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| {{#Wiki_filter:L>Jl'<~I~hm FileCyr'egulatory NIAGARAMOHAWKPOWERCORPORATION 6lI](gPf'prQ.@8~<gleda~Q~QErgo<<NIAGARA~MOHAWK300ERIEBOULEVARD WESTSYRACUSC, N.Y.13202 I~~Mqc>(~CiApril15,1970Dr.PeterA.Morris,DirectorDivisionofReactorLicensing UnitedStatesAtomicEnergyCommission Washington, D.C.20545 | | {{#Wiki_filter:L>Jl'<~I~hm File Cyr'egulatory NIAGARA MOHAWK POWER CORPORATION 6lI](gP f'p r Q.@8~<gled a~Q~QE r go<<NIAGARA~MOHAWK 300 ERIE BOULEVARD WEST SYRACUSC, N.Y.13202 I~~M qc>(~Ci April 15, 1970 Dr.Peter A.Morris, Director Division of Reactor Licensing United States Atomic Energy Commission Washington, D.C.20545 |
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| ==DearDr.Morris:== | | ==Dear Dr.Morris:== |
| IIjt'lIIIInreference toyourletterofFebruary12,1970,concerning retraining of.licensedoperators, Ihavediscussed belowourprogramandthemannerinwhichweintendtodischarge it.Inasmuchasoursenioroperators havebeenlicensedfor9monthsandthereactoroperators only3months,aswellasthefactthatwehaveoperatedforonly30fullpowerdays,theretraining programis,forthemostpart,whatwewillcarryoutintheyearahead.Ihav'eoutlinedourretraining programbyanswering thequestions posedinyourletter,inanefforttoensurethatalltheinformation thatwasrequested issubmitted.
| | I I j t'l I I I In reference to your letter of February 12, 1970, concerning retraining of.licensed operators, I have discussed below our program and the manner in which we intend to discharge it.Inasmuch as our senior operators have been licensed for 9 months and the reactor operators only 3 months, as well as the fact that we have operated for only 30 full power days, the retraining program is, for the most part, what we will carry out in the year ahead.I hav'e outlined our retraining program by answering the questions posed in your letter, in an effort to ensure that all the information that was requested is submitted. |
| l.Aformalretraining programconsisting ofscheduled lectureshasbeensetup.Asplanned,thecourseofinstruction willbeapproximately 50hoursindurationcoveringthefollowing subjects: | | l.A formal retraining program consisting of scheduled lectures has been set up.As planned, the course of instruction will be approximately 50 hours in duration covering the following subjects: a.Principles of Reactor Operation b.Features of Facility Design c.General Operating Characteristics d.Instruments and Controls e.Safety and Emergency Systems Standard and Emergency'Operating Procedures g.Radiation Control and Safety sizes will be utilized to check on individual retention as well as to uncover group weakness.2.The retraining program is administered by the Operations Supervisor or a designated assi.stant. |
| a.Principles ofReactorOperation b.FeaturesofFacilityDesignc.GeneralOperating Characteristics d.Instruments andControlse.SafetyandEmergency SystemsStandardandEmergency | | The Reactor Analyst, Radiation Protection Supv., Instrument and Control Supervisor, and other qualified members of the plant staff will conduct the retraining program in their respective fields of interest.3.Each member of the operating staff is issued a complete set of Plant Operating Procedures, Emergency Procedures, Special Procedures, and the Technical Specifications. |
| 'Operating Procedures g.Radiation ControlandSafetysizeswillbeutilizedtocheckonindividual retention aswellastouncovergroupweakness. | | When a change is.made in any of these documents, each member is notified by a group distribution notice or 4>s A~I IC" f'1 |
| 2.Theretraining programisadministered bytheOperations Supervisor oradesignated assi.stant. | | ~Og Dr.Peter A.Morris April 15, 1970 3.is issued a copy of the change.In addition, a master set is maintained with a list of changes made.The Operations Supervisor's Night Order Book contains information on plant evolutions, unusual occurrences, and major equipment malfunctions. |
| TheReactorAnalyst,Radiation Protection Supv.,Instrument andControlSupervisor, andotherqualified membersoftheplantstaffwillconducttheretraining programintheirrespective fieldsofinterest.
