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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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. r y March 10,'1989-
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' Docket No. 50 483 DISTRIBUTION:
155Td6711esj NRC & Local PDRs '
PDIII-3 Wf" GHolahan MVirgilio JHannon Mr. Donald F. Schnell TAlexion PKreutzer Senior Vice President - Nuclear OGC-WF1 EJordan i Union Electric Company BGrimes ACRS(10) l Post Office Box 149 PDIII-3 Gray j St. Louis, Missouri 63166 j
Dear Mr. Schnell:
The staff has completed its review of your initial Sinvjlator Certification submittal and of the additional information submitted in response to our comments on this submittal. The staff's review has identified several areas >
in which there is, as yet, inadequate infnrmetion and data- to ensure complete ,
, documentation of your certification. These areas are described in Enclosures 1 and 2.. You are requested to provide the additional data and your reply to.the questions no later than April 28, 1989 so that this information may be probptly J incorporated in the staff's' records. If you cannot meet thic-schedule, please l contact me as soon as possible.
As-indicated above, our review is only to ensure com)1eteness of documentation.
The review- does not, nor is it intended to, verify t1e accuracy cf the data or statements made in the certification, nor provide NRC approval of the acceptability of a particular simulator for use.in administering operating: tests. .j This request for information affects fewer than 10 respondents;.therefore, OMB clearance is not. required under Pub. L.96-511.
If you require additional information or clarification about this-letter or
- its enclosures, please contact me on (301) 492-1387.
4 Yours truly,
'/s/
Thomas W. Alexion, Project Manager Project Directorate III-3 Division of Reactor Projects - III, IV, V and.Special Projects Office of Nuclear Reactor Regulaticn Knciosures: 1 As stated -l W10tiSLY'CONCURRE&' gi gi p Office:
- LA/PDIII-3 PM/PD nPD/PD a
, Surname: PKr#uder TAlexion/tg O I l
Date: g/g/89 40/ p9/rG f[MHannon
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L ;DR ADOCK 05000483 PDC
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, 'Mr. D. F. Schnell '
Callaway Plant f Union Electric Company Unit No. 1-
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cc: ,
Dr. J. O. Camack Mr. Bart D. Withers )
CFA Inc. . President and Chief i 4 Professional Dr., Suite 110 Executive Officer l Gaithersburg, MD 20879 Wolf Creek Nuclear Operating Corporation Gerald Charnoff, Esq. P. O. Box 411
, Thomas A. Baxter, Esq. Burlington, Kansas 66839 "
,., Shaw, Pittman, Potts and Trowbridge
" 2300 N Street, NW Mr. Dan I. Bolef, President a Washington, DC 20037 Kay Drey, Representative l Board of Directors Coalition q Mr. T. P. Starkey for the Environment i Supervising Engineer, St. Louis Region j Site Licensing. 6267 Delmar Boulevard j Unica Electric Compaqy University City, Missouri 63130 .]
Post Office Box 620 ;
Fulton, Missouri 65251
'U. S. Nuclear Regulatory Commission {
' Resident Inspectors Office l RR#1 Steedman, Missouri 65077' Mr. Alan C. Passwater, Manager Licensing and Fuels j
' Union Electric Company '
Post Office Box 149 )
St. Louis, Missouri 63166 Manager - Electric Department I Missouri Public Service Commission !
301 W, High 'I Post-Office Box 360 J Jefferson City, Missouri 65102 1 I
Regional Administrator !
U. S. NRC Regian III 799 Roosevelt Road J>
Glen Ellyn, Illinois 60137 i
Mr. Ronald A. Kucera, Deputy Director l Department of Natural Resources J P. O. Box 176 Jefferson City, Missouri 65102 f l l i1
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4 ENCLOSURE 1
'COMMENTSONULNRC'-18b9,CALLAWAYPLANTRESPONSETONRC'S ;
LREQUEST FOR ADDITICNAL DATA
- 1. Your a~ n swer to General Question number 4. refers specifically to ' tests.
