ML20044H170

Rev 1 to Lsro Job/Task Analysis.

ML20044H170
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	05/18/1993
From:	Bright E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20044H168	List: ML20044H167 ML20044H170
References
NUDOCS 9306080023
Download: ML20044H170 (100)

Text

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PHILADELPHIA ELECTRIC COMPANY ,

NUCLEAR TRAINING DIVISION TRAINING MATRIX COVER SHEET Program: Limited Senior Reactor Operator Code No.: LSRO (LSRO)

Course: LSRO Initial Item No.: 0001 Rev.: 001

Title:

LSRO Trainina Matrix CL Jl f' ' /A 9~-r r/n)93 Prepared by:

' d If5;McFK Date: 8I) '

Y N'ane/ Title Date: f!!8!T3 P Q t Staff /SME - L'&Sh

. >{ Date: C//7b/3 Plant Efraff/RME - PBAPS S ~

N Date: rllT Y9

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3 NMD Staf(/SM M Q ,

Approved for use.

! C Date: 6 8 [W T ii Mani -- -

'S S bli ) Date: S l0' '-

rain g Pdnsger y

-/P APS T Date: ~ /[- D Training Manager /- NTD O

9306080023 930528 PDR ADOCK 05000277 V PDR

O INDEX TAB CONTENT  ;

1 Introduction JOB TASK SECTION 2 Performance Tasks 3 Directing Tasks t-4 Cognizant Tasks g;'~r

(-. # ,s KNOWLEDGE SECTION 5 Plant Wide Generics 6 Generic Fundamentals 7 Systems O

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MASTER LISTING OF LSRO TERMINAL OBJECTIVES

.O The task statements presented represent the result of.an extensive systematic training development process. The sequence of events for the task analysis of the Limited Senior Reactor Operator (LSRO) is flowcharted in Figure 1 "LSRO Task Analysis Process". The analysis follows the Training System Development (TSD) model. The tasks were derived from ES-701, NUREG 1123, current site procedures and previous job training materials. Tesk statements were reviewed and approved by '

both Peach Bottom Atomic Power Station and Limerick Generating Station Operations Managemer.t, and the Philadelphia Electric Co. Nuclear Maintenance Division.

The task statements are grouped into three categories. The first category is the statements describing tasks which are performed by the LSRO as a part of licensed activities.

The second category is a list of task statements describing functions that the LSRO would be expected to perform or to delegate during performance of licensed activities. Direction of a task is expected to include the skills required to determine the need for the performance of the task, supervise the performance of the task, and verify successful completion. This expectation is commensurate with _

expectations of a senior license holder.

The third category of task statements describes procedural

-( ) activities in which the LSRO will be interfacing with other plant' work groups and procedural requirements. Knowledge of the work being performed is required for the LSRO to evaluate the impact to plant refueling activities and to fulfill the LSRO's license responsibilities.

This list of cognitive tasks is in addition to those specified in Examiner Standard ES-701 for Generic Fundamentals and Systems knowledge per NUREG 1123.

In addition to the above listed categories ES-701 delineated specific subject areas. These subject area K/A objectives from NUREG 1123 were individually evaluated as to applicability to fuel handling activities by a portion of the incumbent LSRO population.

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LSRO TASK ANALYSIS PROCESS l j

Assemble Job Task ,

j List from:

Procedure Analysis Previous Lists Line Management NRC ES-701 Selection l Required Systems and l eneric Fundamentals of Procedural Tasks i

( Commonality Assessment h (

NUREG 1123 Applicable K/A Lists

)

( LSRO Incumbent

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J O DiF Rating j

(

Determine Training Settings

) l Final Matrix - to Programs l

LSRO LSRO Requel Initial Program Program O

FIGURE 1 i 4

The following list of tasks, are tasks determined to be directed by the '

Limited Senior Reactor Operator.

3420040171 Direct actions for jet pump assembly.

3420060271 Direct actions for operation of the grid guide.

3420070271 Direct actions to identify and locate vessel components requiring-inservice inspection (ISI).

3420110271 Direct actions to unlatch control rod blades from above the vessel and transfer the control rod blades using the control rod blade grapple and the control rod blade' latching tool for core alteration and storage.

3420140271 Direct actions for installation and removal of a control rod guide tube.

3420150271 Direct actions for installation and removal of a guida tube seal.

3420190271 Direct actions to move and maintain control of radioactive materials in the spent fuel pools.

3420240271 Direct actions for unlatching, removal, and installation of a Local Power Range Monitor (LPRM).

3420250271 Direct actions for installation and removal of a fuel support.

piece.

3420260271 Direct actions for handling of a vessel specimen. ,

3430010371 Direct actions for Fuel Floor housekeeping.

3440040471 Direct actions for loss of secondary containment.

3440070471 Direct actions to control refuel water level in the reactor cavity and fuel storage areas.

3440080471 Direct actions for a dropped or damaged bundle.

3440090471 Direct act.sns for an inadvertent criticality.

3440140471 Direct actions for fuel floor area radiation monitor alarm.

3450010271 Direct actions to operate the refuel platform.

3450020271 Direct actions to move fuel for core alterations and storage.  ;

3450030271 Direct actions to move blade guides for core alterations and storage.

3450040271 Direct actions for handling and loading of transport . casks.

() 3450050271 Direct actions for movement of fuel in and out of sipping equipment.

3450060271., Direct actions to move fuel in and out of the fuel prep machine.

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- The following list of tasks, are tasks determined to be performed by the Limited Senior Reactor Operator.  :

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'3410020371 Perform OJT/0JE. .

3420030271 Perform operation of underwater camera / equipment for inspections, f 3420080271 Perform notifications to ensure radiological controls.for core l 3

component movement.

3420090271 Perform administrative actions for core component movement.

3420120271 Perform actions to verify refueling interlocks and required equipment operability.

34201802'71 Perform actions for mapping and orientation of components in the core and spent fuel pool. i 3420200271 Perform top of core inspection prior to core alterations.

3420210271 Perform actions for completion, including revision, of CCTAS sheets.

3430020371 Perform actions to fulfill the shift responsibilities of the licensed Fuel Handling Director.

3430030371 Perform communications using plant communications systems and controls, including independent verification.

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3430050371 Perform administrative actions for troubleshooting and to make temporary circuit alterations.

3430060371 Perform administrative actions to make temporary changes to procedures.

3430070371 Perform administrative actions for surveillance tests.

3430090371 Perform actions to implement Plant Evolutions /Special Test procedures.

3430120371 Perform administrative actions for direct reading dosimetry.

3430130371 Perform administrative actions for use of protective clothing.  :

l 3430160371 Perform administrative actions for contamination control. l 3430170371 Perform the operation of survey instruments.

3430190371 Perform administrative actions to remove and return equipment to service.

I 3440160471 Perform actions to backup the. inflatable seals during a loss of

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service air.

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The following list of tasks, are tasks determined to be required-knowledge. of the Limited Senior Reactor Operator. This list <.f cognitive tasks is in addition to those specified in Examiner Standard ES-701 for Generic Fundamentals and Systems knowledge per NUREG 1123, 3410019971 Cognizant of the methods for normal makeup to the fuel storage pool. I 1

3410039971 Cognizant of the methods of decay heat removal through fuel pool .i cooling.

3410049971 Cognizant of the methods for inflation and venting of refueling l area seals. ,

i 3410059971 Cognizant of administrative controls for heavy loads.

3410069971 Cognizant of the methods for establishing secondary containment. j 3420029971 Cognizant of the methods for installation, operation, and removal of the fuel floor water cleanup system.

3420059971 Cognizant of the methods for installation and removal of MSL plugs.

3420109971 Cognizant of actions to verify shutdown margin.

3420139971 Cognizant of the method for installation and removal of the control rod drive thermal sleeve.

O 3420169971 Cognizant of the methods to verify control rod operability.

t 3420179971 Cognizant of the methods for receipt, examination, and handling of new fuel and examination of irradiated fuel.

?420229971 Cognizant of the methods of underwater vacuum operation. .

3420239971 Cognizant of the methods of fuel sipping.

3420279971 Cognizant of the methods for refuel platform inspections.

3420289971 Cognizant of the methods for fuel prep machine inspections.

3420299971 Cognizant of the methods for unlatching and latching the shroud head / steam separator.

3420300271 Cognizant of the methods for inspection of refueling component grapples.

3430049971 Cognizant of working hour restrictions.

3430089971 Cognizant of administrative control for locked valves. >

3430109971 Cognizant of the Station Qualified Reviewer process and the use of ,

operator aids.

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3430119971 Cognizant of administrative controls for access to locked high

, radiation areas.

3430149971- Cognizant of administrative controls for respiratory protection.

3430159971 Cognizaat of administrative controls for ALARA.

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3430189971 Cognizant of administrative controls for Special Nuclear Material, 3440019971 Cognizant of the metheds for control of' refuel. floor water inventory.

3440029971 Cognizant of the response to alarms on LGS Fuel Floor panel 10C222.

3440039971 Cognizant of the response to alarms on PBAPS Fuel Floor Panel 3 l

20C075.

3440059971 Cognizant of actions in the event of fire.  !

3440069971 Cognizant of actions to backup fuel pool cooling with RER shutdown ,

cooling.

3440109971 Cognizant of actions in the event of an injury.

3440119971 Cognizant of actions in the event of a radioactive liquid spill. ,

3440129971 Cognizant of actions for emergency classification.

3440139971 Cognizant of cetions for evacuation.

3440159971 Cognizant of actions in the event of loss of service water to FPC O

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Plant Wide Generics (294001) )

WUM KNOWLEDGE' APP LSRO SRO NOTE {

A 101 Ability to obtain and verify control procedure copy

• 4.5 3.4  ;

A.102 Ability to execute procedural steps

• 4.8 4.2 A 103 Ability to locate and use procedures and station directives related to shift *-

4.7 3.7 staffing and activities )

A 104 Ability to operate the plant phone, paging system, and two-way radio

• 4.2 3.2. .!

A 105 Ability to make accurate, clear, and concise verbal reports

• 4.5 3.8 ,

A 106 Ability to maintain accurate, clear and concise logs, records, status boards and

• 4.5 3.6 reports A 107 Ability to obtain and interpret station electrical and mechanical drawings

• 3.5 . 3.7 j A 108 Ability to obtain and interpret station reference material such as graphs,

• 2.7 3.6 nomographs, and tables which contain system performance data A 109 Ability to coordinate personnel activities inside the control room 2.2 4.2 1 A 110 Ability to coordinate personnel activities outside the control room

• 4.7 4.2 A 111 Ability to direct personnel activities inside the control room 1.8 4.3 1 A 112 Ability to direct personnel activitics outside the control room

• 4.7 4.2 A 113 Ability to locate control room switches, controls, and indications, and to determine 2.4 4.3 1 that they are correctly reflecting the desired plant lineup A 114 Ability to maintain primary and secondary plant chemistry within allowable limits 1.5 3.4 1 A 115 Ability to use plant computer to obtain and evaluate parametric information on 1.7 3.4 i system and component status A 116 Ability to take actions called for in tr.e Facility Emergency Plan, including (if

• 2.5 4.7 required) supporting or acting as the Emergency Coordinator K 101 Knowledge of how to conduct and verify valve lineups

• 2.8 3.7  ;

K 102 Knowledge of tagging and clearance procedures 4.1 4.5  ;

K 103 Knowledge of 10 CFR 20 ard related f acility radiation control requirements

• 4.5 3.8 K 104 Knowledge of facility ALARA program

• 4.4 3.6 e K 105 Knowledge of facility requirements for controlling access to vital / control areas

• 3.5 - 3.7 ,

K 106 Knowleoge of safety procedures related to rotating equipment

• 3.7 3.4 K .107 Knowledge of safety procedures related to electrical equipment

• 4.2 3.6 K 108 Knowledge of safety procedures related to high temperature

• 3.5 3.4 I K 109 Knowledge of safety procedures related to high pressure 2.2 3.8 - 1 K 110 Knowledge of safety procedures related to caustic solutions 1.7 3.4 1 K 111 Knowledge of safety procedures related to chlorine 1.2 3.3 1 K 112 Knowledge of safety procedures related to noise 18 3.1 1 K 113 Knowledge of safety procedures related to oxygen-deficient environment 1.8 3.6 1 K 114 Knowledge of safety procedures related to confined spaces 2.0 3.4 . 1 K 115 Knowledge of safety procedures related to hydrogen 1.2 3.8 1 K 116 Knowledge of facility protection requirements, including fire brigade and portable

• 3.2 3.8 fire-fighting equipment usage K 117 Knowledge of the equipment rotation schedules and the reasoning behind the rotation 1.2 2.6 1 ,

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-> .i j VALVES (291001)

NUM KNOWLEDGE APP. LSRO SRO NOTE j j

, /3 K 101 -The operation of safety valves 2.1 3.5 i K 102 The operation of relief valves 2.1 3.6' 1

.j K 103 - The relationship of valve position to flow rate and back pressure 1.7 2.8 1. l K 104 closed and 1.8 2.8 1. l Valve spring design loaded for a given valves, f ailed-valve hydraulic, position contro pnetsnatically (open, t ted valves,electric as-is positions,  ;

motor-driven valves)

K 105 The significance of stem position (valve status) for gate valves 2.2 2.8 1 K 106 Safety concerns in the use of gate valves (protect valves seats, open slowly) 2.2 2.7 - 1 K 107 Cautions for placing a valve controtter in manual mode 1.8 3.4 ' 1 -i K 108 Emergency operation of MOV with motor inoperable 1.7 3.5 1 K 109 The stroke test for a valve, including the use of a stopwatch 1.2 2.7 1 K 110 Principles of operation and purpose of check valves 2.2 ' 3.1 1 K 111 Operation of manual valves and verification of position with indicator lights 1.8 3.2 1 K 112 Reason for using globe valves versus gates valves for throttling 1.8 . 2.8 1 N s l

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SENSORS AND DETECTORS (291002)

WUM KNOWLEDGE APP LSRO SRO NOTE K 101 Flow - Operation of venturis and orifices

• 1.5 2.5 5

. K 102 Flow - Temperature compensation requirements 1.4 2.5 i K 103 Flow - Ef fects of gas or steam on liquid flow rate indications (erroneous reading) 1.5 2.6 i K 1D4 Flow Modes of f ailure 1.5 3.1 1 K 105 Flow - Operation of a flow D/P cell type flow detector 1.7 3.1 1 K 106 Level Temperature / pressure compensation requirements 1.8 2.9 1 K 107 Level - Operation of a dif ferential pressure level detector

• 2.4 3.2 5 K 108 Level - Effects of operating environment (pressure, temperature, and radiation) 2.4 2.9 1 K 109 Level - Modes of fatture

• 2.7 3.3 K 110 Pressure - Theory of operation of bourdon tubes, diaphragms, bellows, and pressure 1.5 2.5 1 detectors K 111 Pressure - Ef fects of operating environment (pressure, temperature, radiation) 1.4 2.5 1 K 112 Pressure - Operation of a pressure D/P cell

• 1.7 2.9 5-K 113 Pressure - Modes of f ailure 1.5 3.1 1 K 114 emp ature - Theory of operation of T/C, RTD, thermostats, thermometers (expanding

• 2.1 2.4 5 K 115 Temperature - Indications of f ailure modes of T/C, RTD, thermometers 2.0 2.8 1 K 116 Position Detectors - Failure modes of reed switches, LVDT, limit switches, and 2.1 2.7 1 potentiometers ,

K 117 Position Detectors - Applications of reed switches, magnets, LVDT, potentioneters, 2.1 2.4 1 and limit switches K 118 Electrical - Applications of voltmeters, aweeters, f requency, and ground detectors 2.0 2.4 1 K 119 Nuclear instrumentation - Operation of fission chambers, ion chambers

• 4.2 3.1 K 120 Nuclear Instrumentation - Neutron monitoring indication units

• 4.1 3.2 K 121 Nuclear Instrumentation - Ef fects of voltage changes on neutron detector performance 4.0 . 2.9 4 K 122 Nuclear Instrumentation - Failure modes of fission chambers, ion chambers, and

• 4.0 3.1 proportional counters K 123 Radiation Detection - Operation of ion chambers, G-M tubes and scintillation

• 4.0 2.9 detectors l K 124 Radiation Detection - Use of portable radiation monitoring instruments

• 3.7 3.2

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CONTROLLERS AND Pos!TIONERS (291003) I NLM KNOWLEDGE APP LSRO SRO Note K 101 Function and operation of flow controller in manual and automatic modes 1.5 3.7 i K 102 Function and operation of a speed controller 1.4 3.6 1 K 103 operation of a valve controller, including seal-in features 1.4 3.4 1 K 104 Function and operation of pressure and temperature controllers, including pressure 1.4 3.3 1 and tenperature control valves K 105 Function end charer.teristics of valve positioners 1.5' 2.8 1 K 106 Function snd characteristics of governors and other mechanical controllers 1.7 2.6 1 K 107 Safety precautions with respect to the operation of controllers and positioners 1.4 2.8 i K 103 Theory of operation of the following types of controllerst electronic, electrical, 1.4 2.2 1 and pnetsnatic j K 109 Effects on operation of controllers due to proportional, proportional and reset, and 1.2 2.2 1 proportional and integral features i

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PUMPS (291004)  :

1 NUM KNOWLEDGE APP' LSRO SRO NOTE K 101 Centrifugal Identification, symptoms, and consequences of cavitation - 1.8 - 3.2 1 K 102 Centrifugal - Reasons for venting a centrifugal pump 1.8 2.8 1 K 103 centrifugal Consequences of air binding 1.8 2.9 1.