| | A status of equipment out of commission is maintained by the Station Red Tag Procedures. |
| 3.Eachmemberoftheoperating staffisissuedacompletesetofPlantOperating Procedures, Emergency Procedures, SpecialProcedures, andtheTechnical Specifications. | | In addition, the Station Log contains pertinent information on plant equipment, and each operator is required to read the log prior to coming on shift.4.Every effort will be made to ensure that all operators perform reactor startups and shutdowns, plant conditions permitting. |
| Whenachangeis.madeinanyofthesedocuments, eachmemberisnotifiedbyagroupdistribution noticeor 4>sA~IIC"f'1
| | Each operator has a folder for the express purpose of recording training evolutions completed other than the formal course of instructions. |
| ~OgDr.PeterA.MorrisApril15,19703.isissuedacopyofthechange.Inaddition, amastersetismaintained withalistofchangesmade.TheOperations Supervisor's NightOrderBookcontainsinformation onplantevolutions, unusualoccurrences, andmajorequipment malfunctions. | | The operators'bilities will be observed and evaluated by the Station Shift Supv.or other qualified members of the staff, as often as possible.5.Each shift crew is required to"walk through" the Emergency Procedures on a continuing basis to maintain the highest operator proficiency. |
| Astatusofequipment outofcommission ismaintained bytheStationRedTagProcedures.
| | Periodically, a simulated drill will be imposed and the shift crew per-formance evaluated. |
| Inaddition, theStationLogcontainspertinent information onplantequipment, andeachoperatorisrequiredtoreadthelogpriortocomingonshift.4.Everyeffortwillbemadetoensurethatalloperators performreactorstartupsandshutdowns, plantconditions permitting.
| | The formal classroom lecture series will also dis-cuss the Emergency Procedures as well as plant response characteristics during a major accident.6.Periodic fire and/or evacuation drills have and will be conducted. |
| Eachoperatorhasafolderfortheexpresspurposeofrecording trainingevolutions completed otherthantheformalcourseofinstructions.
| | These drills are normally unannounced so that a degree of realism can be injected and personnel response observed.The Station Superintendent is normally the evaluator during these drills.Niagara Mohawk conducts its own fire school in the local area of the Station.Everyone perma-nently assigned to the Station has received a one-week course in fire fighting.It is anticipated that each Station Shift Supervisor will receive a refresher course in fire fighting at least every two years.7.As presently structured, the retraining program is wholly within the Niagara Mohawk Power organization. |
| Theoperators'bilities willbeobservedandevaluated bytheStationShiftSupv.orotherqualified membersofthestaff,asoftenaspossible.
| | If assistance becomes necessary, it will be employed.8.The audio-visual training aids consisting of video tapes are utilized in both the classroom and as a self-study program.The entire course,"Physics for Reactor Operator," consisting of 21 fifty-minute tapes is available, as well as tapes on major systems such as Control Rod Drive, Rod Worth Minimizer, and the Neutron Monitoring System.Various sub-jects of continuing interest have been recorded here at the Station for use in the retraining program.It is anticipated that the video tape recording unit can be utilized during plant evolutions such as startup and shutdown, and Station drills.These tapes will be most valuable to the operator when the plant evolutions are static and the number of start-ups and shutdowns are limited.9.As indicated in the A.E.C.Licensing Guide, a senior operator should exhibit more detailed knowledge than that required of an operator.Also, the senior operator will be required to display a more thorough knowledge 1Tee=q,~-*e lA'e." O''f f~~I J*j~I Dr.Peter A.Morris April 15, 1970 9.of administrative controls and procedures. |
| 5.Eachshiftcrewisrequiredto"walkthrough"theEmergency Procedures onacontinuing basistomaintainthehighestoperatorproficiency. | | Thus, although the retrain-ing requirements are quite similar, the minimum acceptable performance of the senior operator is higher than that of a reactor operator.To further illustrate this point, the entire Operating Procedures and Pre-Operational Test Program were written by the Station.Shift Supervisors (Senior Operators). |
| Periodically, asimulated drillwillbeimposedandtheshiftcrewper-formanceevaluated. | | They have thus become system"experts" and have been utilized in training reactor operators and will continue to do so.'0.Operators and senior operators are evaluated using several factors, the most important being the rating by his immediate supervisor who observes'hrough daily contact his competence in discharging the duties assigned to his position.Since this evaluation is a summary of the individual's achievements over a period of many months, it should be the best possi-ble indicator of his ability and directly support or.reject his applica-tion for A.E.C.license renewal.A second factor used in appraising qualifications for license renewal is successful participation in the retraining program.The lecture series is designed to reiterate the more important aspects of the areas listed in paragraph no.l.It should keep the individual as mentally, ready as the time at which the license exams were first given.A third facet will be utilized in certifying applications for license renewal.In conjunction with paragraph no.4 (i.e.startups and shut-downs), each operator will successfully complete at least one reactor startup and shutdown in the presence of the Operations Supervisor or designated assistant. |
| Theformalclassroom lectureserieswillalsodis-cusstheEmergency Procedures aswellasplantresponsecharacteristics duringamajoraccident.
