ML13007A425

University of Missouri-Columbia Research Reactor - License Amendment Application: Operator Requalification Program

ML13007A425
Person / Time
Site:	University of Missouri-Columbia
Issue date:	01/04/2013
From:	Butler R A, Fruits J L Univ of Missouri
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME1584
Download: ML13007A425 (24)

Text

UNIVERSITY of MISSOURIRESEARCH REACTOR CENTERJanuary 4, 2013U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555-0001REFERENCE: Docket 50-186University of Missouri-Columbia Research ReactorAmended Facility License R-103SUBJECT: Written communication as specified by 10 CFR 50.4 regarding the response to the"University of Missouri, Columbia -Request for a Copy of the Physical Security Planand Operator Requalification Program, RE: License Renewal (TAC No. ME1584),"dated December 20, 2012On August 31, 2006, the University of Missouri-Columbia Research Reactor (MURR) submitted arequest to the U.S. Nuclear Regulatory Commission (NRC) to renew Amended Facility OperatingLicense R- 103.On December 20, 2012, as part of the NRC's review of MURR's renewal request, the NRC requested acopy of the current Physical Security Plan (PSP) and Operator Requalification Program. Enclosed is acopy of each of the documents.The PSP is enclosed in a separate envelope that has been classified as SAFEGUARDS INFORMATIONas per 10 CFR 73.21(b)(1). Pursuant to 10 CFR 2.390, we request that this correspondence be withheldfrom public disclosure. No person may have access to SAFEGUARDS INFORMATION unless theperson has an established "need to know" for this information and is authorized per 10 CFR 73.21.Please deliver the enclosed envelope, which contains SAFEGUARDS INFORMATION, to the addressee(Beth Reed) on the envelope. The envelope is clearly marked: "Attention: Beth Reed, Withhold fromPublic Disclosure Under 10 CFR 2.390." If this person is no longer employed at your facility or will beabsent for an extended period, please call (573) 882-5296 for the correct disposition of these materials.As required by 10 CFR 50.30(b), I declare under penalty of perjury that the foregoing is true and correct.ENDORSEMENT:Sincerely, Reviewed and Approved,John L. Fruits Ralph A. Butler, P.E. CHRInNE M. ERRANTEReactor Manager Director Natu Pb-NtySea[Commswe for oone CountMy n3pil 14,720155 Commission Number 115283811513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.edu (ý -AFigbting Cancer with Tomorrow's Technology Enclosed:1. Operator Requalification Program -University of Missouri Research Reactor (MURR)Submitted January 7, 19972. Physical Security Plan for University of Missouri Research Reactorxc: Reactor Advisory CommitteeReactor Safety SubcommitteeDr. Robert Duncan, Vice Chancellor for ResearchMr. Geoffrey A. Wertz, U.S. NRCMr. Alexander Adams, U.S. NRCMr. Craig Bassett, U.S. NRC UNIVERSITY OF MISSOURIOPERATOR REQUALIFICATIONPROGRAMUNIVERSITY OF MISSOURIRESEARCH REACTOR(MURR)SubmittedJanuary 7, 1997 OPERATOR REQUALIFICATION PROGRAMUNIVERSITY OF MISSOURI RESEARCH REACTOR (MURR)SUBMITTED:JANUARY 7, 1997 TABLE OF CONTENTSSection PageT able of C on ten ts .................................... ................ iList of E ffective Pages ................................................. i1.0 IN TR O D U CT IO N ..................................................... 12.0 DESCRIPTION OF THE PROGRPA. ................................. 12 .1 O p eration ........................................................ 22.2 Biennial Requalification Examination and Retraining Lectures ......... 22.3 On-The-Job Training ................................................ 42.4 Annual Operating Examination and Evaluation ...................... 42.5 Documented Review of Changes .................................... 43.0 ADMINISTRATION OF THE PROGRAM .............................. 43.1 Trainihg Coordinator ............................................... 43.2 Reactor Manager and Reactor Operations Engineer ................... 53.3 Individual O perator ................................................ 54.0 R E C O R D S ............................................................. 6APPENDIX A:Annual On-The-Job Training Requirement'Checklist .................. A-1W ritten Examination Form ..................................... A-3* Annual Operating Test Record ........................................ A-4Change Review Sheet ................................................ A -6MURR Operator Active Status Log .................................... A-7APPENDIX B:.Topics for O perating Tests ............................................ B -1O perational Tasks Index .............................................. B -2 MURR OPERATOR REQUALIFICATION PROGRAMLIST OF EFFECTIrE PAGESPAGE DATEDi .. ................. ............................................. O riginal................................................................ Origo nal1 ... .... .. .. ... ... .. .. .. .... .. .... .. .. .. .... ... .... .O r igin al2.. ........... ...............................Original3 ... .. .......... ............ .. .. ....... ............ O rigin al4 ... .. ............ .......... .... ........ ............ 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1.0 INTRODUCTION