K 104 Centrifugal - Consequences of operating a p m p dead headed or for extended 2.0 3.1 1 recirculation times -

K 105 centrifugal Discuss relationships among head, flow, speed, and power 2.1. 2.9 1 K 106 Centrifugal - Need for net positive suction head (NPSH) 2.2 3.3 1-effects of. loss of suction j K 107 Centrifugal - Starting current and operating current interpretation 1.7 2.8 1 K 108 centrifugal - Purpose of starting a pump with discharge valve closed 1.7 2.8 1 K 109 Centrifugal - Pressure and flow relationship of pm ps in parallel 1.7 2.4 1 K 110 Centrifugal - Pressure and flow relationship of pumps in series 1.7 ' 2.4 1 K 111 Centrifugal - Definition of punp shutof f head 1.7 2.5 1 K 112 Centrifugal "Runouta of a centrifugal pump (definition, indications, causes, 1.8 2.8 1 effects, and corrective measures)

K 113 Centrifugal - Principles of operation of a centrifugal pump 2.2 2.7 1 K 114 Centrifugal - Relationship between flow from a p m p and suction heads 1.7 2.5 1 K 115 Centrifugal Purpose of punp minimum flow requirements Positive Displacement 1.8 2.9 1 K 116 Positive Displacement - Discuss relationship among head, flow, speed, and power 1.4. 2.7 1 K 117 P9sitive Displacement - Net positive suction head (NSPH) requirements for a positive 1.5 2.6 1 displacement pump K 118 Positive Displacement - Consequences of operating a positive displacement punp 1.2 3.3 1 against a closed flow path K 119 Positive Displacement - Functions and characteristics of positive displacement pumps 1.8 2.6 1 .j

. K 120 Positive Displacement - Reason for starting a positive displacement pump with the 1.4 3.1 1  ;

discharge valve open 4 need to clear the flow path l K 121 P9sitive Displacement Safety procedures and precautions associated with positive 1.4 3.0 1

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displacement pumps ,

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MOTORS AND GENERATORS (291005)

NUM KNOWLEDGE APP LSRO SRO NOTE 1.7 2.6

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k K 101 Locked motor rotor, recognition from motor parameters 2.1 2.7 1

K 102 Potential consequences of overheating motor insulation or motor bearings 1 K 103 Causes of excessive current in motors, such as low voltage, overloading , and 1.8 2.7 1 mechanical binding n

K 104 alationship between punp motor current (ansneter reading) and the following pwp 1.5 2.7 1

.uid flow, head, speed, and stator tenperature K 105 Explain the difference between starting current and operating (running) current in a 2.0 2.7 1 motor K 106 Reason for limiting the number of motor starts in a given time period 1.8 3.1 1 K 107 Electrical units volts, amps, A.C., D.C., and hertz 2.5 2.6 4 K 108 consequences of overexcited /underexcited 1.7 2.6 1 K 109 Interrelations of the following: VfRs, Watts, Amps, Volts, Power factor 1.7 2.6 1 5

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HEAT EXCHANGERS AND CONDENSERS (291006)

APP 'LSR0 SRO NOTE

'NUM KNOWLEDGE K 101 Startup/ shutdown of a heat exchanger 2.4 2.7 1 l

K 102 Proper filling of a shell and-tube heat exchanger 2.0 2.6 i K 103 Basic heat transfer in a heat exchanger

• 2.7 2.6 K 104 Effects of heat exchanger flow rates that are too high or too low

• 2.5 2.8 K 105 Flow paths for the heat exchanger (counterflow and U- types) 2.4 - 2.3 1.

K 106 Components of a heat exchanger (shells, tubes, plates, etc.)

• 2.7 2.3 5 K 107 Control of heat exchanger temperatures 2.1 2.8 1-K 108 Relationship between flow rates and temperatures 2.4l 3.0 1

• 2.5 2.8 -

K 109 cefinition of thermal shock i

K 110 Principle of operation of condensers 1.5 2.8 1 K 111 Relationship between condenser vacuum and backpressure 1.4 2.8 1* ,

K 112 Causes of natural circulation 3.2 3.0 8 K 113 Use of steam tables to determine saturation pressure for a given tenperature and vice 1.5 2.9 - 1 versa 2.4 . 3.2 K 114 Fluid haniner and methods of prevention 1

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K 115 Effects of heat exchanger tube fouling 1.7 2.8 1 K 116 Effects of scaling on heat exchanger operation 1.7 2.6 1 K 117 Consequences of heat exchanger ' tube f ailure 2.1 2.8 1 K 118 Reasons for non-condensible gas removat 1.8 2.9 1 O e i

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DEMINERAL12ERS AND 10N EXCHANGERS (291007)

NUM KNOWLEDGE APP LSRO SRO NOTE

/~*\ K 101 Effect of excessive differential pressure on demineralizer performance 2.0 2.7 1.

• - ' K 102 Effects of channeling in a demineralizer 2.1 2.6 1 K 103 Purpose of a demineralizer 2.5 2.9 9 K 104 Reason for sanpling intet and outlet of demineralizer 2.4 2.7 K 105 Purpose of demineralizer D/P gauge 2.5 2.5 4 K 106 Reason for demineralizer tanperature and flow limits 2.2 2.7 1 K 107 Principles of demineralizce- operation 2.2 2.5 1 K 108 Demineralizer D/P to determine condition of demineralizer resin bed 2.0 2.6 1 K 109 Effects of demineralizer operation on water conductivity 2.0 2.7 1 S

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BREAKERS, RELAYS AND DISCONNECTS (291008)

NUM ' KNOWLEDGE APP LSP0 SRO- NOTE K 101 Pur se for racking out breakers (de-energize cornponents and associated control and 2.4 3.6 1 ind cation circuit )

y 3.5' K 102- Local indication that breaker is open, closed or tripped

• 3.2

• K 103 Meaning of power supply circuit breaker indicator lights and capability to remotely

• 3.0 3.4 open and close K 104 Operation of various push buttons, switches and handles and the resulting action on -

• 3.0 3.3 .

breakers K 105 Function of thermal overload protection device

• 2.8 3.1 K 106 Interpreting one-line diagram of control circuitry

• 3.7 3.6 l K 107 Safety procedures and precautions associated with breakers, including MCC bus

• 3.1 3.7 l breakers, high, medlun and low voltage breakers, relays and disconnects K 108 Effects of closing breakers with current out of phase, different frequencies, high

• 2.8 3.5 voltage differential, low current, or too much load K 109 Effect of racking out breakers on control and indicating circuits and removal of

• 3.0 ~ 3.5 control pcwer on breaker operation K 110 Function, control, and precautions associated with disconnects' 2.2 3.4 1 i h

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A 4 a NEUTRC2S (292001)

NUM KNOWLEDGE APP LSRO SRO NOTE K 101 Define fast, intermediate, and slow neutrons 4.2 - 3.5 - 6 V K 102 Define prompt and delayed neutrons

• 4.1 3.6 -

K 103 Define thermal neutrons

• 4.1 2.8 K 104 Describe neutron moderation 4.2 2.8 K 105 Identify characteristics of good moderators

• 4.1 2.8 K 106 Define neutron lifetime '4.0 2.7 -3 K 107 Define neutron generation time 4.0 3.4 6 K 108 Describe fast flux, thermal flux, and flux distribution 4.0 3.5 6

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NEUTRON LIFE CYCLE (292002)

APP LSRO SRO NOTE NUM KNOWLEDGE l K 101 Describe the neutron life cycle using the following term: --fast fission factor 4.0 2.7 3 K 102 Describe the neutron life cycle using the following term: --fast non leakage 4.0 3.1 6 l probability factor K 103 Describe the neutron life cycle using the following term: --resonance escape 4.0 3.2 6 i probability factor K 104 Describe the neutron life cycle using the following term: -thermal non-leakage 4.0 2.8 3 probability factor K 105 Describe the neutron life cycle using the following term: --thermat utilization 4.0 2.5 3 ,

factor K 106 Describe the neutron life cycle using the following term: --reproduction factor 4.0 2.5 3 K 107 Define critical, suberitical, and supercritical with respect to a reactor

• 4.5 2.6 K 108 Define ef fective multiplication factor and discuss its relationshfp to the state of a

• 4.5 3.1 reactor

• 4.4 3.1 K 109 Define K-excess K 110 Define shutdown margin

• 4.5 2.9 K 111 Define reactivity

• 4.5 3.2 K 112 State the relationship between reactivity and effective multiplication factor

• 4.5 2.9 K 113 Calculate shutdown margin using procedures and given plant parameters 4.0 3.3 6 K 114 Evaluate change in shutdown margin due to changes in plant paramsters

• 4.0 2.5 i

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REACTC:t KINETICS AND NEUTRON SOURCES (292003) l NUM KNOWLEDGE APP- LSRO SRO NOTE- I K 101 Explain the concept of subcritical fruttiplication .* 4.2 2.5 l

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% K 102 Given the sinplified fornuta for subcritical multiplication, perform calculations 4.0 2.9 3 'l involving steady state count rate and source count rate K 103 Describe the production of delayed neutrons- 4.4 3.1 4 K 104 Define delayed neutron fraction and effective delayed neutron fraction

• 3.8 2.4 state the reasons for variation K 105 Define reactor period

• 4.5 . 2.8 K 106 Explain the effect of delayed neutrons on reactor period

• 4.4 2.7.

K 107 Explain pronpt critical, pronpt jtsp, and pronpt drop

• 4.5 2.4 K 108 Given the power equation, solve problems for power changes and period 4.1 2.4 7-K 109 Define doubling time and calculate it using the power equation

• 4.2 3.1 ,

K 110 Explain the necessity for installed neutron sources in a reactor core 4.4 3.2 6 K 111 Explain why installed sources are not needed after one cycle of core operation 4.2 2.9 3 O (,

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REACTIVITY COEFFICIENTS (292004) 'l NUM KNOWLEDGE APP LSRO SRO NOTE l i

K 101 Define the temperature coefficient of reactivity

• 4.2 3.1 ]

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Describe the ef fect on the magnitWe of the tenperature coef ficient of reactivity * .

4.1 2.9  !

N K 102 from changes in moderator temperature and core age K 103 Explain resonance absorption

• 3.7 3.2 ]

K 104 Explain doppler broadening and self-shielding

• 3.7 3.7 'l K 105 Define the doppler coefficient of reactivity

• 3.7 3.6 K 106 Describe the effect on the magnitude of the doppler coefficient of reactivity for 4.0- 3.4 6 ,

changes in the following: -Moderator temperature l K 107 3.2 3.3 6 Describetheeffectonthemabnitudeofthedopplercoefficientofreactivityfor changes in the following: - ore void fraction l K 108 Describe the ef fect on the magnitWe of the doppler coef ficient of reactivity for 3.5 . 2.8 7 changes in the following: --Fuel temperature K 109 Describe the effect on the magnitude of the doppler coefficient of reactivity for 3.8 2.6 3 changes in the following: -Core age K 110 Define the void coefficient of reactivity

• 3.2 2.8 K 111 Describe the effect on the magnitude of void coefficient from changes in the 3.2 2.2 7 following: -Core void fraction K 112 Describe the effect on the magnitude of void coefficient from changes in the 3.2 2.2 7 i

following: --Fuel tenperature K 113 Describe the ef fect on the magnitude of void coef ficient from changes in the 3.2 3.2 7 following: --Core age K 114 Compare the relative magnitudes of the temperature, doppler, and void coefficients of

• 4.0 2.8 reactivity 1

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CONTROL RODS (292005)

NUM KNOWLEDGE APP LSRO ' SRO NOTE 2.9 K 101 Relate notch and rod positlon

• 4.5 K 102 Name the material used for thermal neutron absorption in control rods

• 4.5 3.1 ,

K 103 Describe nuclear properties of active material in the rod 4.5 2.9 3 l K 104 Predict direction of change in reactor power for a change in control rod position

• 4.5 3.3 K 105 Define rod density

• 4.5 2.8 K 106 Define reactor scram

• '4.5 2.8  !

K 107 Define control rod worth, differential control rod worth, and integral control rod

• 4.5 2.4 worth K 108 Explain the shape of curves for differential and integral CRW versus rod position 4.1 2.4 3 K 109 Explain direction of change in the magnitude of CRW for a change in moderator

• 3.7 2.5 ,

tepperature, void f raction, and control rod density, and Xeron K 110 State the purpose of flux shaping and rod sequencing

• 3.8 2.8 K 111 Define deep rods, and shallow rods 3.2 2.7 7  ;

K 112 Describe effects of deep, and shallow control rods on axial and radial flux

• 3.2 2.5 '

distribution i

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FISSIOW PRODUCT POSIONS (292006)

WlM . KNOWLEDGE APP LSRO SRO NOTE K 101 Define fission product poison * '3.1 2.9 K 102 State the characteristics of Xenon-135 as a fission product poison

• 3.1 2.7 K 103 Describe the production of Xenon-135

• 3.1 2.6 K 104 Describe the removal of Xenon-135

• 3.1 3.3 K 105 Describe the following processes and state their effect on reactor operations:

• 3.0 2.6 -

" Equilibrium xenon K 106 Describe the following processes and state their effect on reactor operations:

• 2.7 3.1

--Maneuvering xenon K 107 Describe the following processes and state their effect on reactor operations:

• 2.5 3.0 '

--Xenon following a scram K 108 Describe the ef fects that Xenon concentration has on flux shape and control rod

• 2.5 2.6 patterns K 109 Plot the curve and explain the reasoning for the reactivity insertion by xenon-135 2.7 2.7 4 versus time for the following: --Initial reactor startup and ascension to rated power K 110 Plot the curve and explain the reasoning for the reactivity insertion by Xenon 135 2.5 2.7 4 versus time for the following: --Reactor startup with xenon-135 already present in '

the core K 111 Plot the curve and explain the reasoning for the reactivity insertion by Xenon 135 2.4 2.7 4 versus time for the following: " Power changes from steady-state power to another K 112 Plot the curve and explain the reasoning for the reactivity insertion by xenon-135 2.4 2.7 4 versus time for the followings --Reactor scram K 113 Plot the curve and explain the reasoning for the reactivity insertion by xenon-135 2.8 3.1 4 i versus time for the following: " Reactor shutdown K 114 Explain the process and reasons for the Reactor Operator to compensate for the time 2.5 2.6 4 dependent behavior of Xenon-135 concentration in the reactor K 115 State the characteristics of Samarium-149 as a fission product poison 2.8 2.6 3 K 116 Describe the production of Samarit.sn-149 3.0 2.6 3 K 117 Describe the removal of Samarium 149 3.0 2.7 3 K 118 Define equilibrium samarium 3.0 2.6 3 K 119 Plot the curve and explain the reasoning for reactivity insertion by Samarium-149 2.2 2.6 3 versus time for the following: --Initial reactor startup and encension to rated power l K 120 Plot the curve and explain the reasoning for reactivity insertion by Samarium-149 2.4 2.8 3 l i versus time for the following: " Reactor shutdown K 121 Describe ef fects of power changes on samaritsn concentration 2.5 2.3 3 K 122 Compare effects of Samarium-149 on reactor operation with those of xenon-135 2.8 2.3 3 .j l

