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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA ML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F0901999-09-21021 September 1999 Confirms Discussion Between M Hammer & Rd Lanksbury to Have Routine Mgt Meeting on 991005 in Lisle,Il.Purpose of Meeting to Discuss Improvement Initiatives in Areas of Operations & Equipment Reliability ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20211Q6981999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Monticello Operator License Applicants During Wks of 010604 & 11.Validation of Exam Will Occur at Station During Wk of 010514 ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam ML20210H0861999-07-28028 July 1999 Forwards Insp Rept 50-263/99-04 on 990521-0701.No Violations Noted.Licensee Conduct at Monticello Facility Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209G5621999-07-14014 July 1999 Forwards Insp Rept 50-263/99-11 on 990621-24.No Violations Noted.Objective of Insp,To Determine Whether Monticello Nuclear Generating Station Emergency Plan Adequate & If Station Personnel Properly Implemented Emergency Plan ML20196J5351999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950515 & NSP Responses & 980917 for Monticello Npp.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206N5601999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Monticello Npp.Organization Chart Encl ML20206G2181999-05-0505 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Dtd 960110,for Plant ML20206G4901999-05-0404 May 1999 Forwards Staff Review of Licensee 960508 Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Sf,Over Fuel in Rc or Over Safety-Related Equipment, .Overall, Responses Acceptable.Tac M95610 Closed ML20206G7741999-05-0303 May 1999 Forwards Insp Rept 50-263/99-02 on 990223-0408.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20205N0821999-04-12012 April 1999 Forwards SE of NSP Response to NRC GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Licensee Adequately Addressed Actions Requested in GL ML20205N4811999-04-0909 April 1999 Forwards Licensing Requalification Insp Rept 50-263/99-10 on 990308-12.No Violations Noted.However,Inspectors Through Observation of Simulator Scenario Exams Noted Difficulties in Ability of SM to Simultaneously Implement Duties of SM ML20205N5301999-04-0909 April 1999 Discusses Arrangements Made on 990406 for Administration of Licensing Exams at Monticello Nuclear Generating Station During Wk of 990823.Requests That Exam Outlines Be Submitted by 990128 & Supporting Ref Matls by 990719 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C4851999-03-26026 March 1999 Informs That on 990203,NRC Staff Completed PPR of Nuclear Plant.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20205A5881999-03-24024 March 1999 Forwards Request for Addl Info Re Submittal Requesting Rev of pressure-temperature Limits & Surveillance Capsule Withdrawal Schedule ML20204H4711999-03-18018 March 1999 Forwards SER Concluding That Util Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello & Adequately Addressed Actions Requested in GL 96-05 ML20207H5161999-03-11011 March 1999 Forwards Insp Rept 50-263/99-01 on 990112-0222.No Violations Noted ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20217A1741990-11-0909 November 1990 Advises That Requalification Program & Licensed Personnel Evaluation Scheduled for Wk of 910318 ML20058G2371990-10-16016 October 1990 Forwards Results & Conclusions of Regulatory Effectiveness Review Re Safeguards Measures Conducted on 900910-14.Encl Withheld (Ref 10CFR73.21).Elements of Security Program Sound & Well Managed ML20059C2561990-08-21021 August 1990 Confirms Plans for 900911 Meeting to Present Initial SALP 9 Rept for Facility.Region III Encourages Appropriate Corporate & Plant Mgt Representation at Meeting to Ensure Mutual Understanding of Issues & Findings Presented by NRC 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 ML20055H9971990-07-26026 July 1990 Ack Receipt of 900430 & 0713 Ltrs Re Allegation on Breaker Failure on Cooling Tower Sys.Investigation Found Sufficient Indicating That Load Ctr 106 Located Outside Security Fence Was nonsafety-related ML20055G6671990-07-20020 July 1990 