In August 1973 the AEC (now the Nuclear Regulatory Commission)published amendments to Parts 50 and 55 to Title 10, Chapter I, Code of FederalRegulations, which require that all licensees submit for approval an operatorrequalification program. All reactor operators and senior reactor operators shallcomplete this program as a condition for retaining their current licenses andmeeting the requirements for renewal of their licenses.This document is the Operator Requalification Program for the University ofMissouri Research Reactor (MURR) which is required by 10 CFR 50.54(i- 1) andconforms generally to the requirements of 10 CFR 55.59(c) as specified by 10 CFR55.59(c)(7). All licensed operators at MURR shall participate in the program andshall satisfactorily complete this program during each requalification cycle, whichshall not exceed 24 months in duration. Each two year requalification program cycleshall be promptly followed by successive requalification program cycles.2.0 DESCRIPTTON OF THE PROGRAMThe requalification program is divided into four major areas which are designed toprovide assurance that all operators maintain competence in all aspects of licensedactivities. The four areas are as follows:a. A biennial written examination which is used to verify the operator'sknowledge level. Preplanned lectures shall be used to retrain those operators whodemonstrate deficiencies in any part of the examination.b. On-the-job training which will ensure (1) that the operator maintains hiscompetence in manipulating the plant controls and in operating all apparatus andmechanisms required by his license, and (2) that he has a thorough understanding ofall emergency procedures.c. An annual operating test which will require the operator or senior operator todemonstrate an understanding of and ability to perform the actions necessary toaccomplish a broad sample of applicable items specified in 10 CFR 55.45(a) (2)through (13). These applicable items are further specified in NUREG-1478, Rev. 1,Non-Power Reactor Operator Licensing Examination Standards, Procedure ES-301N, "Preparation of Operating Tasks at Non-Power Reactors," Attachment 1.1

d. Document review which will ensure all licensed individuals are cognizant ofall design, procedure, and license changes.2.1 OperationTo maintain active status [as defined in 10 CFR 55.53(e)] each licensed operatorshall actively perform the functions of an operator or senior operator for a minimumof four hours per calendar quarter. These functions can be documented for reactoroperators for time performing refuelings, reactor startups, or as console operator.Each senior operator can doctunent time directing refuelings or startups, or timedirecting shift activities.Documentation of active status will be on the Active Status Log form (A-8). If alicensed operator has not been actively performing the functions of an operator orsenior operator as described above, the Reactor Manager shall verify the operator'slicense is current and valid. The operator shall complete a minimum of six hours ofoperation tinder the supervision of an operator or senior operator as appropriate,covering the functions described in the preceding paragraph.2.2 Biennial Requalification Examination and Retraining LecturesBiennially a comprehensive examination will be administered to all operatorshaving a reactor operator or a senior reactor operator license for more than 90 days.This examination will be given within a period of one to two weeks and will be of ascope and complexity equivalent to the license examinations administered by theCommission. The function of the examination is to establish the knowledge level ofthe operator in all areas applicable to the licensed activities he performs. The resultsof this examination shall provide the basis for a determination of those areas in whichan operator needs retraining.The examination will contain questions from each of the following areas asdescribed in procedure ES-40iN, "Preparation of Facility-Specific WrittenExaminations at Non-Power Reactors" of NUREG-1478, Rev. 1, Non-Power ReactorOperator Licensing Examination Standards:A. Reactor Theory, Thermodynamics and Facility Operating CharacteristicsB. Normal and Emergency Procedures, Radiological ControlsC. Plant and Radiation Monitoring Systems2 At the discretion of the facility training coordinator, a review program may beinstituted to prepare individuals