[

FUEL DEPLETION AND BURNABLE POSIONS (292007)

NUM KNOWLEDGE APP LSRO SRO NOTE K 101 Define burnable poison and state its use in the reactor

• 3.0 2.8

[-

\ - K 102 Describe and explain distribution of burnable poisons in the core 3.0 3.0 6' K 103 Given a curve of K-ef f ective versus core age, state the reasons for maxinnsn, minimisn,

• 3.4 2.8 '

and inflection points n

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REACTOR CPERATIONAL PHTSICS (292008)

NUM KNOWLEDOE APP -LSRO SRO NOTE  ;

2.4 2.8 1 i O K 101 Startup controlledandduring Approach to Criticality the approach to criticalityList parameters which she"ld be monitored and K 102 Startup and Approach to Criticality - List reactivity control mechanisms which exist

• 3.0 '2.8 1 for plant conditions during the approach to criticality K 103 Describe count rate and period response which-

• 3.0 3.0 Startup should beand Approach observed for rodto withdrawa Criticality l during the approach to criticality K 104 Startup and Approach to Criticality - Relate the concept of suberitical

• 3.0 2.9 multiplication to predicted count rate and period response for control rod withdrawal during the approach to critical K 105 Startup and Approach to Criticality - Explain characteristics to be observed when the

• 2.8 3.2 reactor is very close to criticality K 106 Criticality - List para.neters which should be monitored and controlled upon reaching

• 2.5 2.8 initial criticality K 107 Criticality Define criticality as related to a reactor startup

• 2.2 2.6 5 K 108 Criticality - Describe reactor power and period response once criticality is reached

• 2.7 2.8 K 109 Intermediate Range operation - List parameters which should be monitored anu 1.7 2.9 1 controlled during the intermr:diate phase of startup l K 110 Intermediate Range Operation - Explair. procedures for adjusting reactor period during 1.7. 2.7 1 the intermediate phase of startup K 111 Intermediate Range Operation - Discuss the concept of the point of adding heat (POAH) 1.7 2.6 1 and its inpact on reactor power K 112 Intermediate Range Operation - Describe reacter power and period response prior to 1.7 2.9 1 reaching the POAH K 113 Intermediate Range operation - Explain characteristics to look for when the PCAH is 1.7 2.7 1 reached K 114 Heatup Operation - Describe three parameters to be monitored and controlled during 1.7 2.5 1 heatup K 115 Heatup operation - Describe reactor power and period response af ter reaching the 1.5 2.7 1 point of adding heat K 116 Heatup Operation - Explain proceduros for establishing and controlling heatup rate 1.5 2.5 1 K 117 Power Operation

• Describe three parameters to be monitored and controlled during 1.7 2.6 1 power operation K 118 Power Operation - Describe means by which reactor power will be increased to rated 1.5 2.7 1 power K 119 Power Operation - Explain transient and steady-state effects of a control rod 1.5 3.6 1 withdrawal on reactor power and void fraction content K 120 Power Operation - Explain transient and steady-state effects of an increase in core 1.5 3.5 1 flow on reactor power and void fraction K 121 Power Operation - Explain the relationship between steam production rate and reactor 1.5 3.4 1 6 i

power given specific conditions K 122 Power Operation - Explain the effect that opening steam bypass valves, during power 1.5 3.3 1 operation, will have on reactor power K 123 Power operation - Explain the necessity for rod pattern exchanges 1.8 3.1 1 K 124 Power Operation Describe the parameters to be monitored and controlled during rod 1.8 3.6 1 pattern exchanges K 125 Reactor Response on a Scram Explain the shape of a cu ve of reactor power versus 2.1 3.7 1 time after a scram K 126 hormal Reactor Shutdown - Explain reactor power response to a decrease in core flow 2.7 3.5 7 K 127 Normal Reactor Shutdown - Explain reactor power response to a control rod insertion

• 2.8 3.5 K 128 Normal Reactor Shutdown - Explain the necessity for inserting control rods in a 2.8 3.7 7 predeterminec sequence during normal shutdown K 129 Normal Reactor Shutdown - Define decay heat

• 3.8 3.6 K 130 Wormal Reactor Shutdown - Explain the relationship between decay heat generation and:

• 4.1 3.5 a) power level history, b) power production, and c) time since reaction shut down ,

b

THER;C0YNAMIC UNITS Aun PROPERTIES (293001)

NLW KNOWLEDGE APP LSRO SRO NOTE K 101 Convert between absolute and relative pressure and vacuum scales 1.8 2.3 1

-O K 102 Recognize the difference between abootute and relative temperature scales 1.8 2.1 1 K 103 Describe how common pressure end levet sensing instrunents work 2.5 2.7 3 K 104- Explain relationsi?os between work, power, and energy 2 1.9 1 O

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BASIC ENERGY CONCEPTS (293002) ,

NUM KNOWLEDGE APP LSRO SRO NOTE 2.1 1.7 1

[\

K 101 Identify energy and work forms 2.5 1.9 . 1 N K 102 Explain the law of conservation of energy K 103 Explain the difference between state and phase of a working substance 2.4 1.7 1 2.2 2.4 .1 K 104 Explain the application of enthelpy in the monitoring of plant processes K 105 Identify the relationship between heat flow during a process and a T-s diagram 2.2 2.2 ' 1-representation of the process K 106 Define specific heat 2.4 2.1 -1 K 107 Apply specific heat in solving heat transfer problems 2.2 1.6' 1 t

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s STEAM (293003)

~ APP LSRO SRO NOTE NUM KNOWLEDGE K 101 Describe ef fects of pressure on density or specific volune of a liquid 2.2 2.4 1

/

2.1 2.3 K 102 Distinguish between liquids, vapors, gases, and fluids 1 K 103 Define latent heat of vaporization 1.7 2.4 1 K 104 Define vaporization line 1.7 2.1 1  ;

1.7 1.8 I K 105 Define critical point 1 K 106 Define vapor dome 1.7 2.0 1 K 107 Define saturated liquid 1.8 2.8 1 K 108 Define wet vapor 1.7 1.9 1

• 1.8 2.6 ~ 1 i K 109 Define saturated vapor K 110 Define vapor pressure 1.7 1.9 1 K 111 Define moisture content 1.8 2.3 1 K 112- Define quality 2.0 2.6 e K 113 Define superheated vapor 1.5 2.4 1 K 114 Define supersaturated vapor 1.5 1.8 1 K 115 Define subcooled and compressed liquids 2.0 2.4 1

-l K 116 Define subcooling 2.0 2.8 1 K 117 Define specific heat 1.8 2.1 1 K 118 Identify the following terms on a T-s diagra.n: --Critical point 1.5 ~1 .7 1~

K 119 Identify the fo' lowing terms on a T-s diagram: --Saturated liquid line 1.5 2.2 1 I

K 120 Identify the following terms on a T-s diagram: --Saturated vapor line 1.5 2.3 1-K 121 Identify the following terms on a T-s diagram: --Solid, liquid, gas, vapor, and 1.5 2.2 1 fluid regions K 122 Explain the usefulness of steam tables to the Control Room Operator 1.8 3.2 1 K 123 Use saturated and superheated steam tables 1.4 3.1 1 3

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THERMODYNAMIC PRCCESSES (293004)

NUM KNOWLEDGE APP LSRO SRO NOTE K 101 Explain the relationship between real and ideal processes 1.1 1.7 1 f

K 102 Explain the shape of the T-s diagram process line for a typical boiler 1.1 1.9 1 1.5 2.2 1 K 103 Nozzles - Describe the functions of nozzles in flow restrictors K 104 Nozzles - Describe the functions of nozzles in air ejectors 1.1 2.6 1

• 2.6 2.7 K 105 Nozzles - Describe the principles of operation of a jet pump K 106 Turbines Explain the function of nozzles, fixed blading, and moving blading in the 1.6 2.1 1 turbine K 107 Turbines Explain the reason turbines are multistages 1.5 2.2 1 K 108 Turbines - Define turbine efficiency 1.5 2.1 1-K 109 Turbines - Explain the dif ference between actual turbine performance and ideal 1.5 1.8 1 thermal efficiency K 110 Pumps Define pmp ef ficiency 1.8 1.9 1-K 111 Pmps Explain the dif ference between ideal and real pmping processes 1.6 1.8 1 K 112 Condensers - Discuss subcooling 1.6 3.1 1 K 113 Condensers Explain vacuum formation in condenser processes 1.5 2.6 1 K 114 Cordensers - Explain the condensing process 1.6 2.7 1 K 115 Throttling and the Throttling Process - Define throttling 1.5 2.3 1 K 116 Throttling and the Throttling Process a Explain the reduction of process pressure 1.3 2.3 1 from throttling l

THERMODYNAMIC CYCLES (293005)

NUM KNOWLEDGE APP LSRO- SRO NOTE K 101 Define thermodynamic cycle 1.2 1.8 i K 102 Define thermodynamic cycle ef ficiency in terms of net work produced and energy 1.1 1.7 1 applied K 103 Describe the moisture effects on turbine integrity and efficiency 1.1 2.7 1 K 104 Explain steam quality effects on nuclear turbine design 1.1 2.4 1 K 105 State the advantages of moisture separators / reheaters and feedwater heaters for a 1.2 2.8 1 typical steam cycle a

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FLUID STATICS (293006)

NtM KNOWLEDGE APP LSRO SRO NOTE .

K 101 Distinguish between fluids and other substances 1.7 1.8 1 K 102 Distinguish between static pressure, dynamic pressure, and total pressure 1.4 2.2 1 , ,

K 103 Define heed loss 1.4 2.5 1 K 104 Discuss operational considerations of viscosity as related to head loss 1.4 1.9 1 K 105 Explain operational implications of fluid hanrner 1.7 3.3 1 K 106 Pm ps and Pump Characteristics--State the purpose of a pm p 2.2 2.6 i 4

K 107 PLrnpa and Punp Characteristics -Discuss pump head 2.2 2.6 1 K 108 Pmps and Pm p Characteristics -Discuss relationship between punp speed, head, flow, 2,1 2.6 1 and power without using formulas or calculations K 109 Pumps and Pump Characteristics -Define cavitation 2.0 2.9 1 i K 110 Pumps and Pump Characteristics--Define net positive suction head (NPSH) 1.8 2.8 1 K 111 Pmps and Pmp Characteristics -Define punp shut-off head, pmp runout, and axial 2.0 2.5 1 thrust K 112 Pmps and Punp Characteristics--Explain the inportance of proper system venting for 1.8 2.9 1 ,

punp operations K 113 Pumps and Pmp Characteristics -Explain the results of putting centrifugal punps in 1.8 2.7 1 parallel or series conbinations K 114 Pumps and Pump Characteristics--Given the characteristic curve for a typical 1.7 2.3 1  ;

centrifugal pump, explain the reason for its shape K 115 Pumps and Pump Characteristics- Using a centrifugal pump characteristic curve and a 1.5 2.4 1 .i system characteristic curve, illustrate how the system operating point changes due to system changes K 116 Pumps and Punp Characteristics- Describe how a centrifugal pmp characteristic curve 1.5 2.3 1-will change with pump speed K 117 Pmps and Pump Characteristics--Explain how operating a centrifugal pung at shutoff 1.8 2.7 1 head may cause overheating of the pump and describe methods used to avoid overheating O K 118 Pumps and Punp Characteristics- Discuss the characteristic curve for a typical positive displacement pump and explain the reason for its shape K 119 Pmps and Pump Characteristics--Describe the problems that will occur in emergency 1.2 2.1 2.1 2.9 1

1 core cooling systems if the pumps are operated at lower than design flow for extended periods of time K 120 Define or explain mass flow rate 1.5 2.4 1

• K 121 Define or explain two phase flow 1.5 2.6 1 >

2.3 I K 122 Define or explain pressure spike 1.4 1 K 123 Define or explain gas binding 1.4 2.3 1 K 124 Define or explain recirculation ratio 1.4 2.3 1 K 125 Define or explain pipe whip 1.1 2.2 1 K 126 Explain why flow measurements must be corrected for density changes 1.1 2.4 i K 127 Explain the relationship between pressure head and velocity head in a fluid system 1.5 2.0 1 K 1* > Discuss the vetocity profites for laminar fIow and tubutent flow 1.5 1.8 1 K 129 Describe the methods of controtting system flow rates 2.0 2.7 1 r

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HEAT TRANSFER AND HEAT EXCHA%GES (293007)

NUM KNOWLEDGE APP LSR0 SRO NOTE K 101 Heat Transfer Describe three mechanisms of heat transfer

• 2.8 3.2 s K 102 Heat Transfer Describe thermal conductivity 2.2 2.6 1 K 103 Heat Transfer - Explain the manner in which fluid films affects heat transfer. 2.2 2.8 - 1 K 104 Heat Exchangers Discuss parallel-flow heat exchangers 2.1 2.2 1 K 105 Heat Exchangers Discuss counter-flow heat exchangers 2.1 2.2 -1 K 106 Heat Exchangers - Discuss the factors which affect heat transfer rate in a heat 2.1 2.8 1 ,

exchanger K 107 Heat Exchangers - Describe how the presence of gases or steam can affect heat 2.1 2.9 1 transfer and fluid flow in heat exchangers K 108 Condenser Applications of Heat Transfer - List functions of the main condenser in a 1.8 3.1 1 power plant K 109 Condenser Applications of Heat Transfer - Discuss operational l @lications of 1.5 2.7 1 condensate depression K 110 Core Thermal Power - Define core thermal power

• 2.5 . 2.9 K 111 Core Thermal Power - Explain methods of calculating core thermal power 2.2 3.1 .1 K 112 Core Thermal Power - Define percent reactor power

• 2.7 2.7 K 113 Core Thermal Power - Calculate core thermal power using a sl @lified heat balance 1.7 2.6 l' i

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1 THERMAL HYDRAULICS (293008) j NUM' KNOWLEDGE APP LSRO SRO NOTE

~ K 101 Boiling Heat Transfer - Distinguish between boiling processes and other heat transfer 2.1 2.8 1 mechanisms K 102 Boiling Heat Transfer - Describe surface or cavity nucleation 2.1 2.3 1 K 103 Bolling Heat 1ransfer - List factors affecting bubble formation in a cavity 2.0 2.1 1 K 104 Boiling Heat Transfer - Describe means by which boiling improves convection heat 2.0 2.7 1 transfer K 105 Bolling Heat Transfer Describe microconvection 2.0 1.5 i K 106 Pool Bolling Curve (T vs. Q/A) - Define a natural convection heat transfer 1.7 2.6 1 K 107 Pool Boiling Curve (T vs. Q/A) - Define nucleate boiling, subcooled nucleate boiling, 1.8 '3.0 1 and bulk boiling K 108 Pool Bolling curve (T vs. Q/A) - Describe DNB (departure f rom nucleate boiling) 1.8 3.1 1 K 109 Pool Boiling Curve (T vs. Q/A) - Describe OTB (onset of transition boiling) 1.8 3.2 1 K 110 Pool Boiling curve (T vs. Q/A) - Describe CHF (critical heat flux) 1.8 3.0 1 K 111 Pool Boiling Curve (T vs. Q/A) - Describe transition (partial film) boiling 1.8 2.8 1 K 112 Pool Boiling Curve (T vs. Q/A) - Describe stable film boiling 1.8 2.8 1 K 113 Pool Boiling Curve (i vs. Q/A) - Describe burnout and burnout heat flux 1.7 2.3 1 K 114 Two Phase Flow - Classify slug flow region along a fuel channel, experiencing two 2.0 2.1 1 phase flow K 115 Two Phase Flow - Describe annular flow region along a hypothetical fuel channel, 2.0 2.3 1 ,

experiencing two phase flow i K 116 Two Phase Flow - Describe dryout region or mist flow region along a hypothetical fuel 2.0 2.3 1 channel, experiencing two phase flow K 117 Two Phase Flow Describe OTB point along a hypothetical fuel channel, experiencing 2.0 2.8 1 two phase flow K 118 Two Phase Flow - Describe effects of flowrate and phase change on the heat transfer 1.8 2.4 1 coefficient g K 119 Core Inlet Subcooling - Define core intet subcooling 1.7 2.8 1 K 120 Core Inlet Subcooling - Define carryunder 1.7 2.6 1 1

K 121 Voids and void Fraction - Define void fraction 1.8 3.0 1 l K 122 volds and void Fraction - Explain the term void as applied to core operations 1.8 3.0 1 K 123 voids and Void Fraction - Define qualitty 1.8 2.7 1 I 1

K 124 Voids and Void Fraction Draw the temperature profile f rom the centerline of a fuel 1.8 2.5 1 pellet to the centerline of the channel K 125 Recirculation System - Explain the reason for forced core recirculation

• 2.5 3.2 K 126 Recirculation System - Explain the jet ptsnp operating principle

• 3.1 3.1 K 127 Recirculation System Explain the necessity of determining core coolant flow

• 2.7 3.0 K 128 Recirculation System - Describe the factors affecting single- and two-phase flow 2.4 2.5 1 resistance i

)

K 129 Core Orificing - Describe the effects of increasing bundle power on bundle flow

• 2.5 3.0 resistance K 130 Core orificing - Conpare the flow resistance through high powered bundles to that of

• 2.7 2.7 low powered bundles K 131 Core Orificing - Explain the necessity of core orificing

• 2.8 3.0 K 132 Core orificing - Describe core bypass flow

• 2.8 2.6 K 133 Core Orificing - Explain the need for adequate core bypass flow. Natural Circulation

• 3.4 2.6 K 134 Natural Circulation

• Explain the causes of natural circulation in BWR's 3.4 3.1 K 135 Natural Circulation - Describe problems that thermal stratification can cause

• 3.4 3.3 K 136 Natural Circulation

• Describe means by which the operator can determine if natural

• 3.1 3.3 circulation flow exists K 137 Natural Circulation - Describe means by which the operator can enhance natural 3.1 3.4 7 circulation

(

K 138 Siretch the axial temperature and enthalpy profiles for a typical reactor coolant 1.7 2.1 1 channel and describe how they are affected by the following: --Onset of nucleate boiling

- . . ~. . .

