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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) 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 ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 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 ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.TAC MA0531 Closed ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS 1999-09-22
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E5581990-11-14014 November 1990 Forwards Safety Insp Rept 50-483/90-18 on 901001-03 & 1105. No Violations Noted ML20058C0941990-10-23023 October 1990 Forwards Safety Insp Rept 50-483/90-16 on 901001-05.No Violations Noted ML20062B5711990-10-18018 October 1990 Forwards Safety Insp Rept 50-483/90-15 on 900816-0930.No Violations Noted ML20059N7151990-10-0505 October 1990 Forwards Request for Addl Info Re Seismic Design Consideration for Plant Refueling Water Storage Tank. Response Requested within 90 Days of Ltr Receipt ML20059H6281990-09-13013 September 1990 Responds to Re Plant Fitness for Duty Program. Any Subsequent Confirmed Positive Test,No Matter How Many Yrs Elapsed Must Be Treated as Second Confirmed Positive,Per 10CFR26,Section 26.27(b)(2) ML20059H2591990-09-0707 September 1990 Advises That 900604 Rev 12 to Operational QA Manual Meets Requirements of 10CFR50,App B & Acceptable ML20059F1031990-08-31031 August 1990 Forwards Insp Rept 50-483/90-14 on 900831.No Violations Noted ML20059E0981990-08-28028 August 1990 Forwards Safety Insp Rept 50-483/90-13 on 900701-0815. Violations Noted Met Requirements of 10CFR2,App C,Section V.G.1 & No Notice of Violation Issued ML20059A1641990-08-10010 August 1990 Confirms Mgt Meeting on 900828 in Region III Ofc to Discuss Items of Mutual Interest,Per 900718 Discussion ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20056A5591990-08-0606 August 1990 Forwards Safety Evaluation Re Util 860108 Steam Generator Tube Rupture Analysis ML20059A7291990-08-0606 August 1990 Provides Comments on 891228 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. NRC Accepts Request to Submit Only Changes to Commitments Significant in Nature ML20058M0741990-08-0202 August 1990 Ack Receipt of 900604 Changes to QA Program Description ML20055J2961990-07-25025 July 1990 Requests Util to Inform NRC of Significant Changes in Estimated Completion Schedule,Per Util Response to Generic Ltr 88-17, Loss of Dhr. Response to Generic Ltr Acceptable ML20055J4391990-07-23023 July 1990 Advises That 900621 Rev 13 to Radiological Emergency Response Plan Acceptable.Rev Includes Clarifications to Emergency Action Levels & Changes to Position Titles & Responsibilities in Plant Organization ML20055G3681990-07-13013 July 1990 Forwards Safety Insp Rept 50-483/90-12 on 900516-0630.No Violations Noted ML20059M8691990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C2821990-02-16016 February 1990 Forwards Safety Insp Rept 50-483/90-03 on 900124-25 & 900131 Telcon.No Violations Noted ML20248C6171989-09-25025 September 1989 Forwards Amend 3 to Indemnity Agreement B-93,reflecting Changes to 10CFR140,effective 890701.Util Requested to Submit Signed Amend to Signify Acceptance ML20248A5621989-09-22022 September 1989 Forwards Safety Insp Rept 50-483/89-17 on 890821-25.No Violations Noted ML20247E9021989-09-0808 September 1989 Forwards Safety Insp Rept 50-483/89-16 on 890821-25.No Violations Noted ML20246K7141989-08-28028 August 1989 Forwards Safety Insp Rept 50-483/89-14 on 890717-0803.No Violations Noted ML20245H5921989-08-11011 August 1989 Advises That 890609 Rev 12 to Operating QA Manual Meets Requirements of 10CFR50,App B & Acceptable ML20245J6271989-08-0101 August 1989 Informs That Facility Chosen for Safeguards Regulatory Effectiveness Review (Rer) Scheduled for Wk of 890918-22. Appropriate Plant Personnel Support Should Be Provided for Three Rer Team Subgroups During Scheduled Review ML20247P7231989-07-31031 July 1989 Requests Addl Info Re 890320 Request for Exemption from 10CFR50,App J Re Interpretation to Leave Leak Chases Plugged During Integrated Leak Rate Test ML20247R7901989-07-28028 July 1989 Forwards Safety Insp Rept 50-483/89-11 on 890601-0715.No Violations Noted ML20247K2811989-07-21021 July 1989 Forwards Addendum to Insp Rept 50-483/88-08 Re Comparison of Results Between Analyses Performed on Liquid Spike & Monitor Tank Sample.Tank Results in Insp Rept 50-483/88-17 ML20247G6461989-07-21021 July 1989 Advises That 