for the examination. The review program mayutilize, but is not limited to, the following study aids:a. Lectures or review seminars to present or disciiss in a preplanned mannerthe information relative to each of the areas listed above.b. Worksheet questions and problems which the operator can answer in hisspare time.c. Taped lectures which the operator can review while on shift, but not whileassigned console watch or other license required activity.The Training Coordinator is responsible for scheduling the preparation andadministration of the requalification examination. Twvo separate exams will bedeveloped and administered such that no licensed operators will take an exam theyhelped develop and review. The examinations will be developed from the MURRrequalification question bank and other relevant source material. The examinationswill be open reference.Each examination will be graded by the Train'Ig Coordinator and will besubmitted to the Reactor Manager or Operations Engineer for review. The evaluationof each operator will be facilitated by completing an Examination Form as shown inAppendix A to this document.After all of the examinations have been graded, the Training Coordinator Willprepare the retraining schedule for those operators who were deficient in any area.An operator will be considered deficient in any area of the examination in which hescores less than 70%; he will retrain until he satisfactorily passes reexamination inthe section(s) on which he scored below 70%. If the g-rade for an operator is less than70% averaged over all required sections, the operator shall be placed in an acceleratedtraining program until he has been retrained and satisfactorily passes reexaminationover the section(s) on which he was below 70%,o with a grade greater than 70% in eachsection. Furthermore, the individual will be removed from licensed activities until hepasses his written reexamination. All examinations and reexaminations will berex-iewed with the operator and will be retained for a period covering the duration ofeach operator's license (> 6 years) in the facility's files.'2'-I 2.3 On-The-Job-TrainingThis section of the program provides assurance that all operators will maintainI competence in those major evolutions which can be performed by licensed, operatorsonly. These evolutions consist of control plant manipulations and plant evolutionsrequired by 10 CFR 55.59(c)(3), as applicable to MURR. The requirements areoutlined in the checklist in Appendix A.2.4 Arnual Operating Test and EvaluationThe Reactor Management will, on a continuing basis, observe and evaluate theperformance of all operators to maintain familiarity with the operators' competencein handling routine and emergency evolutions. This program implements the meansof documenting the evaluations made by management.The Training Coordinator, Reactor Manager, Reactor Operations Engineer, orShift Supervisor will annually conduct an operating test for all licensed operators.The person conducting the evaluation will complete an Operator Annual OperatingI Test Evaluation Sheet (Appendix A).2.5 Documented Review of ChangesAll design changes, procedure revisions, and license changes will be reviewedwithin 60 days. The reviews will be documented on the Change Review Sheet(Appendix A). The operator shall read the document attached to the Change ReviewSheet and then sign the sheet verifying he understands the change. The completed.Change Review Sheet will be retained for six years in Reactor Operations files.I 3.0 ADMINISTRATION OF THE PROGRAM'13.1 Training CoordinatorThe Reactor Manager shall assign, a member of the reactor staff to be theTraining Coordinator (TC) for this requalification program. The Training Coordinatorshall be responsible for:a. The overall administration of this program.I b. Scheduling the preparation and administration of biennial writtenexamination.I4I!~_ __ __ _

c. Assisting in the preparation of material., examinations, and retraininglectures or tutoring sessions.d, Reviewing the graded examinations with the operators and scheduling anyretraining indicated by the examination results.e. Periodically reviewing the on-the-job training checklist of each operator toensure that the operators are progressing satisfactorily in this area ofrequalification. If an operator is not progressing satisfactorily in theon-the-job training, the TC will ask the operator's immediate supervisor toaccelerate the operator's efforts.f. Scheduling the reviews required by the Reactor Manager or the ReactorOperations Engineer.g. Scheduling the annual operating test and the staff member who will conductthe test.h. Maintaining all of the requalification records required by Section 4.0.i. Annually reviewing the content of this program.j. Ensuring that all newly licensed operators are aware