 22 weeks has been i
decreased to 16 weeks b) Why training in Mitigating Core Damage is not included in STA training
c) Future plans to use STAS as described in the last paragraph of 13.2.1.2.10 in Amendment 49 d) Although Section 13.2.2.2.2 includes STA participation in an annual requalification program, there is no provision for evaluating STA performance in the program.
The staff recommends that STA retraining, particularly simulator exercises, be conducted with shift personnel.
13.2.1.3 General Employee Training We recommend the paragraph in Amendment 47 requiring additional H. P.
training for entry into radiation areas as required by 10 CFR 20 be included in the revised FSAR.
13.2.2 Retraining and Requalification Programs The staff has not reviewed the revised retraining and requalification programs. However, in Section D of the RAI, we have provided comments to the 5
September 11, 1985 letter which contained GGNS Licensed Operator Requalification Program.
C.
Appendix 98 - Fire Protection Program We have reviewed the training and personnel-related areas of the GGNS Fire Protection Plan utilizing Section III-I, Appendix R of 10 CFR Part 50. We conclude that additional information is required to complete our review.
98.2.2.2 Plant Fire Chief We are unable to determine the qualifications of the Plant Fire' Chief. Since the Plant Fire Chief is responsible for developing training and qualifying members of the Plant Fire Brigade, the plan should include the Chief's qualifications (refer to Section I.1.b of Appendix R).
I
.g.
98.2.2.4.1 Fire Brigade Leader The second sentence should state an operator's license in lieu of an operating license.
98.3 Qualifications of Personnel Please reference the administrative procedure or similar document that establishes the training and qualification requirements for personnel responsible for maintenance and testing of the fire protection systems.
98.7.1 Fire Brigade Personnel Regarding the minimum number of operating shift personnel who are not fire brigade members, it appears that the number of licensed personnel does not comply with the table in 10 CFR 50.54(m)(2)(1).
The two fire brigade members who have been trained and are knowledgeable of safety systems should also be identified in 98.2.2.4.2.
Since these members are probably nonlicensed operators, MP&L should reference the qualified operators by title as stated in FSAR 13.2.2.
D.
Requalification Training In response to a staff request, MP&L in a letter dated September 11, 1985, submitted the GGNS Licensed Operator Requalification Program (01-S-04-2, Rev.
4 of November 5, 1984). This submittal is in response to Generic Letter 84-14. At the time of submittal, the requalification program was undergoing revision in preparation for INP0 accreditation. DHFS and Region II have reviewed the Requalification Program and find, with several exceptions, the program meets the current criteria contained in Appendix A of 10 CFR Part 55 and NUREG-0737.
In this RAI, the staff also requests clarification of some parts of the program and provides several recommendations. The
' recommendations were developed from observations of other licensee's programs and does not constitute a regulatory requirement.
When the INP0 accreditation review is complete, MP&L should respond to this section of the RAI and submit the revised program.
3.9 This reference contains the implementing procedure for the Licensed Operator Requalification Program. MP&L should review the following comments and responses to assure the implementing procedure continues to reflect the features contained in the program.
5.2 Since evaluations are conducted utilizing the GGNS simulator, we-recommend that simulator evaluations be included in this section.
6.2 Requalification Program Participants With regard to instructors' participation in the requalification program, we concur with the concept of an appropriate requalification program and the use of guest lecturers. Licensed instructors need additional participation. Our comments are contained in Section 6.5.
Personnel who are exempt from specific areas due to normal duties should be exempted by an administrative procedure which is approved by station management. For example, Section 6.3.3, Station Design Feature Awareness, is normally issued by the Operations Manager and his immediate subordinate; therefore, they may be exempt from this requirement.
With regard to licensed personnel who have recently received a license, they should have been participating in the lecture series and On-the-Job portion of the program.
In addition, recently licensed personnel may be exempt from the annual examination up to 6 months from the' effective date of the license.
-u__.
. 6.3.1 Lecture Series Our interpretation is that the six lectures will be repeated for all shift personnel.
Staff personnel will also be required to attend lectures unless exempted by provisions contained in 6.2 or 6.3.6.
In Section 18.1.12, Amer 4 ment 49, MP&L response to Item I.C.5 of NUREG-0737 included feedback from operating experience in the Required Reading Program. MP&L should evaluate if significant events from operating experience is a suitable topic to add to the lecture series.
6.3.2 Reactivity Control Manipulations With regard to control manipulations, the program lacks evaluations as described in Item I.A.2.1 of NUREG-0737 (Reference Item C.3, Enclosure 1 of the H. R. Denton letter of March 28,1980). These evaluations should also be included in Section 6.7.8.
MP&L should also consider a suitable -
practice period before conducting evaluations.
Our review of other licensees' programs and actual events indicate a lack of practice for Senior Operators in the implementation of the Site Emergency Plan. MP&L should review simulator scenarios to insure that Senior Operators are given periodic practice in implementing the Site Emergency Plan and until they are relieved from duties by facility management.
6.3.5 Examinations With regard to personnel who score less than 80% in a lecture series examination, our position is that retraining and reexamination be conducted in a timely manner. Therefore, remedial assignments and re-examination should be completed within a specified time period.
If the individual does not achieve the passing criteria, management must consider the individual for accelerated training in Section 6.4.1.
. 6.3.6 Annual Requalification Examination Written examination - We recommend a separate paragraph contain criteria for those personnel who may be exempted from attending lectures.
In addition, since lectures in a particular subject may introduce new or revised material, instructors should evaluate if licensed personnel who are exempted would benefit from attendanco at a lecture. Some licensees allow personnel to
" test-out" in order to be exempted from attendance of lectures where new material is presented.
6.5 Requalification for Instructors MP&L should consioer an appropriate period for licensed instructors to participate in shift activities, preferably on a monthly basis.
6.6 Requalification of Inactive Operators The NRC's current position concerning this area is in the revision to Regulatory Guide 1.8, " Personnel Selet: ion and Training." During the interim, MP&L should consider inactive operators; become current in the requalification OJT; perform a period of licensed activities under supervision; and review of lecture series material before the administration of a written and/or oral examination.
Certification by MP&L and NRC review is conducted in accordance with 6 55.31(e).
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