| | In addition, the Operations Supervisor will con-duct a"walk through" with each of the licensed reactor operators to ensure their readiness for licensed renewal.If there is any doubt concerning an individual's competence from the above guide-lines, a comprehensive examination of the scope of the Atomic Energy Commission exam will be given.The outcome from such an examination will indicate an indi-vidual's preparedness for relicense. |
| 6.Periodicfireand/orevacuation drillshaveandwillbeconducted. | | Very truly yours, a.s~~F.J.Schneider Vice President-Operations mjs 1 I II~~t F jN}} |
| Thesedrillsarenormallyunannounced sothatadegreeofrealismcanbeinjectedandpersonnel responseobserved.
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| TheStationSuperintendent isnormallytheevaluator duringthesedrills.NiagaraMohawkconductsitsownfireschoolinthelocalareaoftheStation.Everyoneperma-nentlyassignedtotheStationhasreceivedaone-weekcourseinfirefighting.
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| Itisanticipated thateachStationShiftSupervisor willreceivearefresher courseinfirefightingatleasteverytwoyears.7.Aspresently structured, theretraining programiswhollywithintheNiagaraMohawkPowerorganization.
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| Ifassistance becomesnecessary, itwillbeemployed.
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| 8.Theaudio-visual trainingaidsconsisting ofvideotapesareutilizedinboththeclassroom andasaself-study program.Theentirecourse,"PhysicsforReactorOperator," | |
| consisting of21fifty-minute tapesisavailable, aswellastapesonmajorsystemssuchasControlRodDrive,RodWorthMinimizer, andtheNeutronMonitoring System.Varioussub-jectsofcontinuing interesthavebeenrecordedhereattheStationforuseintheretraining program.Itisanticipated thatthevideotaperecording unitcanbeutilizedduringplantevolutions suchasstartupandshutdown, andStationdrills.Thesetapeswillbemostvaluabletotheoperatorwhentheplantevolutions arestaticandthenumberofstart-upsandshutdowns arelimited.9.Asindicated intheA.E.C.Licensing Guide,asenioroperatorshouldexhibitmoredetailedknowledge thanthatrequiredofanoperator. | |
| Also,thesenioroperatorwillberequiredtodisplayamorethoroughknowledge 1Tee=q,~-*elA'e."O''ff~~IJ*j~I Dr.PeterA.MorrisApril15,19709.ofadministrative controlsandprocedures. | |
| Thus,althoughtheretrain-ingrequirements arequitesimilar,theminimumacceptable performance ofthesenioroperatorishigherthanthatofareactoroperator. | |
| Tofurtherillustrate thispoint,theentireOperating Procedures andPre-Operational TestProgramwerewrittenbytheStation.ShiftSupervisors (SeniorOperators).
| |
| Theyhavethusbecomesystem"experts" andhavebeenutilizedintrainingreactoroperators andwillcontinuetodoso.'0.Operators andsenioroperators areevaluated usingseveralfactors,themostimportant beingtheratingbyhisimmediate supervisor whoobserves'hroughdailycontacthiscompetence indischarging thedutiesassignedtohisposition.