of the requirements ofthis program and are provided with the necessary requalification materials3.2 Reactor Man aeer and Reactor Operations Enp-ineerThe Reactor Manager, Reactor Operations Engineer and each Shift Supervisorwill assist the TC as necessary to ensure that all operators participate in andcomplete all of the requirements of this program. They shall also schedule andconduct the reviews of changes in the license, facility design and operatingprocedures.If an operator scores an average grade of less than 70% on the biennialexamination, the Reactor Manager shall ensure that the requirements of Section 2.1are met. The Reactor Manager or Operations Engineer will review the reexaminationof a deficient operator with the TC and if the operator's scores are satisfactory, heshall reinstate the operator to normal licensed activities..3.3 Individual OperatorThe extensive responsibilities of the TC for adnministering this progaram do notrelieve the individual operator of the responsibility for ensuring that all of hisrequirements of this requalification prog-ram are completed as required.5 4.0 RECORDSAs indicated in Section 3.1, the TC is responsible for ensuring that all of therecords required by this requalification program are maintained. The following recordsshall be retained at the facility for a period covering the duration of each operator'slicense (> 6 years):a. All examinations and required reexaminations which were administeredduring the requalification period and the answers used to grade these examinations.b. The examination review sheets completed after the biennial examinationand any subsequent reexaminations.c. The annual operating exam performance evaluation sheet used to evaluatethe operator's competence in operating the reactor.d. The retraining schedule used. to correct any deficiencies discovered throughthe biennial examination.e. Copies of the completed on-the-job training checksheets.f. Record of reviews of the License, Operating Procedures, and Facility Designchanges.6 MURR OPERATOR REQUALIFICATION PROGRAMANNUAL ON-THE-JOB TRAINING REQUIREMENTS/CHECKLISTI. Reactivity ChangesEach Reactor Operator must perform five (5) reactivity changes and each SeniorReactor Operator must perform or direct five (5) reactivity changes annually, with atleast one change in each of the below categories.1. Reactor Startup to CriticalityDateInitials ofObserver2. Reactor Power Level Change (in manual mode) of greater than 1 MW.Date _Initials ofObserver _3. Reactor' Shutdown1Date [Initials ofObserverII. Process Equipment OperationEach licensed operator must perform at least two (2) process instrumentationstartups or shutdowns as the Control Room Operator and one startup or shutdownas the Roving Operator.1. Process Instrumentation Startups and Shutdowns as Control Room Operator.Date 1Initials ofObserverStartup _o nShutdown2. Process Instrumentation Startups in~d Shutdowns as.Roving Operator.DateInitials ofObserverStartup ___________________________________SbhitdownA-1 MURR OPERATOR REQUALIFICATION PROGRAMANNUAL ON-THE-JOB TRAL-NING REQUIREMENTS/CHECKLIST (Cont'd)III. Nuclear Insturmentation ChecksEach licensed operator must perform two (2) pre-startup checks of the NuclearInstrumentation.DateInitials ofObserverIV. Reactor RefuelingEach Reactor Operator shall participate in one refueling evolution and each SeniorReactor Operator shall direct the activities of one refueling evolution.DateInitials ofObserverV. Radiation MonitorsEach licensed operator shall annually participate in a Health Physics trainingsession conducted by the Health Physics Department. These sessions will includetraining in use of radiation monitors.DateHP SignatureVI. Abnormal and Emergency Procedure ReviewAll abnormal and emergency procedures shall be reviewed and appraised annuallyby the operating crews. Each operator shall acknowledge completion of the reviewby signing below.Review Completed:DateSignatureVII. Security Plan and Procedure ReviewEach operator shall acknowledge completion of the review by signing below.Review Completed:DateSignatureNote: Observer will be an SRO unless otherwise noted.A-2 MURR OPERATOR REQUALIFICATION PROGRAMWRITTEN EXAMINATION FORMLicense: SR(NameRO0I. EXAMINATION TOPICA. Reactor Theory, Thermodynamics &Facility Operating CharacteristicsB. Normal & Emergency Procedures& Radiological ControlsC. Plant & Radiation Monitoring SystemsAVERAGE SCOREComp Exam ReexaminationGrade Date Grade DateII. REQUALIFICATION SUMMARYA.. Retraining Required: No__ Yes__ Parts (circle) A B CB. Recommend relieved of normal licensed activities while retraining:No YesIII. COMMENTSReviewed by:Approved by:A-3 MURR REQUALIFICATION EXAMINATIONANNUAL OPERATING TEST RECORDNAME:Critical StepsNumber/CorrectOral QuestionsNumber/CorrectControl Console ReactivityTask No:Title:Response