1 I

f

'K 130 Sketch the axial- tenperature erd enthalpy profiles for a typical resctor coolant 1.7 1.9 1 channel and describe how they are affected by the following: - Axial core flux I K 140 Sketch the s .lat tenperature and enthalpy profiles for a typical reactor coolant 2.0 1.9 1 channel and describe how they are affected by the following: --Inlet temperature.

K 141 Sketch the axial temperature and enthalpy profiles for a typical reactor coolant 2.0 2.0 1 channel and describe how they are af fected by the following - Heat generation rate ,

K 142 Sketch the axial temperature and enthalpy profiles for a typical reactor coolant 2.0 1.9 1 channel and describe how they are affected by the following: -Flow rate in the channel K 143 Sketch the temperature profile in the axial and radial directions for a typical fuel 2.1 2.2 1

. rod and explain the reason for its shape e

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CORE THERMAL LIMITS (293009)

NUM KNOWLEDGE APP LSRO SRO NOTE K 101 Explain radial peaking factor (RPF) ' 2.0 2.5 1

+ K 102 Explain axial peaking factor (APF) 2.0 2.6 1 7

K 103 Expiain local peaking factor (LPF) 2.0 2.5 't K 104 Explain total peaking factor (TPF) 2.0 2.6 - 1 K 105 state the reason thermal limits are necessary 2.4 3.5 1 K 106 LHGR Define LNGR 1.7 '3.8 '1 K 107 LHGR

• Explain the basis of the limiting condition of LHGR 1.7 ' 3.6 1 K 108 LHGR - Describe the mode of fuel failure for LHGR 1.7 3.4 '1 '

K 109 LNGR - Define FLPD and MFLPD 1.7 3.7 1 K 110 MAPLHGR - Define APLHGR 1.5 3.7 1 K ill MAPLHGR - Explain the basis of the limiting condition for APLGHR 1.5 3.6 1 K 112 MAPLHGR - Describe the mode of fuel failure for APLHGR 1.5 3.5 1 K 113 MAPLHGR - Define MAPLHGR 1.5 3.6 1 K 114 MAPLHCR - Explain the mechanisms most limiting for each region of the MAPLHGR limit 1.5 2.7 1 curves K 115 MAPLHCR - Describe conditions under which radiative heat transfer becomes the 1.5 3.1 1 significant method of heat transfer within a fuel bundle K 116 MAPLHGR - Discuss how changes in the heat generation rate and thermal conductivity of 1.5 2.8 1 the fuel rod af fect fuel centerline tenperature K 117 MCPR - Define critical power 1.5 3.7 1 K 118 MCPR - Define critical power ratio 1.5 3.7 1 K 119 MCPR - Explain the basis of the limiting condition for CPR 1.5 3.6 1 K 120 MCPR - Describe the mode of fuel f ailure for CPR 1.5 3.6 1 T r 121 MCPR - Define MCPR 1.5 3.6 1 K 122 MCPR - Describe the effects of subcooling on critical power 1.5 3.3 1 K 123 MCPR - Describe the ef fects of mass flow on critical power 1.5 3.2 i K 124 MCPR - Describe the effects of pressure on critical power 1.5 3.2 1 K 125 MCPR - Describe the effects of local power distribution on critical power 1.5 3.2 1'

]

K 126 MCPR - Describe the effects of axial power distribution on critical power 1.5 3.1 1 K 127 MCPR - Explain the purpose of the flow blasing correlation f actor, (K ), as it 1.5 3.3 1 relates to MCPR Limits j K 128 MCPR - Define FLCPR 1.5 3.5 1 l

K 129 Thermal Time Constant - Define fuel thermat time constant 1.7 2.7 1 ~j K 130 Thermal Time Constant - Relate thermal time constant to transient operating condition 1.7 - 2.7' 1 K 131 Pe!!et Ctad Interaction - Describe pellet-clad interaction (PCI)

• 2.7 3.4 K 132 Pellet Clad Interaction - List the causes of PCI

• 2.7 3.3 K 133 Pellet Clad Interaction Describe the purpose of the pellet to clad gap * .

' 2.7 2.8 K 134 Pettet Clad Interaction - Identify the possible effects of fuel densification 2.7 2.6 4 K 135 Pellet Clad Interaction - Describe the ef fects of iodine and cachium on PCI - 2.7 2.6' . 4 K 136 PCIDMR - Explain the purpose for PC10MR (Plant Specific) 1.8 3.4 1 K 137 PC10MR - Identify how the PCIOMR rules minimize the adverse effects of PCI (Plant 1.8 3.3 1 Specific)

K 138 PCIOMR - State the items measured for each of the three core thermal limits .1.5 3.1 1 1

i K 139 2.0 3.2 1 for the core following thermal plant limits areoperating or accident most limiting: conditions,ionidentify Full power operat which of the three K 140 For the following plant operating or accident conditions, identify which of the three 1.7 3.3 ' 1 core thermal limits are most limiting: Loss of reactor coolant O- K 141 For the core following thermal plant limits areoperating or accident most limiting: conditions,flowidentify Increase in core which of the three 1.7 3.3 1 K 142 For the following plant operating or accident conditions, identify which of the three 1.7 3.3 1 core thermal limits are most limiting: Increase in reactor pressure

4 &

+

K 143 For the following plant operating or accident corditions, identify which of the three - 1.7 3.4 1 core thermal limits are most limiting Cold water addition  !

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BRITTLE FRACTU2E AND YESSEL THERMAL STRESSES (293010)

NUM KNOWLEDGE APP LSR0. SR0 NOTE K 101 State the brittle fracture mode of failure 2.0 2.8 1 O~ K 102 State the definition of Nil Ductitity Transition Tenperature 2.0 2.7 1 K 103. Define reference tenperature 2.0 2.5 1 K 104 State how the possibility of brittle f racture is minimized by operating timitations 2.0 3.2 1 K 105 State the ef fect of f ast neutron irradiation on reactor vesset metals 2.1 2.8 1 O

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SELECTION CRITERIA AND GENERAL FOOTNOTES

1. Drop because LSRO Rating < 2.5.

2. Drop because SRO < 2.5.

3. Drop because LSRO < 3.0 and specifically approved for deletion by NMD/NTD.

4. Selected by NMD/NTD as applicable towards Fuel Handling activities.

O  ;

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._____m .__

l Control Rod Drive trd Hydraulic System (201001) =

NUM KNOWLEDGE ' APP LSRO $20 NOTE A 100 Ability to predict and/or make changes in parameters associated with operating the CONTROL R00 DRIVE HYDRAULIC SYSTEM controts including

'O ' A 101 CRD drive water header pressure

• 3.5 2.9 A 102 CRD cooling water header pressure

• 3.3 2.9 A 103 CRD system flow

• 3.5 2.8 A 104 Head spray flow: BWR-3 2.0 2.7 1-A 105. SDV isolation valve position

• 3.1 3.4 A 106 HCU presswre/tevel

• 3.8 3.4 A 107 Reactor water level

• 4.1 3.2  !

A 108 Pump amps 2.6 2.2 2 A 109 CRD drive water flow

• 3.5 2.8 A 110 CRD cooling water flow

• 3.3 2.6 ,

A 200 Ability to a) predict the impacts of the following on the CONTOL ROD DRIVE HYDRAULIC SYSTEM, and b) based the consequences onabnormal of those those predictions condit lons or operationsuse procedures to correct, or mitigate A 201 Pumps trips

• 2.8 3.3

• '3.0 3.3 ' $

A 202 valve closures A 203 Power supply failures

• 3.0 3.1 A 204 Scram conditions

• 3.1 3.9 A 205 Discharge strainer (s) becoming plugged

• 2.8 2.9 A 206 Suction strainer (s) becoming plugged

• 2.8 2.9

• 3.1 A 207 Flow control valve failure ~ 2.8 A 208 Inadequate system flow

• 2.8 ' 2.8 A 209 Loss of applicable plant air systems

• 2.6 3.1 A 210 Low HCU accumulator pressure /high level

• 3.3 3.6

• 3,0 2.7_

A 211 valve openings A 212 High cooting water flow

• 3.1 2.9, A 213 Low cooling water flow

• 3.1 2.8 A 214 Low drive header pressure

.3.0 2.8 A 300 Ability to monitor automatic operations of the CONTROL ROD DRIVE HYDRAULIC SYSTEM including A 301 valve operation-

• 2.8 3.0 .

A 302 Pump start: Plant-Specific

• 2.6- 2.8 A 303 System pressure '*

2.6 2.7 A 304 System flow *

- 2.6 2.7 A 305 Reactor water level

• 3.0 2.8 A 306 Reactor power

• 3.1 2.8 A 307 HCU accumulator pressure / level

• 2.5 3.3 A 308 Drive water flow *-

2.5 2.9 j A 309 Cooting water fIow

• 2.5 - 2.8 -

A 310 Lights and alarms 2.1 2.9 1 A 311 SDV tevel 2.3 - 3.5 1:

-A 400 Ability to manually operate and/or monitor in the con' trol room A '401 CRD pumps 1.5 - 3.1 1 A 402 CRD pump discharge valve 1.5 2.6 1

.A 403 CRD system flow control valve 1.5 2.8 1 A 404 Drive water header pressure control valve 1.5 3.0 1 A 405 Cooling water header pressure control valve 1.5 - 2.8 1 1

-i

A 406 SDV isolation valve test switch 1.5 2.7 1 A 407 Stabilizing valve selector switch 1.5 2.1 1 K 100 Knowledge of the physical connections and/or cause effect relationships between CONTROL ROD ORIVE HYDRAULIC SYSTEM and the following K 101 Condensate system 2.1 3.1 1 K 102 Condensate s urage tanks 2.1 3.0 1 ,

i K 103 Recirculation ponps (seat purge): Plant-Specific 1.8 3.1 1 K 104 Head spray: BWR-3 1.3 2.7 1 ,

K 105 Feedwater (or reactor water cleanup) CRD return to vessel: Plant-Specific 2.1 2.7 1 K 106 Component cooling water systems: Plant-Specific 1.8 .2.8 1 K 107 Reactor protection system 4.1 3.4 K 108 Reactor manual control system 4.0 3.4 K 109 Plant air systems 3.5 3.2 K 110 Control rod drive mechanisms 3.8 2.8 K 111 Reactor water cleanup pumps: Plant-specific 2.0 2.8 .1 K 200 Knowledge of electrical power supplies to the following K 201 Pumps 1.8 3.1 ~ 1 ,

K 202 Scram valve solenoids 2.1 3.7 1 K 203 Backup SCRAM valve solenoids 2.1 3.6 1 K 204 Scram discharge volume vent and drain valve solenoids 2.1' 3.3 1 K 205 Alternate rod insertion valve solenoids: Plant-Specific 2.1 4.5 1 K 206 Motor operated valves 1.8 2.3 1 i K 207 Breaker control 1.8 2.1 1 K 300 Knowledge of the effect that a toss or malfunction of the CONTROL RCD DRIVE '

HYDRAULIC SYSTEM will have on the following Recirculation pumps: Plant Specific 2.1 3.1 1-p K 301 K 302 Reactor water levet

• 3.3 2.6 K 303 control rod drive mechanisms 3.6 3.2 l K 304 Head spray: BWR-3 1.1 2.7 1 K 305 Reactor water cleanup pumps: Plant-Specific 2.0 2.3 1 K 400 Knowledge of CONTROL RCD DRIVE MYDRAULIC SYSTEM design feature (s) and/or Interlocks which provide for the following

• K 401 Frotection against punp runout during SCRAM conditions (location of the CRD system

• 2.8 2.6 i flow element and a restricting orifice M the accumulator charging water line).  !

K 402 Stable system flow when moving ear trol rods (stabillring valves)

• 3.1 2.6 K 403 Control rod drive mechanism cooling water flow

• 3.3 2.7 K 404 Scraming control rods with inoperative SCRAM solenoid valves (back up SCRAM valves)

• 3.1 3.6 K 405 Control rod SCRAM 3.5 3.8  ;

K 406 1 solation of the SCRAM discharge volumes during SCRAM conditions

• 3.1 3.9

• 2.5 2.8 K 407 Testing SCRAM discharge volume isolation valves K 408 Controlling control rod drive header pressure 3,0 _3.0 -

• 2.3 2.8 4 K '409 Controtting control rod drive cooling header pressure K 410 Control of rod movement (HCU directional control valves)

• 3.5 3.0 K 411 Protection against fitting the SDV during non-SCRAM conditions

• 2.6 3.6  :

K 412 Controtting CRD system flow 2.1 2.9 1 K 413 Motor cooling 2.1 2.3 1 K 500 Knowledge of the operational applications of the following concepts as they apply to  ?

' CONTR01, RCD ORIVE HYORAULIC SYSTEM K 501 Purp operation 1.3 2.4 1 K 502 Flow indication 1.5 2.6 1 K 503 Pressure indication 1.5 2.7 - 1 1

-~ . .- ~.- ~ . . . .