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| Sincethisevaluation isasummaryoftheindividual's achievements overaperiodofmanymonths,itshouldbethebestpossi-bleindicator ofhisabilityanddirectlysupportor.rejecthisapplica-tionforA.E.C.licenserenewal.Asecondfactorusedinappraising qualifications forlicenserenewalissuccessful participation intheretraining program.Thelectureseriesisdesignedtoreiterate themoreimportant aspectsoftheareaslistedinparagraph no.l.Itshouldkeeptheindividual asmentally, readyasthetimeatwhichthelicenseexamswerefirstgiven.Athirdfacetwillbeutilizedincertifying applications forlicenserenewal.Inconjunction withparagraph no.4(i.e.startupsandshut-downs),eachoperatorwillsuccessfully completeatleastonereactorstartupandshutdowninthepresenceoftheOperations Supervisor ordesignated assistant.
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| Inaddition, theOperations Supervisor willcon-ducta"walkthrough"witheachofthelicensedreactoroperators toensuretheirreadiness forlicensedrenewal.Ifthereisanydoubtconcerning anindividual's competence fromtheaboveguide-lines,acomprehensive examination ofthescopeoftheAtomicEnergyCommission examwillbegiven.Theoutcomefromsuchanexamination willindicateanindi-vidual'spreparedness forrelicense.
| |
| Verytrulyyours,a.s~~F.J.Schneider VicePresident
| |
| -Operations mjs 1III~~tFjN}} | |
|
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Category:Letter
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 2024-08-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3519, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-30030 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3516, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-29029 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves2021-11-15015 November 2021 Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-06-0404 June 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 22021-01-27027 January 2021 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2 NMP1L3373, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 22021-01-22022 January 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 2 NMP2L2754, Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22021-01-0707 January 2021 Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 NMP2L2749, Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 22020-10-22022 October 2020 Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 2 NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-10-0202 October 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components2020-08-28028 August 2020 Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates2019-11-21021 November 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain2019-02-25025 February 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containm JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre2018-11-0202 November 2018 Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pres NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...2018-10-0101 October 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ... NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039) NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 September 2017 Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017 Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17037A2652017-02-0606 February 2017 Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16131A6542016-05-0404 May 2016 Response to a Question Raised During the Audit ML16131A6552016-05-0404 May 2016 White Paper Prepared in Response to a Question Raised During the Audit NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-03-21021 March 2016 Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP1L3068, Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A....2016-01-25025 January 2016 Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A.... 2024-08-09
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L>Jl'<~I~hm File Cyr'egulatory NIAGARA MOHAWK POWER CORPORATION 6lI](gP f'p r Q.@8~<gled a~Q~QE r go<<NIAGARA~MOHAWK 300 ERIE BOULEVARD WEST SYRACUSC, N.Y.13202 I~~M qc>(~Ci April 15, 1970 Dr.Peter A.Morris, Director Division of Reactor Licensing United States Atomic Energy Commission Washington, D.C.20545
Dear Dr.Morris:
I I j t'l I I I In reference to your letter of February 12, 1970, concerning retraining of.licensed operators, I have discussed below our program and the manner in which we intend to discharge it.Inasmuch as our senior operators have been licensed for 9 months and the reactor operators only 3 months, as well as the fact that we have operated for only 30 full power days, the retraining program is, for the most part, what we will carry out in the year ahead.I hav'e outlined our retraining program by answering the questions posed in your letter, in an effort to ensure that all the information that was requested is submitted.
l.A formal retraining program consisting of scheduled lectures has been set up.As planned, the course of instruction will be approximately 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> in duration covering the following subjects: a.Principles of Reactor Operation b.Features of Facility Design c.General Operating Characteristics d.Instruments and Controls e.Safety and Emergency Systems Standard and Emergency'Operating Procedures g.Radiation Control and Safety sizes will be utilized to check on individual retention as well as to uncover group weakness.2.The retraining program is administered by the Operations Supervisor or a designated assi.stant.
The Reactor Analyst, Radiation Protection Supv., Instrument and Control Supervisor, and other qualified members of the plant staff will conduct the retraining program in their respective fields of interest.3.Each member of the operating staff is issued a complete set of Plant Operating Procedures, Emergency Procedures, Special Procedures, and the Technical Specifications.