Confirms 900809 Mgt Meeting in Glen Ellyn,Il to Discuss Corporate Reorganization & Other Matters of General Interest ML20055G4291990-07-18018 July 1990 Forwards Safeguards Insp Rept 50-263/90-13 on 900604-0711.No Violations Noted ML20055D9961990-06-29029 June 1990 Advises That 900605 Rev 30 to Security Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable W/Exception of Items Noted in Encl.Correction to Plan Addressing Issues Requested.Encl Withheld (Ref 10CFR73.21) ML20059M9431990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248B6241989-06-0202 June 1989 Forwards Enforcement Conference Insp Rept 50-263/89-13 on 890427.No Enforcement Action Taken Based on New Testing, Analyses,Field Insp & Clarifications Provided by Licensee ML20247N8291989-05-26026 May 1989 Forwards Enforcement Conference Rept 50-263/89-14 on 890512 & Notice of Violation.Concludes That RCIC Steam Line Flooding Issue Resulted in Severity Level IV Violation for Failure to Have Adequate Test Controls ML20247A0611989-05-0404 May 1989 Forwards SER Accepting Util Response to Generic Ltr 83-28, Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Technical Evaluation Rept Also Encl ML20246C2631989-05-0101 May 1989 Confirms 890602 Meeting in Monticello,Mn to Present SALP 8 Rept for Plant ML20244D2511989-04-13013 April 1989 Confirms 890427 Enforcement Conference at Region III Ofc to Discuss Apparent Violation Re Inadequate Corrective Action for Previous Equipment Qualification Violation.Provide Handout at Conference Describing Position on Encl Topics ML20244C7231989-04-11011 April 1989 Forwards Safeguards Insp Rept 50-263/89-08 on 890227-0303 & Notice of Violation.Rept Details & Notice of Violation Withheld (Ref 10CFR73.21) ML20235V7411989-02-27027 February 1989 Advises That 890106 Rev 26 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20196F0931988-12-0707 December 1988 Requests Listed Refs Matl Be Submitted 60 Days Prior to Written & Oral Exams Scheduled for Wk of 890320 ML20206K1971988-11-14014 November 1988 Forwards Emergency Operating Procedure Insp Rept 50-263/88-200 on 880711-22.Deficiencies Noted.Executive Summary of Insp W/Overview of Insp Team Findings in Areas Reviewed Encl ML20206E4611988-11-10010 November 1988 Forwards Reactive Safeguards Insp Rept 50-263/88-18 on 880919-22 & Notice of Violation.Program to Improve Security Performance Presented at 880615 Enforcement Conference Has Not Achieved Intended Goals ML20155J0071988-10-19019 October 1988 Advises of NRC 890206 Visit to Evaluate Util Requalification Program,Per Telcon Between B Mcgillic & D Hills.Nrc Examiner to Administer NRC Prepared Written & Operating Exams. Ref Matl Requirements Encl ML20155F5651988-10-0707 October 1988 Forwards Grading & Answer Sheets for 880921 Generic Fundamentals Pilot Exam.W/O Encls ML20154R8541988-09-23023 September 1988 Forwards Environ Assessment & Finding of No Significant Impact Re Exemption from Requirements of App J to 10CFR50 for Primary Reactor Containment Leakage Testing ML20154C6521988-08-31031 August 1988 Advises That 880812 Rev 25 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20154C6671988-08-31031 August 1988 Advises That 880812 Rev 3 to Safeguards Contingency Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Encls Withheld IR 05000263/19880081988-07-29029 July 1988 Discusses Safeguards Insp Rept 50-263/88-08 & Forwards Notice of Violation.Flaws in Vital Area Physical Barriers Which May Allow Unauthorized Access Must Be Corrected.Notice of Violation Withheld (Ref 10CFR73.21) ML20207F8881988-07-27027 July 1988 Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure ML20151J6731988-07-21021 July 1988 Forwards Exam & Answer Key (Senior Reactor Operator) for Exam Rept 50-263/OL-88-02 Inadvertently Omitted During Distribution of Rept.W/O Encl ML20150B7151988-06-23023 June 1988 Forwards Revised Draft Rev 5 to ES-601, Administration of NRC Requalification Program Evaluations. W/O Encl ML20154Q3971988-05-31031 May 1988 Confirms 880615 Meeting in Glen Ellyn,Il to Discuss Security Problems & Corrective Actions at Plant ML20154L6721988-05-19019 May 1988 Advises That Rev 8 to Security Force Training & Qualification Plan,Transmitted by Consistent W/ Provisions of 10CFR50.54(p) & Acceptable