871130,880719 & 890727 Simulator Certification Submittals Found Complete for Use in Administering Operating Tests ML20247H7101989-07-20020 July 1989 Requests Reclassification of Diesel Generator a Failure. Failure Should Be Classified as Valid Test & Failure,Not Invalid Failure Due to Listed Reasons ML20247C4531989-07-19019 July 1989 Forwards Safeguards Insp Rept 50-483/89-12 on 890626-0707.No Violations Noted ML20247D1891989-07-17017 July 1989 Ack Receipt of 890628 Submittal of Description of Scope, Objectives & Guidelines for 1989 Emergency Preparedness Exercise Scheduled for 891011.Initial Concerns W/Objective 14 Resolved in Telcon.No Other Concerns Expressed ML20246P9171989-07-17017 July 1989 Discusses Environ Qualification of Bunker Ramo Electrical Penetration Assemblies at Facility,Specifically NRC Concerns Re Low Insulation Resistance Readings on Control Circuits. Qualification File May Be Subj to NRC Audit ML20245K0911989-06-28028 June 1989 Advises That Reactor Operator & Senior Reactor Operator Written & Oral Exams Scheduled for Wk of 891016.Ref Matls, Listed on Encl,Should Be Provided at Least 30 Days Prior to Exams ML20245K3961989-06-22022 June 1989 Forwards Safety Insp Rept 50-483/89-09 on 890401-0531.No Violations Noted ML20244E0661989-06-13013 June 1989 Forwards FEMA Final Rept of 890222 offsite-related Unannounced Drill.W/O Encl ML20244B4371989-06-0707 June 1989 Confirms Plans for Mgt Meeting & Site Tour by AB Davis & Eg Greenman on 890621 in Steedman,Mo.General Plant Performance Will Be Discussed at Meeting ML20247P2001989-06-0101 June 1989 Forwards Safety Insp Rept 50-483/89-08 on 890328-30,0417-20 & 0515.No Violations Noted ML20248C2251989-05-30030 May 1989 Forwards Safety Insp Rept 50-483/89-10 on 890501-05 & 11.No Violations Noted ML20247L8651989-05-24024 May 1989 Concurs W/Util 881130 Response to Generic Ltr 88-11, Indicating That Draft Rev 2 to Reg Guide 1.99 Currently Used to Predict Effect of Neutron Radiation on Reactor Vessel Matls ML20247H5791989-05-23023 May 1989 Requests Listed Info in Order to Make Final Determination That Potential Safety Issues Exists Re Ability of safety- Related above-ground Vertical Liquid Storage Tanks to Maintain Structural Integrity.Nrc Recommended Method Encl ML20247D5071989-05-19019 May 1989 Requests That Licensee Submit Info Requested by Advisory Council on Historic Preservation Re Cultural Resources ML20247D1131989-05-19019 May 1989 Informs of Implementation Schedule for NRC Bulletin 88-011, Item,1.b, Pressurizer Surge Line Thermal Stratification, Mutually Agreed Upon Between NRC & Westinghouse Owners Group During 890411 Meeting ML20247D7281989-05-16016 May 1989 Forwards FEMA Evaluation of Unannounced Drill Testing Mobilization & Activation Portions of State & Local Radiological Emergency Response Plans, from Drill Conducted on 890222.No Deficiencies Noted ML20246K7161989-05-0909 May 1989 Discusses TMI Action Item II.K.3.17 Re ECCS Outages.Nrc Considers Requirements of 10CFR50.72 & 73 & Industry Efforts to Rept on NPRDS to Be Adequate for Reporting ECCS Outages. Special Rept from Plant Not Needed to Fulfill Item ML20245C6921989-04-18018 April 1989 Advises That 890302 Request for Review & Approval of Changes to Unusual Event Initiating Condition for Emergency Plan Sent to Headquarters for Resolution ML20244E3001989-04-14014 April 1989 Forwards Safety Insp Rept 50-483/89-07 on 890403-06.No Violations Noted ML20245A4591989-04-13013 April 1989 Forwards Safety Insp Rept 50-483/89-04 on 890216-0331.No Violations Noted ML20247K5181989-03-30030 March 1989 Advises That 890330 Response to Generic Ltr 88-14, Instrument Supply Problems Affecting Safety-Related Equipment, Satisfactory.Item Closed ML20247G4491989-03-24024 March 1989 Forwards Info on Development of risk-based Insp Guide for Facility as Followup to & 890222 Telcon.Technique Used to Produce risk-based Insp Guide to Differ from Method Being Described in Encl Rept ML20246P4781989-03-21021 March 1989 Forwards Safeguards Insp Rept 50-483/89-03 on 890213-23 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR73.21) 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy 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 ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 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 ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.TAC MA0531 Closed ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207E2711999-05-25025 May 1999 