When a change is.made in any of these documents, each member is notified by a group distribution notice or 4>s A~I IC" f'1
~Og Dr.Peter A.Morris April 15, 1970 3.is issued a copy of the change.In addition, a master set is maintained with a list of changes made.The Operations Supervisor's Night Order Book contains information on plant evolutions, unusual occurrences, and major equipment malfunctions.
A status of equipment out of commission is maintained by the Station Red Tag Procedures.
In addition, the Station Log contains pertinent information on plant equipment, and each operator is required to read the log prior to coming on shift.4.Every effort will be made to ensure that all operators perform reactor startups and shutdowns, plant conditions permitting.
Each operator has a folder for the express purpose of recording training evolutions completed other than the formal course of instructions.
The operators'bilities will be observed and evaluated by the Station Shift Supv.or other qualified members of the staff, as often as possible.5.Each shift crew is required to"walk through" the Emergency Procedures on a continuing basis to maintain the highest operator proficiency.
Periodically, a simulated drill will be imposed and the shift crew per-formance evaluated.
The formal classroom lecture series will also dis-cuss the Emergency Procedures as well as plant response characteristics during a major accident.6.Periodic fire and/or evacuation drills have and will be conducted.
These drills are normally unannounced so that a degree of realism can be injected and personnel response observed.The Station Superintendent is normally the evaluator during these drills.Niagara Mohawk conducts its own fire school in the local area of the Station.Everyone perma-nently assigned to the Station has received a one-week course in fire fighting.It is anticipated that each Station Shift Supervisor will receive a refresher course in fire fighting at least every two years.7.As presently structured, the retraining program is wholly within the Niagara Mohawk Power organization.
If assistance becomes necessary, it will be employed.8.The audio-visual training aids consisting of video tapes are utilized in both the classroom and as a self-study program.The entire course,"Physics for Reactor Operator," consisting of 21 fifty-minute tapes is available, as well as tapes on major systems such as Control Rod Drive, Rod Worth Minimizer, and the Neutron Monitoring System.Various sub-jects of continuing interest have been recorded here at the Station for use in the retraining program.It is anticipated that the video tape recording unit can be utilized during plant evolutions such as startup and shutdown, and Station drills.These tapes will be most valuable to the operator when the plant evolutions are static and the number of start-ups and shutdowns are limited.9.As indicated in the A.E.C.Licensing Guide, a senior operator should exhibit more detailed knowledge than that required of an operator.Also, the senior operator will be required to display a more thorough knowledge 1Tee=q,~-*e lA'e." Of f~~I J*j~I Dr.Peter A.Morris April 15, 1970 9.of administrative controls and procedures.
Thus, although the retrain-ing requirements are quite similar, the minimum acceptable performance of the senior operator is higher than that of a reactor operator.To further illustrate this point, the entire Operating Procedures and Pre-Operational Test Program were written by the Station.Shift Supervisors (Senior Operators).
They have thus become system"experts" and have been utilized in training reactor operators and will continue to do so.'0.Operators and senior operators are evaluated using several factors, the most important being the rating by his immediate supervisor who observes'hrough daily contact his competence in discharging the duties assigned to his position.Since this evaluation is a summary of the individual's achievements over a period of many months, it should be the best possi-ble indicator of his ability and directly support or.reject his applica-tion for A.E.C.license renewal.A second factor used in appraising qualifications for license renewal is successful participation in the retraining program.The lecture series is designed to reiterate the more important aspects of the areas listed in paragraph no.l.It should keep the individual as mentally, ready as the time at which the license exams were first given.A third facet will be utilized in certifying applications for license renewal.In conjunction with paragraph no.4 (i.e.startups and shut-downs), each operator will successfully complete at least one reactor startup and shutdown in the presence of the Operations Supervisor or designated assistant.
In addition, the Operations Supervisor will con-duct a"walk through" with each of the licensed reactor operators to ensure their readiness for licensed renewal.If there is any doubt concerning an individual's competence from the above guide-lines, a comprehensive examination of the scope of the Atomic Energy Commission exam will be given.The outcome from such an examination will indicate an indi-vidual's preparedness for relicense.
Very truly yours, a.s~~F.J.Schneider Vice President-Operations mjs 1 I II~~t F jN