ML20148G4791988-03-24024 March 1988 Forwards Exam Rept 50-263/OL-88-01 on 880302-03 ML20149J3541988-02-18018 February 1988 Requests That Encl List of Ref Matl Be Furnished at Least 60 Days Prior to Operator & Senior Operator Licensing Exams Scheduled for Wk of 880606.Requirements for Administration & Review of Written Exams & Rules & Guidelines Also Encl ML20149G5291988-02-12012 February 1988 Advises Util of Region III Intent,If Requested,To Arrange Time & Place to Formally Present License Certificates to Newly Licensed Individuals,In Recognition of Accomplishment of Individuals Having Gone Through Study & Training ML20149G4061988-02-12012 February 1988 Forwards Pilot Requalification Exam Given at Hb Robinson for Help in Generating Questions for Anticipated Testing Later This Yr.Util Encouraged to Begin Review of Programs & Manpower Commitments to Accomodate Effort.W/O Encls ML20149E7641988-01-0606 January 1988 Confirms Arrangements for Written & Oral Exams Scheduled for Wk of 880229,per Telcon.Requirements for Conducting Exams, Rules & Guidance to Be in Effect During Exams & Requirements for Facility Review of Written Exam Encl ML20236Y3971987-12-0707 December 1987 Ack Receipt of Util Forwarding Rev 10 to Corporate Emergency Plan.Revs Consistent W/Requirements of 10CFR50.54(q) & Do Not Decrease Effectiveness of Emergency Plan ML20235V0741987-10-0808 October 1987 Forwards Exam Rept 50-263/OL-87-02 of Exam Administered During Wk of 870901-03 ML20235F4221987-09-22022 September 1987 Forwards NRR Position Re Entry Into Limiting Condition for Operation Based on Inservice Testing Surveillance Results within Required Action Range.Review of Practices for Performing Inservice Testing Surveillances Recommended ML20235A6991987-09-18018 September 1987 Forwards Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys.Request Commitment & Schedule for Upgrading ARI & RPT within 60 Days ML20236P4361987-08-0707 August 1987 Ack Receipt of 861124 Proposed Amend to Physical Security Plan,Per Miscellaneous Amends & Search Requirements.Response to Encl Comments & Revs to Plan Required Prior to Approval of Amend.Response Requested within 30 Days of Ltr Receipt ML20236P4471987-08-0707 August 1987 Ack Receipt of Util Transmitting Proposed Amend to Physical Security Plan.Addl Info & Revs to Plan Required Prior to NRC Approval.Response to Encl Comments Requested within 30 Days of Ltr Receipt ML20215A3311987-06-10010 June 1987 Forwards Mgt Meeting Repts 50-263/87-08,50-282/87-10 & 50-306/87-10 on 870526 ML20215B1491987-06-0909 June 1987 Notifies That Evaluation of Requalification Program Scheduled for Wks of 870831,0907 & 14.NRC Will Administer Written,Oral & Simulator Exams.Encl Ref Matl Requested to Assist Examiner in Preparing for Visit ML20214U9841987-06-0303 June 1987 Forwards Revised NRC Form 398,personal Qualifications statement-licensee & NRC Form 396,certification of Medical Exam by Facility Licensee.Forms Revised to Reflect Changes to 10CFR55 Effective on 870526.W/o Encls ML20214K1601987-05-22022 May 1987 Advises of Operator & Senior Operators Written & Oral Exams Scheduled for Wk of 870831,per Telcon W/Jm Keeton & R Mcgillic.Ref Matl Listed in Encl 1 Requested 60 Days Prior to Exam Date.Encl 2 Describes Exam Requirements ML20209B4581987-04-23023 April 1987 Forwards Exam Rept 50-263/OL-87-01 Administered on 870309-12 ML20207R6171987-03-12012 March 1987 Forwards Insp Rept 50-263/87-03 on 870123-0213 & Notice of Violation.Response to Violation Should Include Plans to Review & Upgrade Controls for Rendering Control Rod Inoperable on 870122 IR 05000263/19860081987-03-12012 March 1987 Informs of Changes on Page 11,Item 4 Re Automatic Fire Detection in Insp Rept 50-263/86-08.Listed Phrase Should Be Removed ML20211J3791987-02-17017 February 1987 Forwards Safety Insp Rept 50-263/87-02 on 861104-870204.No Violations Noted ML20207Q6561987-01-16016 January 1987 Extends Invitation to Participate in 870129 Workshop in Chicago,Il on Incident Investigation Program.W/O Stated Encls 1990-08-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F0901999-09-21021 September 1999 Confirms Discussion Between M Hammer & Rd Lanksbury to Have Routine Mgt Meeting on 991005 in Lisle,Il.Purpose of Meeting to