Ack Receipt of in Response to & Insp Rept Confirming Commitment as Stated by M Taylor During Telephonic Exit Meeting on 990413 ML20207A8711999-05-24024 May 1999 Informs That NRR Reorganized,Effective 990328.Forwards Organization Chart ML20207A4131999-05-19019 May 1999 Forwards Insp Rept 50-483/99-03 on 990321-0501.One Violation of NRC Requirements Identified & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20206K6511999-05-10010 May 1999 Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206N3981999-05-10010 May 1999 Responds to Comments & Questions Submitted to NRC Staff Re Recent License Amend Issued by NRC to Callaway Unit 1 License.Provides Context for Conclusion That Reracking of Callaway SFP Maintains Adequate Protection of Public Safety ML20206H1101999-05-0606 May 1999 Forwards Results of Gfes of Written Operator Licensing Exam, Administered on 990407,to Nominated Employees of Facility. Requests That Training Dept Forward Individual Answer Sheets & Results to Appropriate Individuals.Without Encl ML20206H1821999-05-0606 May 1999 Forwards RAI Re Licensee Request for Relief from Certain ASME Code ISI Requirements Submitted by .Response Requested within 30 Days of Receipt of Ltr ML20206F4931999-05-0303 May 1999 Forwards Exam Rept 50-483/99-302 on 990416.Insp Included Evaluation of Applicant for Reactor Operator License ML20205S2571999-04-19019 April 1999 Discusses Plans to Sponsor Testing of Electrosleeved Tubes to Better Understand Behavior of Electrosleeve Matl Under Severe Accident Conditions ML20205Q5461999-04-19019 April 1999 Forwards Safety Evaluation Relief Request from Certain ASME Section XI Requirements for Concrete Containment ISI for Plant ISI Program ML20205K7641999-04-0808 April 1999 Ack Receipt of Re Comments & Questions Concerning Recent Amend to Plant,Unit 1.Response to Comments & Questions Should Be Completed by mid-May ML20205J8701999-04-0606 April 1999 Ack Receipt of ,In Response to NRC Insp Rept 50-483/99-02,dtd 990225 Re Verbal Commitment Made During Exit Meeting for Insp.Understands Next Rev of Security Plan Will Include Increased Min Staffing of Three Armed Guards ML20205J8721999-04-0505 April 1999 Refers to Meeting Conducted in Emergency Operations Facility at Callaway Plant on 990401 Re Plant Performance Review for Plant Completed on 990211.Year 2000 Readiness Issues & New Reactor Licensee Performance Assessment Also Discussed ML20205J9401999-04-0505 April 1999 Forwards Insp Rept 50-483/99-01 on 990207-0330.One Violation Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy IR 05000019/20250011999-04-0202 April 1999 Informs That Version of Topical Rept BAW-10219P,Rev 3 Dtd Oct 1998 & Document 51-5001925-01,dtd 980828 Will Be Marked as Proprietary & Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20205A3821999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Callaway Plant Performance Review for Period 970510-990125. Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20204E7281999-03-18018 March 1999 Ack Receipt of Which Transmitted Rev 28 to Callaway Plant Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Util Determined Changes Do Not Decrease Effectiveness of Plan ML20204E3671999-03-18018 March 1999 Informs That During 990128 Telcon Between D Lantz & H Bundy, Arrangements Were Made for Administration of Retake Written Operator Licensing Exam at Plant,During Wk of 990419 ML20204B7091999-03-15015 March 1999 Informs That Changes Described in ,Submitting Rev 20 to Plant Operational QA Manual,Appear Consistent with Guidelines for non-reduction in Committments ML20204C4241999-03-15015 March 1999 Forwards Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207F4731999-03-0404 March 1999 Discusses 990302 Public Meeting Re Program Updates & Organizational Changes in Emergency Preparedness & Security. List of Attendees & Licensee Presentation Encl ML20207L6491999-03-0404 March 1999 Informs That Util 990111 Response to Request for Addl Info Re Question 4 Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.709(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended 1999-09-22
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. j a ntaco, UNITED STATES !
k NUCLEAR REGULATORY COMMISSION
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Dear Mr. Schnell:
SUBJECT:
OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. W. O. Jessop, and Mr. Paul Sunderland, arrangements were made for the administration of examinations at the Callaway Plant.