K 504 . Indications of pump cavitation 1.5 - 2.4 1 Indications of punp runoutt - Plant-Specific 1.3 2.7 1 K 505 K 506 Differential pressure indication 1.3 2.6 1 1.3 2.4

[ K 507 Air operated control valves 1.3 2.6 1

1' K 508 Solenoid operated valves K $09 System venting 2.3 2.2 1 K 600 Knowledge of the ef fect that a loss or malfunction of the following will have on the .,

CONTROL ROD DRIVE HYDRAULIC SY$ FEM K 601 condensate system

• 2.6 2.8 K 602 Condensate storage tonks

• 2.8 3.1 K 603 Plant air systems

• 2.8 2.9 K 604 RPS 3.0 3.7 K 605 A.C. power

• 3.0 3.3 K 606 Component cooling water systems: Plant Specific 1.8 : 2.8 :1

• 2.6 3.7 SG 1 Knowledge of operator responsibilities during all modes of plant operation SG 2 Knowledge of system status criteria which require the notification of plant

• 2.5 ' 3.5 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 2.8 4.1 outside agencies SG 4 Knowledge of system purpose and/or function

• 4.0 3.7 SG 5 Knowledge of limiting conditions for operations and safety limits

• 3.6 3.9 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 4.0 3.5 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 3.6 ' 3.7 SG 8 Knowledge of the annunciator alarms and indications, and use of the response 2.1 3.3 ~1 instructions SG 9 Ability to locate and operate components, including tocal controls 2.1 - 3.4 -1 SG 10 Ability to explain and apply all system limits and precautions 2.1' 3.3 - 1 Ability to recognize indications for system operating parameters which are

• 3.1 4.2 SG 11 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.6 3.2- '.1 '

alarm response manual SG 13 Ability to perform specific system and integrated plant procedures dr. ring all modes 1B 3.3 1 , c' of operation SG 14 Ability to perform without reference to procedures those actions that require 2.0 3.4 1 irnmediate operation of system components or controls SG 15 Ability to recognize abnormal indications for system operating parameters which are

• 3.3 3.8 entry-level conditions for emergency and abnormal operating procedures P

Reactor Manual Control System (201002)

NUM KNOWLEDGE APP- LSRO SRO . NOTE A 100 Ability to predict and/or make changes'in p rameters associated with operating the REACTM MANUAL CONTROL SYSTEM controls including A 101 CRD drive water flow

• 2.8 2.8 ,

A 102 Control rod position

• 3.1 3.3 A 103 Rod movement sequence lights

• 3.0 2.9 A 104 Overall reactor power

• 3.1 3.5 A 105 Local reactor power 3.1 3.6 A 200 Ability to a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM, and b) based the consequences of those onabnormal those predictions condit lons or operationsuse procedures to correct, or mitigate A 201 Rod movement sequence timer malfunctions

• 2.5 2.8 A 202 Rod drif t alarm

• 2.8 3.3 A 203 Select block 2.6 2.8-

• 3.5 3.1 A 204 Control rod block A 300 Ability to monitor automatic cperations of the REACTOR MANUAL CONTROL SYSTEM including ,

2.5 -3.1 A 301 Control rod block actuation A 302 Rod movement sequence lights 2.0 2.7 1 A 303 Rod drift alarm 2.1 3.2 1 A 304 Rod movement sequence timer malf unction alarm: Plant-Spec i f ic 2.0 2.8 1 A 400 Ability to manually operate and/or monitor in the control room A 401 Rod movement control switch 2.3 3.4 1 A 402 Emergency in/ notch override switch 2.3 3.5 1 A 403 Rod drift test switch 2.3 2.8 1 Timer malfunction test switch: Plant-S pec i f ic 2.3 2.8 1 A.404 A 405 Rod select matrix

• 2.6 3.0 '

A 406 Rod select matrix power switch 2.6 2.8 K 100 Knowledge of the physical connections and/or cause-ef fect relationships between REACTOR MANUAL CONTROL SYSTEM and the following K 101 Control rod drive hydraulic system

• 3.5 3.2 ,

K 102 Control rod and drive mechanism 3.5 2.9 K 103 Control rod block interlocks / power operation refueling 4.1 3.6 K 104 Rod block monitor: Plant Specifte

• 2.5 . 3.6 K 105 Rod worth minimiter: Plant + Specific

• 3.0 3.5 i K 106 Rod sequence control system: Plant-Specific 2.0 - 3.3 1 K 107 Process computer: Plant-Specific 2.3 2.9 1 K 108 Refueling interlocks: Plant-Specific

• 4.3 3.6 K 200 Knowledge of electrical power supplies to the following ,

1.5 2.3 _1 K 201- Select matrix K 202 CRD HCU directional control valves 1.6 2.3 1 i

K 300 Knowledge of the ef f ect that 'a toss or malf unction of the REACTOR MANUAL CONTROL 'i SYSTEM will have on the following K 301 Ability to move control rods 4.1 3.4

• K 302 Rod block monitor: Plant-Specific

• 3.0- 3.2 K 303 Ability to process rod block signats

• 3.6 - 3.0 -

K 400 Knowledge of REACTOR MANUAL CONTROL SYSTEM design feature (s) and/or interlocks which 2

-- provide for the following K 401 Detection of sequence timer malfunction 1.6 2.7 1 K.402- Control rod blocks

• 4.0--3.5

+ , +-- ,-----..w,. -s e- . v- , m + c w- -

, -. .- . ~ _

l

• ' 3.1 3.6:

K .403 Detection of drif ting contro! rods.

• ' 3.0 3.3 -

K 404 " Single notch" rod withdrawal and insertion

• 3.0 3.3  !

K 405 " Notch override" rod Withdrawal -

• 3.0 3.5

.K 406 " Emergency In" rod insertion

• 2.8 2.5 K 407 Timing of rod insert and withdrawal cycles (rod movement sequence tirer) - ,

• 3.0 3.2 K 408 " continuous In" rod insertion l K 500 Knowledge of the o erational applications of the following concepts as they apply to REACTOR MANUAL CON ROL SYSTEM K 600 Knowledge of the effect that a loss or malfunction of the following will have on the .j REACTOR MANUAL CONTROL SYSTEM 2.1 2.6 1 f

K 601 Select matrix power-1.3 3.8 1 SG 1 Knowledge of operator responsibilities during all modes of plant operation 2.3 3.6 1 l SG 2 Knowledge of system status criteria which require the notification of plant personnel 2.3 4.1- :1.

SG 3 Knowledge of which events related to system operation / status should be reported to outside agencies

• 3.0 3.6 SG 4 Knowledge of system purpose and/or function

• 2.6 4.0 SG 5 Knowledge of limiting conditions for operations and safety limits '

• 2.8 3.7 SG 6 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits '

SG 7 Knowledge of purpose and function of major system components and controls

• 3.1' 3.7 1.3 3.4 1 ,

SG B Knowledge of the annunciator alarms and indications, and use of the response instructions

• 1.5 3.1- 1 SG 9 Ability to locate and operate c$nponents, including local controls 2.1 3.9 1 SG 10 Ability to explain and apply all system limits and precautions

• 2.6 4.0 ,

SG 11 Ability to recognize indications for system operating parameters'which are l entry-level conditions for technical specifications ,

1.5 3;2 1.

SG 12 ' Ability to verify system alarm setpoints and operate controls identified in the

. alarm response manual . t 1.1 3.2 - 1-SG 13 Ability to perform specific system and integrated plant procedures during all modes of operation 1.1 3.4 1 SG 14 Ability to perform without reference to procedures those actions that require immediate operation of system components or controls ,

2.5 3.9 SG 15 Ability to recognize abnormal indications for system operating parameters which are '*

entry level conditions for emergency and abnormat operating procedures Y

t i

h

'l 8

a a

'I

.I

Control Rod and Drive Machanism (201003)

APP LSRO SRO ~ NOTE

.NUM KNOWLEDGE A 100 Abilit[R00ANDDRIVEMECHANISMcontrolsincludingto predict and/or make changes in parameters associa CONTR0

• 4.0 3.8 A 101 Reactor power

• 2.8 2.8 A 102 CR0 drive pressure

• 2.8 2.9 A 103 CRD drive water flow A 200 Ability to a) predict the impacts of the following on the CONTROL R00 AND DRIVE MECHANISM, and b) based on those predictions, use procedures to correct, or mitigate i the consequences of those abnormat conditions or operations A 201 Stuck rod

• 4.0 ~ 3.6 ,

A 202 Uncoupled rod

• 4.1 3.8 A 203 Drifting rod

• 3.5 3.7 A 204 Single control rod SCRAM 3.1 3.6

• 4 '.1 4.1 A 205 Reactor Scram ,

A 206 Loss of CRD cooling water flow

• 3.5 3.1 3.5 3.2 A 207 Loss of CRD drive water flow A 208 Low HCU accumulator pressure /high level

• 3.5 3.7 ,

A 209 Low reactor pressure

• 3.5 . 3.4 A 210 Excessive SCRAM time for a given drive mechanism 3.5 3.4 A 300 Ability to monitor automatic opSrations of the CONTROL RCD AND DRIVE MECHANISM including A 301 Control rod position 3.6 3.6 A 400 Ability to manually operate and/or monitor in the control room CRD rnechanism temperature 1.e 2.6 1 A 401 A 402 CRD mechanism position: Plant Specific

• 2.6 3.5 K 100 Knowledge of the physical connections and/or cause-effect relationships between CON 1ROL ROD AND DRIVE MECHANISM and the following Control rod drive hydraulic system

• 4.0 3.3 K 101

• 4.0 3.0 K 102 Reactor water

• 3.S 3.1 K 103 RPIS K 104 Reactor vesset

• 3.B . 2.9 K 105 CRD mechanism temperature monitor 2.1 2.6 1 K 200 Knowledge of electrical power supplies to the following K 300 Knowledge of the effect that a loss or malfunction of the CONTROL R00 AND DRIVE MECHANISM will have on the following ,

K 301 Reactor power

• 4.3 3.4 K 302 Flux shaping 2.1 3.1 1 Shutdown margin

• 4.1 3.8 ' ,

K.303 K 400 K.nowledge of CONTROL RCD AND DRIVE MECHANISM design feature (s) and/or interlocks +

which provide for the following K 401 Limiting control rod speed in the event of a rod drop

• 3.8 3.0 K 402 Detection of an uncoupled rod

• 4.5' 3.9 K 403 Stowing the drive mechanism near the end of its travel fotlowing a SCRAM: 3.5 2.1 ' 2 Plant Specific K 404 The use of either accumulator or reactor water to SCRAM the control rod

• 3.6 3.7

• 4.1 3.3 K 405 Rod position indication ,

K 406 Uncoupling the control rod from the drive mechanism

• 4.3 2.6 .

K 407 Maintaining the control rod at a given location

• ' 4.0 3.2 K 403 Monitoring CRD mechanism temperature 2.1 2.7 - 1 K 500 Knowledge of the operational applications of the following concepts as they apply to CONTROL R00 AND DRIVE MECHANSIM

U K 501 Hydraulics.

• 3.5 - 2.7 K 502 Flux shaping 1.8 3.3- '1 K 503 Reactor power controt

• 4.0 3.4 2.0 3.4 ' 1 K 504 Rod sequence patterns ,

1.6 3.1 -1 K 505 Reverse power effect K 506 How control rod worth varies with moderator temperature and voids 3.3 2.9 K 507 How control rod movements affect core reactivity

• 4.0 3.6 i K 508 How control rods af fect shutdown margin

• 4.0 3.5 K 600 Knowledge of the ef fect that a loss or malfunction of the following will have on the  :

CONTROL ROD AND DRIVE MECHANISM Control rod drive hydraulic system 3.6 3.3 ' i K 601 K 602 Reactor pressure 2.0 3.0 .i SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.6 3.7 1 SG 2 Knowledge of system status criteria which require the notification of plant

-2.8 3.6 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 3.3 3.9 ,

outside agencies SG 4 Knowledge of system purpose and/or function 3.6 3.6 SG 5 Knowledge of limiting conditions for operations and safety limits

• 3.5 3.9 SG 6 . Knowledge of bases in technical specifications for limiting conditions for

• 3.5 3.7 _'

operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 3.8 3.6 SG 8 Knowledge of the annunciator alarns and indications, and use of the response 1.6 3.4 1 instructions '

SG 9 Ability to locate and operate components,' including local controls 1.6 3.3 1 SG 10 Ability to explain and apply all system limits and precautions 2.6 3.2 SG 11 Abilit to recognize indications for system operating parameters whicn are

• 3.6 3.9

.- entry

• evel conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.8 3.3 1' alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.3 3.3 1 t

of operation SG 14 Ability to perform without reference to procedures those actions that require 1.5 3.3 ' 1:

imediate operation of system components or controls SG 15 Ability to recognize abnormal indications for-system operating paraneters which are .

• 3.0 3.9 entry-level conditions for emergency and abnormal operating procedures p

e 1

l i

. - - . . . . - . . . _. ~. ~

r Recirculation System (202001)-

NUM . KNOWLEDGE ' APP LSRO .SRO. ' NOTE A .100 Ability to pr' dict e and/or make changes in parameters associated with operating the

/" RECIRCULAt10N SYSTEM controls including 6

A 101 Recirct.letion pump flow: Plant-Specific 2.0 3.5 1 i 2.1 ' 3.4 - 1 A 102 Jet pu m flow A 103 Core flow 2.3 3.6 1 A 104 Reactor water level

• 2.8 3.3 -l A 105 Reactor power

• 2.8 3.9 A 106 Recirculation pump motor amps 1.3 2.6 1 A 107 Recirculation pump speed. 1.3 2.8 1 A 108 Recirculation FCV position: EWR 5,6 1.3 3.7 1 A 109 Recirculation p m p seal pressures 1.3 .'3.3 1 A 110 Recirculation seat purge flows 1.3 2.7 1 1.6 2.9 A 111 vessel bottom head drain temperature 1 A 112 Recirculation p m o differential pressure: Plant-Specific 1.3 2.6 1 A 113 Recirculation loop temperatures: Plant-Specific 1.5 3.2 1 A 114 Recirculation drive motor temperature: Plant-Specific 1.1 2.4 J1 A 115 Recirculation MG set temperatures: Plant-Specific 1.1. 2.4- 1 A 116 Recirculation MG drive motor amps: Plant-Specific 1.1 2.3 1 A 117 Recirculation MG set generator current, power, voltage: Plant-Specific 1.1 2.3 1-A 200 Ability to a) predict the impacts of the following on the RECIRCULATION SYSTEM, and b) based on those predictions use procedures to correct consequences of those abnormal conditions or operations . or mitigate the A 201 Jet p m p failure: Plant Specific 1.8 3.9 1 A 202 Recirculation system leak 2.5 3.9 A 203 Single recirculation pump trip 2.0 3.7 - 1 A 204 Nultiple recirculation p mp trip 2.0 3.8 - 1 A 205 Inadvertent recirculation flow increase 2.0 4.0 - 1 A 206 Inadvertent recirculation flow decrease 2.0 3.8- 1 ,

A 207 Recirculation pump speed mismatch: Plant-Specific 1.3 3.3 1 J A 208 Recirculation flow mismatch: Plant-Specific 1.3 3.4 1 A 209 Recirculation scoop tube lockup: Plant-Specific 1.1 3.4 1 A 210 Recirculation pmp seal failure 1.1 ' 3.9 - 1 ,

A 211 Low reactor water level 1. 5 - 3.9 1 A 212 Loss of reactor feedwater 1.5 3.8 1 A 213 Carryunder 1.3 2.8 1 A 214 High reactor pressure (ATWS circuitry initiation): Plant-Specific 1.3 4.2 1.

A 215 End of. cycle trip circuitry: Plant-Specific 1.3 3.9 1 A 216 Loss of seat purge flow (CRD) 1.3- 3.1 '1 A 217 Loss of seat cooling water 1.3 3.2 1 ,

A 218 Loss of motor cooling 1.1 3.1- 1-A 219 Loss of A.C. power: Plant-Specific 1.3 . 3.2.-- '1.

A- 220 Loss of D.C. power: Plant Specific. 1.3 2.9 1 A 221 Recirculation loop temerature out of spec: Plant-Specific 1.1- 3.7 1 ,

A 222 Loss of component cooling water . 1.1 - 3.2 . 1 A 223 - valve closures 1.1 3.2 1 <

A 224 valve opening 1.1 3.1 ~1 A 225 Recirculation flow control valve lockup: Plant Specific. 1.1 3.3 ' 1

. _ ~ _ . .- . . .-

A 226 Inconplete start sequence: . Plant Specific 1.1 - 3.1 1 i

A ~ 300 Ability to monitor automatic operations of the RECIRCULATION SYSTEM including A 301 valve operation 1.0 3.1' 1 A 302 Pump /MG set start sequence: Plant-speci fic 1.0 3.0 1 1.0 3.2 1 A 303 System flow A 304 Lights and alarms 1.0 3.1 1 A 305 Punp speed: Plant-Specific 1.0 2.9 1 A 306 Flow control valve position: BWR-5,6 1.0 3.6 1 A 307 Punp trips: Plant-Specific 1.0 3.3 1 A 308 Pwp downshift: BWR 5,6 1.0 3.3 1 A 309 MG set trip: Plant Specific 1.0 3.3 1 A 400 Ability to manually operate and/or monitor in the control room A 401 - Recirculation ptsnps 1.3 3.7 1 A 402 System velves 1.1 3.4 1 1.5 4,1 1 A .403 Reactor power .