Discuss Improvement Initiatives in Areas of Operations & Equipment Reliability ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20211Q6981999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Monticello Operator License Applicants During Wks of 010604 & 11.Validation of Exam Will Occur at Station During Wk of 010514 ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam ML20210H0861999-07-28028 July 1999 Forwards Insp Rept 50-263/99-04 on 990521-0701.No Violations Noted.Licensee Conduct at Monticello Facility Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML20209G5621999-07-14014 July 1999 Forwards Insp Rept 50-263/99-11 on 990621-24.No Violations Noted.Objective of Insp,To Determine Whether Monticello Nuclear Generating Station Emergency Plan Adequate & If Station Personnel Properly Implemented Emergency Plan ML20196J5351999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950515 & NSP Responses & 980917 for Monticello Npp.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20206N5601999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Monticello Npp.Organization Chart Encl ML20206G2181999-05-0505 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Dtd 960110,for Plant ML20206G4901999-05-0404 May 1999 Forwards Staff Review of Licensee 960508 Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Sf,Over Fuel in Rc or Over Safety-Related Equipment, .Overall, Responses Acceptable.Tac M95610 Closed ML20206G7741999-05-0303 May 1999 Forwards Insp Rept 50-263/99-02 on 990223-0408.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20205N0821999-04-12012 April 1999 Forwards SE of NSP Response to NRC GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Licensee Adequately Addressed Actions Requested in GL ML20205N4811999-04-0909 April 1999 Forwards Licensing Requalification Insp Rept 50-263/99-10 on 990308-12.No Violations Noted.However,Inspectors Through Observation of Simulator Scenario Exams Noted Difficulties in Ability of SM to Simultaneously Implement Duties of SM ML20205N5301999-04-0909 April 1999 Discusses Arrangements Made on 990406 for Administration of Licensing Exams at Monticello Nuclear Generating Station During Wk of 990823.Requests That Exam Outlines Be Submitted by 990128 & Supporting Ref Matls by 990719 ML20205C4851999-03-26026 March 1999 Informs That on 990203,NRC Staff Completed PPR of Nuclear Plant.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205A5881999-03-24024 March 1999 Forwards Request for Addl Info Re Submittal Requesting Rev of pressure-temperature Limits & Surveillance Capsule Withdrawal Schedule ML20204H4711999-03-18018 March 1999 Forwards SER Concluding That Util Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello & Adequately Addressed Actions Requested in GL 96-05 ML20207H5161999-03-11011 March 1999 Forwards Insp Rept 50-263/99-01 on 990112-0222.No Violations Noted ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20202B7191999-01-26026 January 1999 Discusses 990125 Telcon with T Witschen & D Mcneil Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Monticello Nuclear Generating Station.Insp Planned for Week of 990308 ML20199H8321999-01-20020 January 1999 Forwards Insp Rept 50-263/98-18 on 981201-990111.No Violations Were Identified.Conduct of Activities at Monticello Facility Was Generally Characterized by safety- Conscious Operations & Sound Maint Practices ML20199G7721999-01-14014 January 1999 Forwards Request for Addl Info Re GL 88-20, Individual Plant Exam of External Events (IPEEE) for Severe Accident Vulnerabilities, Issued in June 1991 ML20206R8631999-01-12012 January 1999 Informs That Staff Has Prepared TS Interpretation of Requirements for Extending Surveillance Intervals at Plant,Per NRC Request ML20199E4791999-01-0606 January 1999 Forwards SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Monticello ML20206R8741999-01-0404 January 1999 Discusses Clarification of Understanding of Safety Evaluation Related to Deviation from Emergency Procedure Guidelines for Monticello.Staff Agrees with NSP Characterization & Resolution of Issues ML20198R2001998-12-30030 December 1998 Forwards Insp Rept 50-263/98-19 on 981214-18.No Violations Noted.Purpose of Insp Was to Review Plant Chemistry Program, PASS & REMP ML20198P0501998-12-28028 December 1998 Informs of Completion of Review of Relief Request 9 Re Third 10-year Interval ISI Program Plan,Entitled Use of High Alloy/High Nickel Calibr Block for Dissimilar Metal Welds. Supporting SE Encl ML20198G0761998-12-21021 December 1998 Acks Receipt of Notifying NRC That Commitment Noted in Is Complete Re Tornado Effects on Reactor Bldg Superstructure ML20198D0181998-12-15015 December 1998 Informs That as Part of PRA Implementation Plan,Commission Assigned Two SRAs to Each Regional Ofc.Sras Will Routinely Assess Licensee Event Repts,Plant Events,Insp Findings & EAs from Risk Perspective ML20198B7721998-12-14014 December 1998 Forwards Insp Rept 50-263/98-16 on 981014-1130 & Notice of Violation Re Fire Brigade Drill Participation ML20198D0641998-12-10010 December 1998 Forwards SE Accepting Licensee 971118 Request for Review & Approval of Deviation from BWROG Epg,Rev 4,NEDO-31331, March,1997.Deviation Will Permit Rev of Plant EOPs to Recognize 2/3 Core Height as Adequate for Core Cooling ML20196C2411998-11-24024 November 1998 Forwards Insp Rept 50-263/98-17 on 981026-30.No Violations Noted.Security Dept self-assessment Efforts Continue to Be Very Strong ML20196D5641998-11-20020 November 1998 Discusses 981104 Insp Resource Planning Meeting for Monticello & Advises of Planned Insp Effort for Next 6 Months at Plant.Info Provided to Min Resource Impacts on Staff & to Allow for Rescheduling Conflicts to Be Resolved ML20195J8811998-11-19019 November 1998 Informs That EOP Flow Charts C.5-1100 RPV Control, Rev 5 & C.5-1100... Rev 6 Marked Proprietary & Submitted as Attachments 3 & 4 to Util Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20196G6081998-11-19019 November 1998 Submits Correction to Which Advises Licensee That EOP Flow Charts, C.5-1100 RPV Control, Rev 5 & C.5-1100 RPV Control, Rev 6,marked Proprietary,Will Be Withheld from Public Disclosure.Ltr Reissued to Correct Date of Issuance ML20195E3321998-11-12012 November 1998 Forwards SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Facility Has Adequately Addressed Purpose of 10CFR50.54(f) Request.Usi A-46 Program Was Established in Response to GL 87-02 ML20196D7291998-11-10010 November 1998 Forwards Insp Rept 50-263/98-15 on 980831-1014.No Violations Noted.Investigation Team Assembled by Station Mgt to Determine Root Cause of Offgas Sys Problem Was Thorough & Aggressive ML20154L2951998-10-0909 October 1998 Informs That Effective 981011,project Mgt Responsibility for Plant Will Be Transferred from Tj Kim to CF Lyon.Cf Lyon May Be Contacted at Listed Number ML20154F4971998-10-0606 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-263/98-09 Issued on 980730 ML20154J2501998-10-0202 October 1998 Forwards Audit of Year 2000 Program at Monticello Nuclear Generating Plant on 980915-17 as Followup to NRC GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants, Issued on 980511 ML20153C4611998-09-21021 September 1998 Submits Comments on Draft Environ Impact Statement for Minnesota Lake Superior Coastal Program 1999-09-09
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r-MAY 2 2 tan Docket No. 50-263 Northern States Power Company ATTN: Mr. C. E. Larson Vice President, Nuclear Generation-International Centre Building 920 Second Avenue South Minneapolis, MN 55401
Dear Mr. Larson:
SUBJECT:
OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. J. M. Keeton and Mr. R. McGillic, '
arrangements were made for the administration of examinations at the Monticello Nuclear Generating Station.
The written and oral examinations are scheduled for the week of August 31, 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 will 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, will likely result in'a lon delay missing the deadline, even by a few dayssinceitmaynotbepossibletorescheduleexa Mr. R. McGillic has been advised of 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 adeguate space and' facilities in order to properly conduct the written examinations.
Enclosure 2, " Administration of Reactor / Senior Reactor.0perator Licensing Written Examinations " describes our requirements for conducting these examinations. Mr. McGillic has also been informed of these requirements.