Do you also take no~ exceptions to those parts of the Standard. ,
which refer to the extent and degree of simulation required?:
- 2. Regarding the " Annual Reportt Enclosure B to Form 474, Page 4, .
j Section 2.10," you state that " Baseline data from the plant is only avail- ,
able for the reactor trip transient." For clarification, baseline dita may cone from actual plant data, engineering code .best estimato, or the judgement of a panel of' experts. For the remainder of the tests you have chosen to use'a panel of experts.; however, your documentation of. their-review is. insufficient for o third party to evaluate the adequacy of the.
test (s)andresults. Please. provide such' documentation which may include such itens as.the makeup and qualifications of the panel and any differing ;
professional opinions as to the outcome of the test (s). ,
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- 3. Regarding the " Checklist
Attachment:
Att'achment 1 to Enclosure B to Form 9 474, Page 6,' Item 1.13," your response remains unclear. Section 3 of'the i Standard requires that "The extent of simulation shall be such that the.
operator is required to'take the same action on the simulator to conduct .
an evolution as on the reference plant using similar procedures." The i required cperator actions are defined by the. reference plant's procedures. ]
Those procedures may include normal integrated plant operations, annunci- {
cator response, systems operations, abnormal operations, emer0ency opera-tions, and emergency plan procedures. All of these procedures are referred to in 10 CFR 55.45.. The Standard has further delineated'the minimum 3 evolutions that a simulator shall be capable of performing in Section 3.1.
A full scope simulator includes the hardware and software necessary to per-form those procedures which, when performed, are.normally conducted by operators. Therefore any hardware or software deficiency which ' precludes
, the operator from conducting ar. evolution in accordance with reference plant procedures should be noted as an exception to the Standard. Please confirm that you are taking no such exceptions or provide justifications for such.
4.a. Siegarding the " Steady State Tests: Attachment 3 to Enclosure B to Form 474," from your response it remains unclear why you do not initialize the simulator to the cycle tinae for which you have reference plant data.
- Please provide additionel clarification.
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4.b. Your method for calculating differences by normalizing scales appears to be inconsistent with respect to conservatism and not in accordance with the Standard. TheStandardrequires,inSections4.1(3)and4.1(4),that parameters agree within given tolerances of the plant parameters, not the scales on which those parameters are indicated. For example, if a non-critical parameter normally reads 32 on a scale of 0-100 then the allow- l able deviation is i 3.2, not i 10. Your use of the method you describe should i be noted as an exception to the Standard and justification should be 1 provided. 1
- 5. Section 3.1.2(1)(c) of the Standard requires malfunctions for "large and small reactor coolant breaks including demonstrations of saturation condi-tion." In Attachment E of your response only one malfunction was found to be pplicable to this requirement: Record #312, Test T0312, Malfunction RCS6. However, RCS6, as described in Attachment F, has a maximum break 4 size of 5 inches or 3000 GPM and does not address the " demonstration of I saturation condition." Please confirm that the Callaway simulator meets i this requirement or provide justification for exception to the Standard.
E. Attachment E to your response references tests T0238, T0242, T0243, l T0253, T0689 through T0709, and T0837'none of which are included in Attachment F. Please provide these missing " SIFT" sheets and malfunction descriptions.
- 7. Section 3.1.2(4) requires malfunctions for " Loss of forced core coolant flow due to single or multiple pump failure." It is not clear that the malfunctions referenced to this requirement, RCS-3 and RCS-4, are capable of multiple pump failures. Please confirm this capability exists or pro-vide justification for exception to the Standard.
E. Attachment G to your response does not indicate that you intend to perform <
approximately 25 percent of the performance tests per year as required by 10 CFR 55.45(b)(5)(vi). Please provide a more detailed schedule from which the percentage of performance tests scheduled per year can be determined, i
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ENCLOSURE 2 ADDITI.0HAL C0i4MENTS ON ORIGINAL SUBMITTAL The fo110 wing 3 comments are in regard to Enclosure "A" to ULNRC 1686.
- This is Nuclear Function Administrative Procedure APA-ZZ-00645 Simulator Configuration Management. ;
- 1. Section 3.1.1 (10) of the Standard requires the simulator to be capable of performing operator conducted surveillance testing on safety-related equipment or systems. In paragraph 4.1.1.10 of your procedure you use the phrase " Applicable operator conducted surveillance testing." Please define your use of the term " Applicable." Any " operator conducted surveillance testing on safety-related equipment or systems" which you consider to be not applicable should be.noted as an exception to the i Standard and justification should be provided.
- 2. Section 4.1 (4) of the Standard requires noncritical parameters to be within .10% of the plant parameters and also that tMy not detract ftom training. In paragraph 5.2.4_of your procedure you have substituted the word "or" for the word "and." This implies that an error greater than ;
10%.is acceptable if such error does not detract from training, and conversely, that if an error detracts from tra$ning it is acceptable if.
such error is.less than 10%. All errors which either exceed i 10% or ,
detract'from. training should be corrected or noted as exceptions to the Standard. Please confirm you are taking no such exceptions or provide justification for these exceptions.