The written and oral examinations are scheduled for the week of September 21, 1987.
In order for us to meet this schedule, it will be necessary for the facility to furnish the approved reference material listed in Enclosure 1 " Reference Material Requirements for Operator / Senior Operator Licensing Examinations" at least 60 days prior to the examination date. Any delay in receiving properly bound and indexed reference material wil: result in a delay in administering the examinations. Our examinations are scheduled far in advance with considerable planning to best utilize our limited examiner manpower and to meet the examination dates requested by the various facilities. Therefore, missing the deadline, even by a few days, will likely result in a long delay since it may-not be possible to reschedule examinations at other facilities.
Mr. Jessop has been advised cf our reference material requirements, the number of reference material sets that are required, and the examiners' names and addresses where each set is to be mailed.
The facility management is responsible for providing adequate space and facilities in order to properly conduct the written examinations.
Enclosure 2, " Administration of Reactor / Senior Reactor Operator Licensing
-Written Examinations," describes our requirements for conducting these examinations. Mr. Jessop has also been informed of these requirements. '
l In addition, to better document simulator examinations, the chief examiner
- will have the facility simulator operator record prespecified plant i
conditions (i.e. , plant pressure, temperature, pressurizer level, etc.),
i for each simulator scenario. The candidate will be responsible for i providing this information, along with any appeal of his simulator operating examination. Therefore, the facility training staff should l retain the simulator examination scenario information until all candidates taking the examination have either passed the operating examination or all appeals filed by the candidates who failed the operating examination have been completed.
Enclosure 3, also contains the Rules and Guidance that will be in effect during the administration of the written examination. The facility management is responsible for ensuring that all candidates are aware of these Rules.
8706090288 870601 .
PDR ADOCK 05000483 ** 1 I /V V PDR o
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JUN 811987
, Mr. Schnell 2
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3 All reactor operator and senior reactor operator license applications should normally be submitted at least 60 days prior to the first examination dates so that we will be able to review the training and experience of the candidates, process the medical certifications, and prepare final examiner assignments after candidate eligibility has been determined. If the applications are not received at least 30 days prior to the examination dates, it is likely that a postponement will be necessary.
This request for information was approved by the Office of Management and Budget under Clearance Number 3150-0101, which expires May 31, 1989.
Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D.C. 20503.
Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Paul Sunderland at (312)-790-5771.
Sincerely,
'Or1 gin-T Sfsnod'By C. L Hohl C. .; W. Hehl, Chief Ope. . ions Branch
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Administration of Operator Licensing Written Examir,ations
- 3. NRC Rules and Guidelines For License Examinations cc w/ enclosures:
A. P. Neuhalfen, Manager Quality Assurance Gary L. Randolph, General Manager, Nuclear Operations DCS/RSB (RIOS)
Licensing Fee Management Branch Resident Inspector, RIII Region IV Resident Inspector, Wolf Creek K. Drey See Attached Distribution l RIII/3 ~
RIIs R11[I Sunder 1 d/a 1 Bur ick Hehl
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7 dl5( 4 1 19f7
. .Hr. Schnell 3
- Distribution Chris R. Rogers, P.E.
Utility Division, Missouri Public Service Commission SNUPPS W. O. Jessop, Plant Training Manager cc w/o enclosures:
T. Alexion, Project Manager, NRR
' J. Hannon, Branch Chief, OLB J. Hinds, Acting.Section Chief, DRP R.. W. Cooper, NRR 4
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i ENCLOSURE 1 Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 1. Existing learning objectives and lesson plans (including training
~ manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics,etc.).
Training materials should include all substantive written material used for preparing candidates for initial R0 and SR0 licensing. The written material should be inclusive of learning objectives and the details presented during ' lecture, rather than outlines. Training.
materials should be identified by plant and unit, bound, and indexed.
Failure to provide complete properly bound and indexed plant reference material will result in canceling and rescheduling of the examinations. Training materials which include the following should be provided:
- System descriptions including descriptions of all operationally relevant flow paths, components, controls, and instrumentation.
System _ training material should draw parallels to the actual-procedures used for operating the applicable system.
- Complete and operationally useful descriptions of all safety-system interactions and, where available, B0P system inter-actions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment-failure.