In addition,.to better document simulator examinations, the chief examiner will have the facility simulator operator record prespecified plant pressurizer level, etc.)
conditions (i.e., plant for each simulator pressure, scenario. temperature,ll The candidate wi be responsible for providing this informath n, along with any appeal of his simulator operating examination.
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J MAY 2 21987 Northern States Power Company 2 Therefore, the facility training staff should 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.
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.
1 Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Mr. Keeton at (312) 790-5545.
Sincerely, i
(.
ORIGINAL SIGNED BY CHARLES HEHL Charles W. Hehl, Chief Operations Branch
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor J
Operator Licensing Examinations
- 2. Administration of Operator Licensing Written Examinations ,
- 3. NRC Rules and Guidelines For ;
License Examinations See Attached Distribution RI
^ RIII II RU)
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MAY 2 219n
- .- Northern States Power Company .3 Distribution
,cc w/ enclosures:
W.' A. Shamla,)
DCS/RSB (RIDS Plant Manager Licensing Fee-Management Branch Resident Inspector, RIII Monticello Resident Inspector, RIII Prairie
. Island John W. Ferman, Ph.D.,
Nuclear Engineer, MPCA -
E. Earney, Plant-Training Manager cc w/o enclosures:
D. Scaletti,. Project Manager, NRR J. Hannon, Branch Chief, OLB R. W. Cooper, NRR.
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1
. ENCLOSURE 1 Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 1. Existinglearning,objectivesandlessonplans(includin manuals, plant orientation manual, system descriptions,g reactortraining theory, thermodynamics,etc.).
Training materials should include all substantive written material used for preparing candidates for initial R0 and SR0 licensing. The written materialshouldincludelearning,objectivesandthedetailspresented during lecture, rather than outlines. Training materials should be identified by plant and unit, bound, indexed, and tabbed. 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.
Systemtrainingmaterialshoulddrawparallelstotheactual procedures used for operating the applicable system.
- Complete and operationally useful descriptions of all safety-system interactions and, where available, B0P system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
- Training material used to clarify and strengthen understanding of emergency operating procedures.
- 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 descriptions of how these principles actuallyapply(tomajorplantpumpsandthesystemsinwhichthey are installed i.e., Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps,ial should include descriptions that drawFeedwate Reactor Theory mater explicit ties between the fundamentals and the actual operating limits followed in the plant (i.e., reactor theory material should explain how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
- 2. ProcedureIndex(alphabeticalbysubject).
- 3. All administrative procedures (as applicable to reactor operation or safety).
- 4. All integrated plant procedures (normal or general operating procedures).
. ' Enclosure 1- 2
- 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,whenappropriate).
- 8. Annunciatorprocedures(alarmprocedures,includingsetpoints).
- 9. Radiationprotectionmanual(radiationcontrolmanualorprocedures).
- 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 and facility Data precautBook, ions, limitations, and set points (PLS) for theand/or p facility.
- 15. Qcestions and answers that licensee has prepared (if available).
- 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
)rovided. Additionally, an indication of which annunciators are to
)e initially expected should be given.
- c. A description of simulator failure capabilities for valves, breakers, indicators and alarms.
- d. Where the capability exists, an explanation of the ability to var the severity of a particular malfunction should be provided, .i.e.y 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 snut
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of a main feedwater control valve).
.. ' Enclosure 1 3
- 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 / level control, degraded heat removal capability, and containment challenges may be provided.
- h. Simulator instructor's manual (voluntary by licensee).
- i. Description of the scenarios used for the training class (voluntary bylicensee).
- 17. Additional material required by the examiners to develop examinations that meet the requirements of these standards and the regulations.
The above reference material should be approved, final issues and should be so 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 tabbed and bound with appropriate indexes or tables of contents so that they can be used efficiently.
ENCLOSURE 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 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, nor 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 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 com)leting the examination. The examiner will distribute these pads to tie 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.
/
i
. 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 automtic 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 ci 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. Fillinthedateonthecoversheetoftheexamination(ifnecessary).
- 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,ANSWERALLPARTSOFTHEQUESTION AND DO NOT LEAVE ANY ANSWERS BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the 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. Assemble 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 in progress, your license may be denied or revoked.