- 3. Section 5.4.1 of the Standard requires performance tests to meet the criteria of Section 4. Section 4 of the Standard includes criteria for Simulator Operating Limits. You have not indicated that you have performed tests. verifying that your simulator meets these criteria. The lack of such tests should be taken as an exception to .the Standard.
Please confirm that such tests have been performed or provide justification for exception.
The 2 following comments are in regard to Enclosure "B" to VLNRC 1686.
l This is the Callaway Plant Simulator Annual Report.
I. Section 4.1 of the Standard requires critical parameters to agree within i 2% of the plant parameters and noncritical parameters to agree within i 10%. In paragraph 2.8 of your report you state that differences greater than 10% were evaluated for impact on operator training. For noncritical 4 parameters any difference greater than 10% should be taken as an exception to 4.1(4) of the Standard. For critical parameters any difference ,
greater than 2% should be taken as an exception' to 4.1(3) of the i Standard. Please confirm you are taking no such exceptions or provide i justification for such. ,
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, 2. In paragraph 2.10 of your report you state "Other simulators providing i transient graphs can also be used to verify and validate the transients j graphed on the Callaway Plant Simulator." This statement requires '
explanation. The intent of benchmark transient tests is to compare rimulator performance to reference plant performance. Comparison to other j simulators would appear to be invalid unless they are referenced to your j plant. l l
The following 2 comments apply to the " Attachment to APA-ZZ-00645, Checklist 1."
- 1. Section 3.2.1 of the Standard requires that the simulator contain ;
sufficient operational panels to provide the controls, instrumentation, )
elarms, and other man-machine interfaces to conduct the normal plant i evolutions of 3.1.1 and respond to the malfunctions of 3.1.2. In l checklist item 12, your floo* plan, comparison, you state that "All main j centrol board panels are simulated." Please clarify what you mean by ;
" main control board panelt." Floor plan sketches of both the control j room and the simulator would be helpful. Any differences which preclude ;
operations required by 3.1.1 or 3.1.2 of the Standard should be noted as exceptions to the Standard and justification should be provided. j
- 2. For steady state operation the Standard requires, in Sections 4.1(3) !
and 4.1(4) respectively, that critical pcrameters agree within 2% and )
noncritical parameters within Ibi of the plant pcraineters and neither shall detract from training. In item 3.1, " Technical Specification Lngs,"
you state that any difference groater than 10% was evaluated for potential impact on training. The " potential impact on training" should be applied as an additional more strict criteria than the 2% and 10%
criteria for critical and noncritical parameters. Any other use of the
" impact on training" criteria should be noted as an exception to the S tar,da rd. please confirm you are taking no such exceptions or provide justification for such.
The following comment applie to "Callaway Plant Simulator Annual Report 1987 Attachment 4 Transients (Test 1 thrcugh 10).
- 1. Appendix B of the Standard, in Section B.2.2, requires that these j trarsients be run "from an iaitial condition of approximately 100% power, 1 steady state xenon and decay heat with no operator followup action l (unless otherwise noted)." Please specify the details of the initial conditions used for each of these telts. Include power level, power history, fission product concentrations, mode, and any other data significant to the given initial condition. l l
Acceptance criteria for these tests is provided in Section 4.2 of the standard. Please provide abstracts of these tests which include:
- a. Final conditions.
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- b. A ' description of the baseline data used to determine fidelity to the reference plant. If this was the judgement of a panel of experts-then inc'lude sufficient documentation of their review for a third' party to evaluate the adequacy of the test (s) and results. .This documentation may-include such items as the makeup and qualifications l of the panel and any differing professional opinions as to the ;
outcomeofthetest(s). l
- c. Deficienciesfoundasaresultofthetest(s)andcorrectiveaction-l.
planned including the schedule.
- d. Exceptions taken to the Standard as a result of the test (s), with justification.
The following 3 comments are in regard to "Callaway Plant Simulator .
1 Annual Report 1987, Attachment 5, Callaway Plant' Simulator Benchmark Graphs."
la Thetimescaleforthesimulatorpowerrangegraph(inAttachment4) l differs from that of the RETRA.N estimate by a factor of ten. Please !
explain, ,
- 2. The pressurizer pressure graph (in Attachment 4) for the simulator shows-an initial jump which is not indicated in the graph in Attachment 5.
Please' explain.
- 3. The steam generator pressure graph for the simulator (in Attachment 4) shows a valley after the initial peak which is not indicated 17 the graph in Attachment 5. Please explain.
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