to Abnormal EventTask No:Title:Response to EmergencyTask No:Title:______________/___________________/___________________/___________________________/______________In-Facility EvolutionTask No:Title:_____________/___________________________/_________Any TaskTask No:Title:_____________/______________TotalsTotals __________/____________________________/______________PercentageOverall Evaluation:Satisfactory =Unsatisfactory>70%70%Facility Examiner:DateA-4 ANNUAL OPERATING TEST RECORD (Cont'd)Test Administration:1. Tasks are derived from MURR specific tasks in the MNURR Operational Task Index.2. The operating test is "open reference" with a minimum of 5 tasks evaluated.3. Where appropriate, there should be a differentiation between the RO and SRO levelof tasks. An RO is only responsible for RO tasks; an SRO is responsible for all tasks.For each task, the facility specifies the criteria for satisfactory completion andindicates critical steps. Critical steps are those which, if performed incorrectly ornot at all would prevent the system from operating safely or prevent completion ofan essential safety action. Examples of essential safety actions are the ability to:effectively manipulate controls affecting reactivityactuate a reactor tripcomply with technical specificationsreduce excessive levels of radiation and to guard against personnel exposure4. Of the tasks that each operator must perform, at least one must be a controlconsole operation involving a reactivity manipulation. This operation may be part ofan overall evolution including more than one task. For example, an operator mayperform a reactor startup as the first task, then respond to a simulated instrumentfailure during the startup as a second task.At least one task must involve a response to an abnormal event. Examples are aninstrument failure, component failure, radiation monitor alarm or similar problem.At least one task must involve a response to an emergency situation. Examples area building evacuation or a large reactor pool leak or high radiation levels.At least one task must be performed in the facility (i.e., out of the control room,where appropriate).5. At least two questions will be developed to ask the operator at the completion ofeach task. Questions may be selected from. facility question banks or previouslyadministered NRC examinations. However, to the extent possible, the questionsshould:be based on the task or system being operateddiscriiminate between RO/SRO responsibilities, where appropriateemphasize knowledge required for task performance or procedure implementationA-5 MURR OPERATOR REQUALIFICATION PROGRAMCHANGE REVIEW SHEETDocument:Date Revised:After reviewing the attached document, sign below acknowledging that you haveread and understand the change. This document will be returned to the TrainingCoordinator, Room 302 Control Room, for his records (within 60 days).Operator's Name Date Reviewed SignatureNOTE: Only licensed individuals or incividuals seeking licenses are listed.A-6 MURR OPERATOR ACTIVE STATUS LOGOPERATOR NAME:YEAR:NOTE: This form is for documenting active status of licensed operators. The Reactor Manager evaluatesthe status of licensed operators not assigned to shifts and the shift supervisor evaluates thestatus of operators assigned to rotating shifts.QUARTER 1D1Active status needs to be documentedto meet minimum requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)Active status lapsed, documentation requiredfor return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)Shift Supervisor/Reactor Manager InitialDaShift Supervisor Initial (for SROs)SRO Initial (for ROs)DateTotal TimeActivityQUARTER 2D1Active status needs to be documentedto meet minimum requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)Shift Supervisor/Reactor Manager InitialDActive status lapsed, documentation requiredfor return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)Shift Supervisor Initial (for SROs)SRO Initial (for ROs)DateTotal TimeActivityA-7 IMURR OPERATOR ACTIVE STATUS LOGOPERATOR NAIIE:YEAR:NOTE: This form is for documenting active status of licensed operators. The Reactor Manager evaluatesthe status of licensed operators not assigned to shifts and the shift supervisor evaluates thestatus of operators assigned to rotating shifts.QUARTER 3[~]Active status needs to be documentedto meet minimum requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)Active status lapsed, documentation requiredfor return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)Shift Supervisor/Reactor Manager InitialShift Supervisor Initial (for SROs)SRO Initial (for ROs)DateTotal TimeActivityQUARTER 4L1 Active status needs to be documentedto meet minimum requirements (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)Active status lapsed, documentation requiredfor