A 404 System flow 1.1 3.7 1 A 405 Lights and alarms 1.1 3.3 ' -1 A 406 cil pm ps 1.1 2.7 1 A 407 vent fans: Plant-Specific 1.1 2.3 1 A 408 Motor-generator sets: Plant-Specific 1.1 3.1 1 .,

A 409 Reactor water level 1.6 3.7 1 A 410 Seal flow: Plant-Specific 1.1 2.8 1 A 411 Seal pressures: Plant specific 1.1 3.3 1 A 412 Core flow 1.1 ' 3.8 1 A 413 Core differential pressure 1.1 3.3 1

'O K 100 Knowledge of the physical connections and/or cause-ef f ect relationst ips between RECIRCULATION SYSTEM and the following K 101 Core flow 2.6 3.7 K 102 Reactor power 2.6 4.1 K 103 Reactor moderator temperature 2.6 3.3 K 104 Reactor / turbine prenure regulating system: Plant-Specific 1.6 3.3 , 1 K 105 Reactor pressure 1.6 3.4 1 K 106 Jet pumps

• 2.5 3.6 K 107 Component cooling water systems 1.6 3.2 i K 108 A.C. electrical 1.6 3.2 1 K 109 D.C, electrical 1.5 2.9 1 K 110 Control rod drive system: Plant-Specific 2.3 ' 2.8 i K 111 Drywell equipment drain suny . 1. 3 ' 2.8 1 K 112 Recirculation system motor-generator sets: Plant-Specific 1.5 3.6 -~ 1 K 113 Jet pump ring header and risers: Plant-Speelfic. 2.3 3.2 1 K 114 Rod block monitor: Plant-Specific 1.8- 3.2 1 K 11$ Nuclear boiler instrunentation (reactor water level / pressure) 2.3 3.2- 1 K 116 Low pressure coolant injection logic:. Plant-Specific 2.5 3.9 K 117 Vessel bottom head drain temperature 2.1 3.3 . -1 K 118 RHR shutdown cooling mode 2.8 . 3.3 K 119 Feedwater flow 2.0 3.2 1 K 120 Plant air systems: Plant-Speelfic 1.5 2.5 1 K 121 Reactor water cleanup system 2.0 2.6 1 K'122 Reactor water level

• 2.8 3.6

I K 123 Averegs power rangs monitor flow converters: Plant Specific 1.5 3.5 .1:

.K '124 -Isolation condenser Plant-Specific = 1.3 - 3.4 1  ;

Reactor water sanpling system 1.3 2.7 11 K .125 K 126 Recirculation flow control system: Plant-Specific 1.3 3.6 1 K 127 ATWS circuitry: Plant Specific 1.5 4.3. 1 1.3 4.1 '1 K 128 End-of-cycle recirculation pump trip circuitry: Plant Specific K 200 Knowledge of electrical power supplies to the following

. 1. 3 3.2 - 1 K 201 Recirculation pumps: Plant Specific K 202 MG sets: Plant-Specific 1.3 3.3 1 K 203 Recirculation system valves 1.3 2.8 1 K 204 Hydraulic power unit oil pumps Plant-Specific 1.3 ' 2.5 1 K 205 MG set oil p m ps: Plant-Specific 1.3 ' 2.3 '1 K 300 Knowledge of the ef fect that a loss or malfunction of the RECIRCULATION SYSTEM will have on the following

• 2.5 3.6 K 301 Core flow K 302 Load following capabilities: Plant-Specific 1.5' - 2.8 1' K 303 Reactor power 2.0 - 3.9 1-

'* ~2.5 3.7 K 304 Reactor water level

'1.6 3.3

~

'1 K 305 Recirculation system MG sets: Plant-Specific.

K 306 Low pressure coolant injection logic: Plant-Specific

• 3,0 3.9 K 307 Vessel bottom head drain temperature 2.1 2.9 1 K 308 Shutdown cooling system 2.6 - 2.9 '

K 309 Reactor water cleanup system 2.3 2.5 1 r K 310 Average power range monitor flow converters 1.3 3.4 .1 >

1.3 2.3 - 1 K 311 Component cooling wrter systems Isolation condenser: Plant-Specific 1. 3 . 3.0 1 K 312 313 Reactor water sampling system 1.3 2.5 1

-K K 314 Primary containment integrity: Plant Specific 1.5 3.5 1:

K 400 Knowledge of RECIRCULATION SYSTEM design feature (s) and/or interlocks which provide for the following 2/3 core covert >ge: Plant-specific 3.1 3.9 K 401 K 402 Adequate recirculation pump kPSH 1.8 . 3.2 1 K 403 Recirculatic,a pump motor cooling 1.5 2.8 1 1.5 3.1 1 K 404 controlled seat flow Seal. cooling 1.5 2.9 1.

K 405 '

K 406 Automatic voltage / frequency regulation: Plant-Specific 1.3 ' 2.7 1 K 407 Motor generator set trips: Plant Specific 1 ~. 3 2.9 1-K 408 Oil p mp automatic starts: Plant-Specific 1.3 2.9 1 K ~ 409 Punp mininum flow limit: Plant Specific 1.5. 2.9 1 K 410 Pump start permissives: Plant-Specific 1.3 3.4 1 Limitation of recirculation p mps flow mismatch: Plant Specific 1.1- 3.5 1-K 411 K 412 . Minimization of reactor vessel bettom head tenperature gradients: Plant-Specific. 2.0 3.5 - .1'  :

K 413 End of cycle recirculation pump trip: Plant-Speelfic 1.5 4.0 1 K 414 ATWS: Plant-Specific 1.5 4.1 ;1 K 415 Slow speed pump start: Plant-Specific 1.3 3.4 1 K 416 Recirculation p m p downshift / runback: PlantaSpecific 1.3 3.6 1 K 417 Fast speed putp start: Plant-Specific 1.3 3.5 1  !

K 418' Automatic MG set start sequencing: Plant-specific 1.3 3.0 1 K $00 Knowledge of the operational applications of the following concepts as they apply to RECIRCULATION SYSTEM a

. - - ~ . ~ . ~ . ~ - . . - . _ . _

Indications of gw p cavitation . 1.3 2.8 1 K ~501

• 2.8 3.2  ?

K ' 502 Jet pm p operation: BW2-3,4,5,6 K $03 Pwp/ motor cooling: Plant Specific 1.3 ' 2.7 1.

K 504 System venting 1.3 2.6 1 K 505 End of cycle recirculation ptsp trip: Plant-Specific 1.3 3.6 1 K 506 ATWS RP1: Plant-Specific 1.3 3.7 1 K 507 Natural circulation: Plant-Specific

• 2.8 3.4 K $08 E/P converters: Plant Specific 1.3 2.1 1 4 1.3 2.6 1

'K 509 Hydraulically operated valves: Plant Specific K 510 Motor generator set operation: Plant-Specific 1.5 2.8 1 K 600 Knowledge of the effect that a loss or malfunction of the following will have on the RECIRCULATION SYSTEM K 601 Jet pumps: Plant-Specif ic 2.1- 3.7 1 K 602 corponent cooling water systems 1.3 3.2 1 1.3- 3.0 . 1- [

K 603 A.C. power: Plant-Specific 1.3 2.8 1:

K 604 D.C. power: Plant-Specific 3 K 605 Control rod drive system: Plant-Specific 1.6 2.8 1 K 606 Recirculation system motor generator sets: Plant-Specific 1.5.'3.1 1 1.8 3.3 1-K 607 Feedwater flow K 608 Reactor water cleanup system 1.8 2.3' 1 K 609 Reactor water level 2.5 3.4 SG 1 Knowledge of operator responsibilities during att modes of plant operettor; 1.6 ' 3.9 1 J

SG 2 Knowledge of system status criteria which require the notification of plant 1.8 3.8 1 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 1.8 4.3 1 outside agencies ,

SC 4 Knowledge of system ourpose and/or function 2.6 3.8 SG 5 Knowledge of limiting conditions for operations and safety limits

• 2.0 '4.2 4 SG 6 Knowledge of bases in technical specifications for limiting conditions for 2.1 4.1 .4 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 2.1 3.8 4 ,

SG 8 Knowledge of the annunciator alarms and indications, and use of the response 1.1 3.4 1  !

i instructions SC 9 Ability to locate and operate components, including local controls 1.1 - 3.5 1 SG 10 Ability to explain and apply all system limits and precautions 1.1 3.7 1 SG 11 Ability to recognize indications for system operating parameters which are 1.6 4.2 1 entry-level conditions for technical specifications SC 12 Ability to verify system alarm setpoints and operate controts identified in the 1.1 3.3 1~ .

alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.1 3.4 ' 1 ~f of operation ,

SG 14 Ability to perform without reference to procedures those actions that require 1.5 3.7 1 imediate operation of system conponents or controls SG 15 Ability to recognize abnormal indications for system operating parameters which are 1.5 4.2 1 i entry-level conditions for emergency and abnormal operating procedures j p a- y <w-.s ..wp .

s.4m .,-t r- w T'1-- w

Red Control End Information System (201005) .l APP LSRO S20 NOTE I WUM KNOWLEDGE  !

-- A 100 Ability to predict and/or make changes in parameters associated with operating the R00 CONTROL AND INFORMATION SYSTEM controls including I

A 200 Ability to a) predict the imacts of the following on the R00 CONTROL AND i INFORMATION SYSTEM, and b) based or' those predict:ons, use procedures to correct, or '

mitigate the consequences of those abnormal conditions or operations

)

A 201 High flux (SRM, IRM, APRM): BWR-6 1.3 3.5 1 ,

A 202 Position indication probe failure: BWR-6 1.0 3.2 1 A 203 Insert block: BWR-6 1.0 3.2 1 A 204 Withdrew block: BWR-6 1.0 3.2 1 ,

A 205 Insert required: BWR-6 1.0 3.2 1  ;

A 206 Insert inhibit: BWR-6 1.0 3.2 1 A 207 Withdraw inhibit: BWR-6 1.0 3.2 1 A 208 LPRM upscale /down scale: BWR-6 1.3 3.2 1 A 209 Test display blinking: BWR-6 1.0 3.0 ~1 A 210 Data fault: BWR-6 1.0' 3.0 1 A 211 Accumulator fault: BWR-6 1.0 3.5- 1 A 212 Rod uncoupled: BWR-6 1.3 3.8 1 ,

A 213 Rod drift: BWR 6 1.3 3.8 ' 1 A 300 Ability to monitor automatic operations of the ROD CONTROL AND INFORMATION SYSTEM including.

A 301 Cperator control module lights: BWR 6 1.0 3.5 1 f

A 302 Rod display module lights: BWR 6 1.0 3.5 1 A 303 Verification of proper functioning / operability: BWR-6 1.0 3.3 1 [

A 304 Annunciator and alarm signals: BWR-6 1.0 - 3.3 1.

A 400 Ability to manually operate and/or monitor in the control room i A 401 Operator control module (lights and push buttons): BWR-6 1.0 3.7 1 .,

A 401 First stage shelt pressure / turbine load: BWR-6 1.1 3.3 1-A 402 Rod display module (lights and push buttons): BWR 6 1.0 3.7 i A 403 Back panel indi: sting lights: BWR 6 1.0 3.3 1 K 100 Knowledge of the pnysical connections and/or cause-ef fect relationships between ROO CONTROL AND INFORMATION SYSTEM and the following K 101 Neutron monitoring system: BWR-6 1.0 3.3 1 K 102 Reactor / turbine pressure control system: BWR-6 1.0 - 3.5 1 .i K 103 control rod drive system: BWR-6 1.0 3.7 1 K 104 Rod position information system: BWR-6 1.0 3.7 1 K 105 Rod action control system: BWR-6 1.0 3.5 1 l

K 106 Rod gang drive system: BWR-6 1.0 3.3 1 K 107 Rod interface system: BWR 6 1.0. 3.3 1 K 200 Knowledge of electrical power supplies to the following .i K 201 A.C. electrical power: BWR-6 1.0 2.6 1 ,

K 300 Knowledge of the effect that a loss or malfunction of the ROD CONTROL /20 j INFORMATION SYSTEM will have on the following K 301 Control rod drive system: BWR-6 1.1 3.7 1 K 302 Reactor startup: BWR 6 1.0 '3.5 1  !

1.1 3.2 1' K 303 Reactor shutdown: BWR-6 1.0 3.3 ' 1 i K 304 Flux shaping: BWR 6 K 400 Knowledge of R00 CONTROL AND INFORMATION SYSTEM design feature (s) and/or interlocks-

.O which provide for the following K 401 Limiting the effects of a control Rod accident: BWR-6 1.1 3.2 1

I 1.0 3.3 1 I K' 402 Benk position withdrawal sequence (SPWS): BWR 6 - I K 403 Rod withdrawal block signals: BWR-6 1.6 3.5 1 K 404 Rod insertion block signals: BWR 6 1.6 3.5 1 1

K 405 Rod withdrawal limiter: BWR-6 1.0 3.5' 1 1 K 406 Rod pattern controller rod blocks: BWR 6 - 1.0 3.5 ~ 1 l K 500 Knowledge of the operational applications of the following concepts as they apply to -

ROD CONTROL AND INFORMATION SYSTEM ]

4 K 501 Rod pattern and program developments BWR 6 1.0 3.2 1- ,

K 502 Rod pattern controller (RPC): BWR 6 1.0 3.3- 1 K 503 Rod groups: BWR-6 1.0 2.7 1 K 504 Rod sequences: BWR-6 1.0 3.0- 1 K 505 Rod density: BWR-6 1.0 3.0 1 K 506 Target rod pattern: BWR-6 1.0 2.8 1 K 507 Low power alarm point: BWR 6 1.0 3.5 1 K 508 Transition zone: BWR 6 1.0 3.5 1 K 509 High power setpoint: BWR-6 1.0 3,5 - 1 K 510 Rod withdrawal limiter: BWR-6 1.0 3.3 1 ,

K $11 Control rod motion: BWR-6 1.0 3.3 1 ,

K 512 Comand word generation and sequencing (operator follow, scan and test): BWR 6 1.0 2.2 1 K 513 Position indication probes: BWR-6 1.0 2.7 1 K 600 Knowledge of the effect that a loss or malfunction of the followtng will have on the ROD CONTROL AND INFORMATION SYSTEM First stage shell pressure or opening of a bypass valve (s): BWR-6 1,0 3.2 1-K 601 K 602 Rod position signal: BWR-6 1.0 3.3 1 ,

K 603 A.C. electrical power: BWR-6 1.0 2.8 1 K 604 1RM channel: BWR-6 1.0 3.2 1 K 605 SRM channel: BWR 6 1.0 3.2 1 K 606 APRM channel: BWR-6 1.0 -. 3.0 - 1-SG ' .1 Knowledge of operator responsibilities during all modes of plant operation 1.0 3.8 . 1 SG 2 Knowledge of system status criteria which require the notification of plant 1.0 4.2 -1 . .

personnel l SG 3 Knowledge of which events related to system operation / status should be reported t3 1.0 ! 4.5 1 outside agencies SG 4 Knowledge of system purpose and/or function 1.0 3.5 ' 1-SG 5 Knowledge of limiting conditions for operations and safety limits 1.0 . 4.0 1 .

SG 6 Knowledge of bases in technical specifications for limiting conditions for 1.0 4.2 1 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls 1.0 3.3 1 SG B Knowledge of the annunciator alarms and indications, and use of the response 1.0- 3.5 1 ,

instructions i SG 9 Ability to. locate and operate components, including local controls 1.0 3.2 1 SG 10 Ability to explain and apply all system limits and precautions 1.0 3.5 - 1 SG 11 Ability to recognize indications for system ope uting parameters which are 1.0 4.0 1- ,

entry-level conditions for technical specificatuns SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.0 3.2 ~1 j

alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.0 3.5 1 of operation l SG 14 Ability to perform without reference to procedures those actions that require 1.0 ' 3.8 1 l immediate operation of system components or controls SG 15 Ability to recognize abnormal indications for system operating parameters which are 1.0 3.8 '1 entry-level conditions for emergency and abnormal operating procedures P e q, u - - - - y - '

't

- . . ~ _ . . . .