- Training material used to clarify and strengthen understanding of emergency operating procedures. '
,
- Comprehensive theory material that includes fundamentals in the area of theory of. reactor operation, thermodynamics, heat
' transfer and fluid flow, as well as specific application to
! actual in plant components. For example, mechanical' theory material on pumps should include-pump theory as well as i
descriptions of how these principles actually apply to major plant pumps and the systems in which they are installed (i.e.,
Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps, Feedwater pumps, and Emergency Feedwater pumps). Reactor Theory material should include descriptions that draw explicit ties between the_ fundamentals and the actual operating limits ,
followed in the plant (i.e., reactor theory material should i contain explanations how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
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Enclosure 1 2
- 2. Procedure Index (alphabetical by subject).
- 3. .All administrative procedures (as applicable to reactor operation or safety).
_4. All-integrated plant procedures (normal or general operating procedures).
- 5. Emergency procedures (emergency instructions, abnormal or special procedures).
- 6. Standing orders (important orders that are safety related and may supersede the regular procedures).
- 7. Fuel-handling and' core _ loading procedures, (initial core-loading procedure, when appropriate).
- 8. Arnunciator procedures (alarm procedures, including set points).
- 9. Radiation protection manual (radiation control manual or-procedures).
-10. Emergency plan implementing procedures.
- 11. Technical-Specifications.
- 12. System operating procedures.
- 13. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams.
.14. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility.
- 15. Questions and answers that licensee has prepared (voluntary by licensee).
- 16. The following on the plant reference simulator:
- a. List of all readily available initialization points,
- b. List of all preset malfunctions with a clear identification number. The list should include cause and effect information.
Specifically, for each malfunction a concise description of the expected result, or range of results, that will occur upon implementation should be provided. Additionally, an indication of which annunciators are to be initially expected should be given.
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- Enclosure 1 3
- c. - A description of simulator failure capabilities for valves, breakers, indicators and alarms.
- d. Where the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.'e. , ability to vary the size of a 'given LOCA or steam leak, or the ability to cause a slow failure of a component such as a feed pump, turbine generator or major valve (e.g., drifting shut of a main feedwater control valve).
- e. An indication of modeling conditions / problems that may impact the examination.
- f. Identification of significant differences between the simulator and the control room,
- g. Copies of facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR) and containment challenges (BWR) may be provided (voluntary by licensee).
- h. Simulator instructor's manual (voluntary by licensee).
- i. Description of the scenarios used for the training class (voluntary by licensee).
- 17. Additional material required by the examiners to. develop examinations that meet the requirements of these standards and the regulations.
The abo've reference material should be approved, final issues and should be so marked. If a plant has not finalized some of the material, the chief examiner shall verify with the facility that the most complete, up-to-date material is available and that agreement has been reached with the licensee for limiting changes before the administration of the examination. All procedures and reference material should be bound with appropriate indexes or tables of contents so that they can be used efficiently.
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-r ENCLOSUkE 2 Administration of Reactor / Senior Reactor Operator Licensing Written Examinations Operator Licensing Branch requirements are:
- 1. A single room shall be provided for completing the written examination.
The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the licensee.
- 2. Minimum spacing is required to ensure exam integrity as determined by the chief examiner. Minimum spacing should be one candidate per table, with three foot spacing between tables. No wall charts, models, and/or other training materials shall be present in the examination room.
- 3. Suitable arrangements are to be made by the facility if the candidates are to have lunch, coffee, etc. These arrangements shall comply with Item 1 above. These arrangements will be reviewed by the examiner and/or proctor.
- 4. A copy of the written examination and answer key shall be given to the utility training department after the last candidate has turned in his completed examination. The utility shall then have five working days to provide formal written comments with supporting documentation to suggest changes or corrections to the examination and answer key. The utility may provide these comments in writing.to the Chief Examiner before he leaves the site or forward them to the Operator Licensing Section Chief in the appropriate regional office.
- 5. The licensee will provide pads of 8-1/2 x 11" lined paper in unopened packages for each candidate's use in completing the examination. The examiner will distribute these pads to the candidates. All reference material needed to complete the examination will be furnished by the examiner. Candidates can bring pens, pencils, calculators or slide rules into the examination room and no other equipment or reference material is allowed.
- 6. Only black ink or dark pencils should be used for writing answers to questions.
m ENCLOSURE 3 NRC Rules and Guidelines for License Examinations During the-administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write on only one side of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. 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.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWERS BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of ti,e examiner only.
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,. Enclosure 3 2
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
- 18. When you complete your examination, you shall:
- a. Asseable your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still i, progress, your license may be denied or revoked.
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