return to active status (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)Shift Supervisor/Re actor Manager InitialShift Supervisor Initial (for SROs)SRO Initial (for ROs)DateTotal Time ActivityA-8 ES-30]N Topics for Operating Tests Attachment 1ES-301NTopics for Operating TestsAttachment IMAJOR SYSTEMS (KAJ):reactorreactor power level controlrodscontrol rod drivesprimary systemsecondary systemmechanical design (fuel assembly)reactor vessel -poolcore constructionAUXILIARY SYSTEMS (AUX):reactor building cooling water controlservice air (compressed air system)sampling systemfire protection systemservice water systemecquipment and floor drainagecontainment air recirculationradioactive waste (solid and liquid)daemineralized waterheating ventilation and air conditioningreactor water clean-up/make-upchemical additionsENGINEERED SAFETY FEATURES (ESF):decay heat removalcore spraycore flooding controlcontainment/reactor building isolationr-eactor building isolationreactor protective systemELECTRICAL (ELT):normal AC supplyemergency AC supplynormal DC supplyemergency DC supplyreactor protectionelectrical po;.wer systembatteriesREACTOR FACILITIES (FAC):fuel handling and storageexposure roomsincore experiment tubesbeam tubesthermal columnspneumatic tube facilitiesliquid waste handling and disposalgaseous waste handlingsolid waste handling and disposalNUCLEAR AND RADIATION SYSTEMS (NUC):startup chanrelslog N channelssafety channelsincore instrumentation/incore probeliquid effluent monitorsarea radiation monitorsgaseous effluentstack gasREACTOR TRANSIENT RESPONSE:Pow.,er increase/decrease -auto controlPo'".,er increase/decrease -manual controlemergency shutdown from full power scram -hot restartsub critical to criticalnormal shut.do-Wn from full poIWerrod malfunctionprimary system leak controlins trumcn t mal functionfuel clad failureIxar incr S L ucar Us30 f 3KB-1iRev,.1,O06/0!/95 REACTOR OPERATOROPERATIONAL TASKS INDEXFACILITY TASKS#1F Perform nuclear instrument pre-startup checks of intermediate range 2 & 3#2F Perform nuclear instrument pre-startup checks of wide range monitorchannel 4#3F Pump waste tank #2 to the sanitary sewer44F Change nitrogen station bottles#5F Perform diesel generator operational checklist46F Perform nuclear instrument pre-startup checks of power range monitorchannels 5 & 6#7F Perform physical adjustment of either IRM channel 2 or 3 drywell at.power#8F Perform physical adjustment of any PRM channel 4, 5 or 6 dry-well at power#9F Area radiation monitor alarm tests#10F Fan failure alarm test# 11F Operational check of the stack monitorREACTOR TASKS# 1R Perform a normal startup to a power level 50 kW#2R Perform a reactor shutdown#3R Perform a reduction in.power#4R Perform a power level changeT5R Continue a normal reactor startup from 50 kW to 10 MW#6R Perform a fuel handling evolution#7R Assuming automatic control of the reactor#8R Startup of the reactor cooling loop#9R Shutdown of the primary cooling system# 1OR Startup of the pool cooling loop .#l.1 R Shutdown of the pool cooling system#4.2R Operation of bypass control valves S-i & S-2B-2 OPERATIONAL TASKS INDEX- Cont'dEMERGENCY TASKS41E Respond to increasing radiation levels before a trip occurs#2E All IRM chamnel 2 indications fail down scale#3E Respond to a loss of secondary flow#4E Respond to V546 A (and/or) B failing to open during operation#5E Respond to a bomb or other overt threat#6E Both V543 A & B fail to open automatically#7E Reactor isolation#8E Failure to scram or rod run-in#9E Reactor scram from unknown source#10E Reactor scram from loss of primary system pressure or flow#11E Area radiation monitoring system (ARMS) fails to actuate a reactor isolation# 12E Control roddrive failure / stuck rod.# 13E Single phasing or low line voltage#14E Failure of experimental apparatus#15E Low fire main pressure#16E Loss of domestic cold water (DCW)#17E Loss of'pool flow#18E Loss of pool water#19E Reactor loop valves (V507A &; V507B) fail to close automatically#20E Pressurizer valves fail to operate#21E High activity levels in primary cooling system#22 E High Stack monitor indications923 E Respond to a medical emergencyB-3 OPERATIONAL TASKS INDEX -Cont'dABNORMNIAL TASKS#1A Reactor is not critical within ECP limitations-4 2A Rod "D" drops off before "drive full-in" clears#3A During reactor operation the reg blade position indication chain breaks#4A Respond to stack monitor low flow alarm#5A Air seals for both personnel airlock doors are discovered to have air suppliesisolated#6A Obtain a pool and/or primary water sample#7A Reactor isolation from instrument failure#8A Rod run-in from an unknown source#9A Loss of containment integrity at power#1OA Loss of cooling tower fan# 1 1A Dropped control rod while at power (10 MW)# 12A Erratic indication on NI channels 2 through 6B-4