Low Pressure Core Spray System (209001) -

NUM KNOWLEDGE APP LSRO SRO NOTE A 100 Ability to predict and/or snake changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including

-O A 101 Core spray flow 2.3 2.3 3.6 3.4-1 1

A 102 Core spray pressure A 103 Reactor water level

• 3.0 3.9 A 104 Reactor pressure 2.3 3.7 1 A 105 Yorus/ suppression pool water level 2.3 3.6 - 1-A 106 Motor amps 1.5 2.4 1 A 107 Emergency generator toading 2.1 3.1 1 A 108 System lineup 2.3 3.2 1 l

A 200 Ability to a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY use procedures to correct, or mitigate SYSTEM, and b) based the consequences on those of those predictions abnormal condit lons or operations .

A 201 Punp trips 1.5 3.4 1 A 202 valve closures 1.5 3.2 1 A 203 A.C. failures 1.5 3.6 1 A 204 D.C. failures 1.5 3.0 -1 A 205 Core spray line break 1.5 3.6 1 A 206 Inadequate system flow 1.5 3.2 1 A 207 Loss of room cooling 1.5 2.8 1 A 208 valve openings 1.5 3.1 1 A 209 Low suppression pool level 1.5 3.3 1 A 210 High suppression pool temperature 1.5 3.4 1 A 211 Loss of fire protection: BWR-1 1.5 3.3 1 A 300 Ability to monitor automatic operations of the LOW PRESSURE CORE SPRAY SYSTEM including A 301 valve operation 1.3 3.6 1 A 302 Pump start 1.3 3.7 1 A 303 System pressure 1.3 3.5 1 A 304 -System flow 1.3 3.6 1 A 305 Reactor water level 1.5 3.9 1

]

A 306 Lights and alacms 1.1 3.5 -1 A 400 Ability to manually operate and/cr monitor in the control room A 401 Core spray pump 1.1 3.6 1 A 402 Suction valves 1.1 3.4 1 A 403 Injection valves 1.1 3.6 1 A 404 Minimal flow valves 1.1 2.9 1 A 405 Manual initiati>n controls 1.1 3.6 1 A 406 Testable check valves 1.1 2.4 1 A 407 Fill pump 1,1 2.8 1 A 408 Reactor water level 1.1 3.9 1 A 409 Suppression pool level 1.1 3.5 -1 A 410 Reactor pressure 1.1 3.8 - 1 A 411 System flow 1.1 3.6 - 1 A 412 System pressure 1.1 3.5 1  !

1.1 3.4 1

4 413 Lights and alarms

,O - A 414 Containment level: BWR-1 1.1 3.6 1 K 100 Knowledge of the physical connections and/or cause ef fect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the following

.- - . - . .- - - . - ~ ~ . .- - . ..- .-. . . . . ~ ~ ~ . .

K 101- Condensate storegs tanks Plant Specific .* 2.6 3.1 K ' 102 Torus / suppression pool

• 3.0 3.4 K 103 Keep fitt system

• 3.0' 3.0 3,0 2.4 2

[ K 104 condensate transfer system '

\ K 105 Automatic depressurization system 3.0 3.7 K 106 Plant air systems 2.6 2.1 2 K 107 0.C. electrical power

• 2.6 2.7 -

K 108 A.C. electrical power

• 2.6 3.3 K 109 Nuclear bolter instrtsnentation

• 2.8 3.4 K 110 Emergency generator

• 2.8 3.8 4 K 111 Orywell cooters: Plant-Speelfic 2.3 2.6 1

• 2.8 . 3.1 i K 112 ECCS room coolers K 113 Leak detection 2.3 3.0 1 K 114 Reactor vesset 2.8 3.8 K 200 Knowledge of electrical power supplies to the following K 201 Pump power 1.8 3.1 1 K 202 valve power 1.6 2.7 1 K .203 Initiation logic 2.0 3.1 1 K 300 Knowledge of the ef f tet that a loss or malfunction of the LOW PRESSURE CORE SPRAY F SYSTEM will have on the following K 301 Reactor water level

• 3.3 3.9 j K 302 ADS logic 1.5 3.9 1.

1.6 3.0 . 1-K 303 Emergency generators ,

K 304 Component cooling water systems 1.3 2.2 1 K 3C5 Orywell cooling: Plant Specific 1.3 2.7 '1 O'

K 400 Knowledge of LOW PRESSURE CORE SPR4Y SYSTEM design feature (s) and/or interlocks which provide for the following Prevention of overpressuritation of core spray piping 1.5 3.4 '1 K 401 ,

K 402 Prevents water hamer 1.8 3.2 ~1 K 4U3 Motor cooling 1.5 2.5 1 K 404 Line break detection 1.5 - 3.2 1 K. 405 Ptanp minimum flow 1.8 2.6 1 K 406 Adequate pump net positive suction head 1.5 2.9 1 K 407 Pump operability testing 1.3 3.0 1 K 408 Automatic system initiation 2.0 4.0 1 q

K 409 Load sequencing 1.8 3.5 1

[

K 410 Testability of all operable corr.ponents 1.3 2.1- 1 K 500 Knowledge of the operational applications of the following concepts as they apply to +

LOW PRESSURE CORE SPRAY SYSTEM l 4

K 501 Indications of ptanp cavitation 1.1 '2.7 1 l

K 502 Differentist pressure indication 1.0 2.6- 1 'i K 503 Testable check valve operation 1.0 2.4 1 K 504 Heat removal (transfer) mechanisms 1.0- 2.9 1 i

K 505 System venting 1,0 2.5 - 1 K 506 Recirculation operation: Plant-Specific (BWR-1) 1.0 4.0 1 K 600 Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSTEM 2.1 3.4 ~1 K 601 A.C. power K 602 Emergency generatoss 2.1 3.9 1:

K 603 Torus / suppression pool water level 2.1 3.4 1 f

. . . , _ , ,;, e.,', -  % . .m, , ., r ,- , , , , , , - _ . - . +

D.C. power 2.1 . 2.9 1 K. 604 2.1 2.9 1.

K 605- ECCS room cooler (s)

Pump motor cooler (s)

. 2.3 2.4 ~ 1 K'606 2.3 2.3 1

-K 607 PLCp seal Cooler (s)

• 2.8 3.0 L

K 608 Keep fitt system.

K 609 - Fire protection: BWR 1 2.1' 3.3 1 K 610 ECCS room integrety: Plant-specific 2.3 2.5 1 ,

2.1 3.7 1 ,

K 611 ADS Knowledge of operator responsibilities during all modes of plant operation 1.5 4.1 1 SG 1 SG 2 Knowledge of system status criteria which require the notification of plant 2.0 3.9 1 personnel ~

SG 3 Knowledge of which events related to system operation / status should be reported to 2.0 4.4 1 f

outside agencies ,

SG 4 Knowledge of system purpose and/or. function

• 2.5, 3.7  ;

SG 5 Knowledge of limiting conditions for operations and safety limits -

• 2.6 4.2 3 SG 6 Knowledge of bases in technical specifications for limiting conditions for 2.6 4.0 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controts

• 2.5 3.7 SG 8 Knowledge of the annunciator alarms and indications, and use of tne response ' 1.1 3.4 1 I" instructions SG 9 Ability to locate and operate components, including local controls 1.0 - 3.7 ,1 SG to Ability to explain and apply att system limits and precautions .1.0 3.6 1 SG 11 Ability to recognize indications for system operating parameters which are 2.0 4.2 1 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.1 3.4' 1' alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.1 3.7 L 1 of operation ,

1.3 3.5 1

(

SG 14 Ability to perform without reference to procedures those actiors that require imnediate operation of system components or controts SG 15 Ability to recognize abnormat indications for system operating parameters which are 1.3 4.2 1 entry levet conditions for emergency and abnormat operating procedures I

9 i

n l

O- .

'l i

{

RHR/LPCI: Injection Mode (Plant Specific) (203000)

APP LSRO SRO NOTE NUM KNOWLEDGE A' 100 Ability to predict and/or make changes in parameters associated with operating the RHR/LPCl: INJECTION MODE (PLANT SPECIFIC) controls including t

• 3.1 4.3 A 101 Reactor water level 2.1 4.0 1 A 102 . Reactor pressure 2.1 3.7 1 A 103 Sr. tem flow

• 2.1 3.6 -1 A 104 System pressure 2.3 3.7 1 A 105 Suppression pool level A 106 Condensate storage tank level: Plant-Specific 2.3 2.5 1 2.0 2.5 1 A 107 Motor amps: Plant-Specific 2.0 3.8 1 A 108 Emergency generator loading 2.3 2.9 1 A 109 Component cooling water systems A 200 Ability to a) predict the impacts of the following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC), and b) based on those predictions use procedures to correct, or mitigate the consequences of those abnormal conditio,ns or operations 1.6 3.4 1 A 201 Inadequate net positive suction head 1.6 3.5 1 A 202 Pump trips 1.6 3.3 1 A 203 valve closures 1.6 3.6 1 A 204 A.C. failures 1.6 3.2 1 A 205 D.C. failures A 206 Emergency generator falture 1.6 '3.9 1 1.6 3.1 1 A 207 Pump seat failure 1.6 3.0 1 A 208 Inadequate room cooling 1.6 3.4 1 A 2 09 Inadequate system flcN 1.6 3.5 1 A 210 Nuclear boiler instrument failures 1.6 3.6 1

\ A 211 Motor operated valve failures 1.6 2.7 1 A 212 Pump runout 1.6 3.3 1 A 213 Valve openings Initiating logic failure 1.6 3.9 1 A 214

.1.6 4.2 1 A 215 Loop selection logic failures Plant-Speci f ic 1.6 4.5 1 A 216 Loss of coolant accident 1.6 3.5 1 A 217 Keep fill system failure A 300 Ability to monitor automatic operations of the RNR/LPCI: INJECTION MODE (PLANT SPECIFIC) including 1.3 3.7 1 A 301 Valve operation 1.3 3.9 1 A 302 Pump start 1.3 3.6 1 A 303 Pump discharge pressure 1.3 3.7 1 A 304 System flow 1.3 4.4; 1 A 305 Reactor water level 1.3 3.6 1

)

A 306 Indicating lights and alarms 1.3 4.6 1 A 307 Loop selection: Plant Specific 1.3- 4.1 1 l A 308 System initiation sequence l

1.3 3.9 i  !

A 309 Emergency generator load sequencing A 400 Ability to manually operate and/or monitor in the control room 1.1 4.1 1 A 401 Pumps 1.1 4.1 1 A 402 System valves 1.1 3.4 1 g

A 403 Keep fill system

\ A 4D4 ' Heat exchanger cooling flow 1.1 3.6 1 1.1 4.1 1 A 405 Manual initiation controls 1

I l

l

A 406' System reset following automatic initiation: Plant-Specific -- 1.1 3.9 1 1.1 4.5 1.

A 407- Reactor water level A 408 Reactor pressure 1.1 4.3 ' 1 A 409 System flow 1.1 4.0 1 A 410 Putp/ system discharge pressure: Plant-Specific 1.1 3.6 1-A 411 Indicating lights and alarms .1.1 3.5 1 A 412 Condensate storage tank level Plant-Specific 1.1 2.6 1 A 413 Suppression pool level / temperature 1.1 3.9 1

.A 414 Testable check valves 1.1 2.7 1:

K 100 Knowledge of the physical connections and/or cause-effect relationships between RHR/LPCl: INJECTION MODE (PLANT SPECIFIC) and the following K 101 Condensate storage and transfer system: Plant-Specific

• 2.6 2.8 K 102 Suppression poot

• 3.0 3.9 K 103 Condensate transfer 2.8. 2.6 K 104 Keep fill system

• 2.8 3.4 K 105 Recirculation system: Bm-3,4

• 2.8 3.8 K 106 Automatic depressi:-ization

• 2.6 3.9 K 107 D.C. electrical power

• 2.6 3.3 K 108 A.C. electrical power

• 2.6 3.5 K 109 Emergency generc ors 2.8 3.8 K 110 ECCS room coolers 2.8 3.2 K 111 Nuclear boiler instrumentation 2.5 3.7 K 112 Plant air systems: Plant-specific

• 2.5 2.7 '

K 113 Drywell pressure 2.6 4.0

'K 114 Shutdown cooling system: Plant-Specific

• 3.3 3.7 K 115 Reactor building drain system: Plant-Specific

• 2.5 2.6 '

K 116 Component cooling water systems

• 2.6 3.2 K 117 Reactor pressure 2.0 4.0 1 K 118 Reactor vessel: Plant-specific 2.3 3.8 1 K 200 Knowledge of electrical power suoplies to the following K 201 Punps 1.8 3.5 1 K 202 valves 1.8 2.7 1 K 203 Initiation logic 1.8 2.9 1 K 300 Knowledge of the effect that a loss or malfunction of the RHR/LPCI: INJECTION NODE (PLANT SPECIFIC) will have on the following

• 3.6 4.4 K 301 Reactor water level K 302 Suppression pool level 2.3 3.5 1 K 303 Automatic depressurization logic 2.1 4.3 '1 K 304 Adequate core cooling 2.6 4.6 K 400 Knowledge of RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) design feature (s) and/or interlocas which provide for the following

• 3.3 4.2 K 401 Automatic system initiation / injection K 402 Prevention of piping overpressurization 1.8 . 3.4 1 K 403 Punp minimum flow protection '1.6 3.3 1-K 404 Ptsro motor cooling: Plant-Specific 1.5 2.7 1 K 405 Prevention of water hanmer 1.8 3.3 1 K 406 Adequate pornp net positive suction head (interlock suction valve open): 1.6 3.5 1 Plant-Specific O. K 407 Emergency generator load sequencing 2.0: - 3.9 1.3 3.4

-1 1

K 408 Punp operability testing l

. , , - . . - . ~~ .. . .. .. . . - _ -.

K 409 surveillance for all operable components 1.3 3.4 1 K 410 Dedicated injection system during automatic system initiation (injection valve - 2.1 4.1 1 interlocks)

K ~ 411 Loop selection logic: Plant Specific 1.6 4.0 1 .

K 412 System redundancy 1.8 3.6 '1 K 413 The prevention of leakage to the environment through LPC1/RHR heat exchanger: 1.8 3.7 1 -

Plant Specific K 414 Operation from remote shutdown panet 1.6 3.7 1 ,

K 415 Pm p runout protection: Plant-Specific 1.1 2.5 1 K 500 Knowledge of the operational applications of the following concepts as they apply to -

• RHR/LPCI: INJECTION MODE (PLANT SPECIFIC)

K 501 Testable check valve operation 1.1 2.9 1 K 502 Core cooling methods 2.0 3.7 - 1 K 600 Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC)

K 601 A.C. electrical power 2.0 3.7 1 2.0 3.0 1 -l K 602 D.C. electrical power 2.1 3,9 1 K 603 Emergency generator K 604 Keep fill system 2.1 3.5 1 K 605 Condensate storage and transfer system: Plant-Specific 2.1 2.5 1 2.1 3.9 '1 K 606 Suppression pool e K 607 Plant air systems: Plant-Specific 2.1 2.7 1 K 608 ECCS room cooling 2.1 3.1 1 ,

1.8 3.4 1 K 609 Nuclear boiler instrumentation K 610 Component cooling water systems 2.1 3.1 1 j 2.1 4.1 1 K 611 ADS K 612 ECCS room integrity 2.1 2.9 1 SG 1 Knowledge of operator responsibilities during all modes of plant operatien '1.6 ' 4.5 -1 l SG 2 Knowledge of system status criteria which require the notification of plant 1. 6 ' . 4.1 1 personnel ,

SG 3 Knowledge of which events related to system operation / status should be reported to 1.8 4.6 .1 outside agencies

-* 2.5 4.3 SG 4 Knowledge of system purpose and/or function SG S Knowledge of limiting conditions for operations and safety limits -* 2.5 4.4 SG 6 Knowledge of bases in technical specifications for limiting conditions for 2.6 4.3 operations and safety limits ,

i SG 7 Knowledge of purpose and function of major system components and controts

• 2.5 4.3 SG B Knowledge of the annunciator alarms and indications, and use of the response 1.3' 3.7 1 instructions SG 9 Ability to locate and operate components, including local cor,trols 1.3 3.9 .1 SG 10 Abilit) to explain and apply all system limits and precautions 1.1 3.9 '1  :,

SG 11 Ability to recognize indications for system operating parameters which are 2.. 4.5 1 entry level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.1 ' 3.8 1-alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes ~1.1 3.9 1

.of cperation SG 14 Ability to perform without reference to procedures those actions that reqvfre . L1 ' 3.9 1 irrmediate operation of system components cr controls SG 15. Ability to recognize abnormal indications for' system operating parameters which are 1.6 4.5 1 entry-level conditions for emergency and abnormal operating procedures

Shutdown Cooling System (RHR Shutdown Cooling Mode)

APP LSRO SRO NOTE NUM - KNOWLEDGE A 100 Ability to predict and/or make changes in parameters associated with operating the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including '

• 2.6 3.2 A 101 Heat exchanger cooling ftow 2.6 3.2 A 102 SDC/RHR pump fIow

• 2.5 3.3 A 103 Recirculation loop temperatures

• 2.6 2.7 A 104 SDC/RHR pump suction pressure

• 3.3 3.4 A 105 Reactor water levet A 106 Reactor tenperatures (moderator, vesset, flange) 3.1 3.7 2 ,

2.5 2.1 1 A 107 Motor anos: Plant Specific A 108 Heat exchanger temperatures

• 2.5 2.9 i A 109 SDC/RHR pump / system discharge pressure

• 2.5 '2.8-

• 2.6 2.9 A 110 Throttle valve position A 200 Ability to a) predict the inpacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTD0uN COOLING MODE). and b) based on those predictions use procedures to correct,ormitigatetheconsequencesofthoseabnormalconditlonsoroperations Recirculation loop high temperature: Plant Specific

• 3.1 3.3 A 201 A 202 Low shutdown cooling suction pressure: Plant-Specific 2.8- .2.7

• 3.1 3.2 A 203 A.C. failure 8 3.1 2.6 A 204 D.C. failure 3.1 3.7 '

A 205 System isotation A 206 SDC/RHR pump trips 2.8 3.5 A 207 Loss of motor cooling: Plant-Specific

• 2.5 2.7 A 208 Loss of heat exchanger cooling

• 2.5 - 3. 5 A 209 Reactor low water level

• 3.5 - 3.8

• ' 2.6 2.9-

• A 210 valve operation Recirculation pump trips: Plant-Specific 2.6 2.7 A 211 Inadequate system flow

• 2.6 3.0 A 212 A 300 Ability to monitor automatic operations of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including 2.3 3.1 1 A 301 valve operation A 302 Pump trips 2.1 3.2 1 A 303 Lights and alarms 2.3 3.3 1 ,

A 400 Ability to manually operate and/or monitor in the control room 2.1 3.7 - 1-A 401 SOC /RHR pumps 2.1' 3.5 1 A 402 SDC/RNR suction valves A 403 SDC/RHR discharge valves 2.1 3.5 1 Heat exchanger cooling water valves 2.1 3.3 1  ;

A 4 04 2.1 3.2 1 A 405 Mininun flow valves 2.1 3.7 1 A 406 Reactor water level A 407 Reactor temperatures (moderator, vesset, flange) 2.1 3.7 1 l

A 408 Reactor power: Plant-Specific 2.3 3.2- 1 l A 409 System flow 2.1 3.1 1 I i

2.1 ~3.0 1 ]

A 410 System pressures Heat exchanger cooling fIow 2.1 3.2 - 1 A 411 A 412 Recirculation loop temperatures 2.1 3.4 1 K 100 Knowledge of the physical connections and/or cause-effect relationships between

/" SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following  ;

• 3.1 3.6 K 101 Reactor pressure l

1

• 3.5 3.6 -l K 102- Reactor water level 103 Recirculation loop tenperature

• 3.3 3.5 K-K 104 Fuel pool cooling assist: Plant-Specific

• 3.5 2.7 .

• ' 3.0 3.1 K 105 Conponent cooling water systems

[ .K 106 .A.C. electrical power 2.8 3,3

• 28 2.6 K 107 0.C. electrical power

• 3.1. 3.9 K 108 LPCI K 109 Auxiliary steam supply: Plant-Specific 2.5 2.2 2 ~ f, 3.0~ 2.3 2 K 110 RWCU K 111 Nitrogen: Plant-specific 2.3- 1.8 1 Isolation Condenser: Plant-Specific 2.3 2.4 1 K 112 K 113 Floor drain system: Plant-Specific 2.3 1.7 1 K 114 Reactor temperatures (moderator, vessel, flange) 3.0 3.6 K 115 RHR service water: Plant Specific

• 3.3 3.6 K 200 Knowledge of electrical power supplies to the following

• 2.5 '3.1 K 201 - Pump motors K 202 Motor operated valves

• 2.5 2.7 K 300 Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RNR SHUTDOWN COOLING N00E) will have on the following

• 3.0 3.3  !

K 301 Reactor pressure K 302 Reactor water level: Plant Specific

• 3.5 - 3.3 K 303 ' Reactor temperatures (moderator, vessel, flange)

• 3.1' 3.9 .

K 304 Recirculation loop tenperatures 3.1 3.7 Fuel pool cooling assittt: Plant-Specific

• 3.3 2.7 K 305 K 400 - Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) cesign feature (s) and/or interlocks which provide for the following K 401 High temperature isolation- Plant-Specific

2.6 . 3.4 "k

K 402 High pressure isolation: Plant-Specific 2.8 38 ,

K 403 Low reactor water level: Plant-Specific

• 2.8 3.8 K 404 Adequate ptmp NP$H 2.5 2.6 K 405 Reactor cooldown rate

• 2.8 '3.7 i K 406 Motor cooling: Plant-Specific 2.5 2.3 . 2 K 407 Punp minimtn flow -

'2.5 2.8 K 500 Knowledge of the operational applications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RNR SHUTDOWN COOLING MODE) 2.1 2.4 ~1 K 501 NPSH K 502 valve operation 2.1 2.? 1 1'

2.3 3.1 K 503 Heat removal mechanisms K 504 System venting 2.3 2.4 - 1 i

K 600 Knowledge of the effect that a loss or malfunction of the following will have on the ,

SHUTDOWN COOLING $YS!Fi4 (RHR SHUTDOWN COOLING MODE)

K 601' A.C. electrical pow <r

• 3.0 -3.4 K 602 D.C. electrical power

• 3.0 2.9 .

K 603 Recirculation system

• 3.0 3.2  ;

K'604 Reactor water level

• 3.1 3.6' K 605 Component cooling water systems

• 3.0 3.3 K 606 Auxiliary steam supply: Plant-Specific 2.8 2.0 2 K 607 Nitrogen: Plant Specific 2.3 1.8 1

• 3.1 ; 3.7 K 608 RHR service water: . Plant-Specific SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.6 ' 3.7 1 I

I l

SG 2- Knou; edge of system status criteria which require the notification of plant 2.1 3.5 1 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 2.3 4'.1 1-outside agencies SG 4 Knowledge of system purpose and/or function

• 3.6 3.7

~

SG 5 Knowledge of limiting conditions for operations and safety limits

• 3.8 3.9 SG 6 Knowledge of bases in technical specifications for limiting conditions for'

• 4.0 3.7  :

operations and safety limits SG 7 Knowledge of purpose and function of major system components.and controls 4.0 3.7 ,

' SG 8 Knowledge of the annunciator alarms and indications, and use of the response 1.5 3.2 1 instructions SG 9 Ability to locate and operate components, including local controls 1.5 3.5 1 SG 10 Ability to explain and apply all system limits and precautions 1.5 3.3 1 SG 11 Ability to recognize indications for system operating parameters which are 2.1 3.9 1 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.3 3.3 1 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.1 3.2 . 1 of operation SG 14 Ability to perform without reference to procedures those actions that require 1.5 3.3 1 innediate operation of system components or controls SG 15 Ability to recognize abnormal indications for system operating parameters which aro 2.0 4.0 1 entry-level conditions for emergency and abnormal operating procedures 1

.O

Reactor vessel Internals (290002)

APP LSRO SRO NOTE NUM- KNOWLEDGE i l

~ A 100 Ability to predict and/or make chenges in parameters associated with operating the REACTOR VESSEL INTERNALS controls including A 200 Ability to a) predict the impacts of the following on the REACTOR VESSEL INTERNALS, and b) based on those predictions, use procedures to correct, or mitigate the  !

consequences of those abnormal conditions or operations I

• 3.1 ~4.0 A 201 LOCA A 202 overpressurization transient 1.8 3.9 1 A 203 control rod drop accident

• 3.0 3.9 .;

A 204 Excessive hestup/cooldown rate

• 2.6 4.1 A 205 Exceeding thermal limits 2.1 4.2 1 A 206 Exceeding safety limits 2.3 4.5 1 A 300 Ability to monitor automatic operations of the REACTOR VESSEL INTERNALS including A 400 Ability to manually operate and/or monitor in the control room K 100 Knowledge of the physical connections and/or cause-effect relationships between REACTOR VESSEL INTERNALS and the following Main steem system

• 3.6 3.2 K 101 K 102 Recirculation system

• 3.6 3.2 K 103 Reactor feedwater System

• 3.6 3.2 .

K 104 HPCI: Plant-Specific

• 3.3 3.5 K 105 RHR: Plant-Specific

• 3.8 3.2 K 106 HPCS: Plant-Specific

• 3.1 3.1 -

K 107 Isolation condenser: Plant Specific

• 2.6 3.4 K 108 RCIC: Plant-Specific 3.1 3.1-K 109 LPCI: Plant specific

• 3.6 . 3.3 K 110 CR0 hydraulic system

• 3.6 3.1 3.6' 2.9 K 111 CRD mechanism

• 3.5 3.5  ;

K 112 SBLC K 113 Relief / safety valves 3.0 - 3.5 3.5 3.1 K 114 RWCU 3.3 3.5 ,

K 115 Nuclear boiler instrLrnentation 3.1 3.4 K 116 LPCS

• 3.1 3.4 -

K 117 ADS K 118 Loss parts monitoring: F ant-Spect,1c 3.6 2.2 '2 3.0 2.6 K 119 TIP K 120 Nuclear instrumentation 3.5 - 3.3 K 200 Knowledge of electrical power supplies to the following ,

K 300 Knowledge of the effect that a loss or malfunction of the REACTOR VESSEL INTERNALS will have on the following ,

3.8 '3.3 K 301 Reactor water level K 302 Reactor pressure 2.8 3.0 ,

K 303 Reactor power

'3.8 3.4

• 3.8 3.2 K 304 Plant radiation levels

• 3.8 3.2 '

K 305 Off site radiation levels

• 3.3 3.1 K 306 PCIS/NS$$$

• 3.3 3.1 K 307 Nuclear boiler instrumentation i K 400 Knowledge of REACTOR VESSEL INTERNALS design feature (s) and/or interlocks which )l provide for the following N K 401 2/3 core coverage following a DBA LOCA

• 3.8 3.9

• 3.8 3.2 K 402 Separation of fluid flow paths within the vessel .

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K 403- Core orificing 3.5 3.3 i

'1 K 404 Moisture removal from generated steam 2.3 2.8 1 l

• 4.0 3.5 j K 405 Natural circulation

-/

K 500 Knowledge of the oDerational applications of the following concepts as they apply to

\ REACTOR VESSEL INTERNALS K 501 Thermat limits' 2.3 3.9 1 K 502 Fission product poisons

• 2.8 3.1 K 503 Burnable poisons

• 2.6 3.0 ,

K 504 PCIDMR: Plant-Specific 2.0 3.7 1 K 505 Brittle fracture

• 2.5 3.3 2.3 3.2 1 K 506 Heat transfer mechanisms K 507 Safety limits 2.0 4.4 1 K 600 Knowledge of the effect that a loss or malfunction of the following will have on the 4 REACTOR VESSEL INTERNALS K 601 CRD hydraulic system

• 3.6 2.9 K 602 CRD mechanism

• 3.6 2.9 K 603 Recirculation system

• 3.6 3.2 K 604 Reactor feedwater system

• 3.5 3.1 K 605 SBLC

• 3.6 3.4 K 606 Relief / safety valves

• 3.1 3.2 K 607 RWCu

• 3.6 2.7  ;

K 608 Nuclear boiler instrtsnentation 3.3 3.2 K 609 LPCS

• 3.6 3.3 K 610 HPCI: Plant-Specific 3.0 3.3 .

K 611 RHR: Plant-Specific

• 3.6 3.2 K 612 Isolation condenser: Plant-Specific

• 2.6 3.2

. K 613 RCIC: Plant-Specific

• 2. 8 -- 2.8 K 614 LPCI: Plant-specific

• 3.5 3.3 K 615 ADS 3.3 3.4 K 616 Loss parts monitoring 3.5 2.0 2 ,

K 617 TIP 3.0 2.5 K 618 Nuclear instrtsnentation

• 3.6 3.1 K 619 hPCS: Plant-Specific (BW".-5&6) 2.6 3.1 K 620 Main steam system 3.3 3.1 SG 1 Knowledge of operator responsibilities during all modes of plant operation 2.1 3.8 1 SG 2 Knowledge of system status criteria which require the notification of plant

• 3.5 3.7 personnel SG 3 Knowledge of which events related to system operation / status shauld be reported to

• 3.6 4.2 outside agencies SG 4 Knowledge of system purpose and/or function

• 4.1 3.3 SG 5 Knowledge of limiting conditions for operations and safety limits

• 4.1 4.1 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 4.3 3.8 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 4.1 3.3 SG 8 Knowledge of the annunciator alarms and indications, and use of the response 2.3 3.2 1 Instructions SG 9 Ability to locate and operate components, including local controls

• 2.5 2.9 SG 10 Ability to explain and apply all system limits and precautions 2.3 3.4 1-Ability to recognize indications for system operating parameters which are

• 3.8 4.2 SG 11 entry level conditions for technical specifications SG 12 Ability to verify system alarm setpoints an:1 operate controts identified in the 1.6 3.2 1 alarm response manual

l SG 13 Ability to perform specific system crd intsgrated plant procedures during all modes- 1.6 3.2 1 I of operation l<

SG 14 Ability to perform without reference to procedures those actions that require 2.5 3.1 ,

immediate operation of syster- Dmponents or controls

• - SG 15 Ability to recognize abnorr indications fo* system operating parameters which are

• 3.5 3.9

.g entry-level conditions fo' m rgency and abnormat operating procedures 1

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Secordary contalrnent (290001)

NUM- KNOWLEDGE APP LSRO SRO NOTE A 100 AbilityRYCNTAINMENTcontrolsinctto SECOND ingpredict and/or make chan 5 in parameters associated with operating the N A 101 System lineups

• 2.6 3.1 A 102 High area te m erature: BWR 6 2.0 3.6 1 A 200 Ability to a) predict the impacts of the following on the SECONDARY CONTAINMENT, and or mitigate the b) based on those consequences predictions of those abnorma { use procedures conditions to correct, or operations A 201 Personnel airlock failure

• 3.1 3.7 A 202 Excessive outleakage

• 3.1 3.7 A 203 High area radiation

• 3.6 3.6 A 204 High airborne radiation

• 3.6 3.7 A 205 High area te m erature

• 3.6 3.3 A 206 Auxiliary building isolation: BWR-6 1.6 4.0 1 A 300 Ability to monitor automatic operations of the SECONDARY CONTAINMENT including A 301 Secondary contairnent isolation 2.1 4.0 1 A 302 Normal building differential pressure: Plant- Speci f ic

• 2.5 3.5 A 400 Ability to manually operate and/or monitor in the control room f A 401 Reactor building differential pressure: Plant-Specific 1.3 3.4 1 A 402 Reactor building area temperatures: Plant-Specific 1.3 3.4 1 A 403 Auxiliary building differential pressure: Plant-Specific 1.3 2.7 1 A 404 Auxiliary building area temperature: Plant-Specific 1.3 2.7 1 1

A 405 Fuel building differential pressure: Plant-Specific 1.3 3.5 1 A 406 Fuel building area temperature: Plant Specific 1.3 3.5 1 A 407 Radwaste building differential pressure: Plant-Specific 1.1 2.5 1 A 408 Radwaste building area temperature: Plant-Specific 1.5 2.4 1 s

A 409 System status lights and alarms: Plant Specific 1.3 3.2 1 A 410 System lineups: Plant-Specific 1.3 3.3 1 A 411 System reset: Plant-Specific '1.3 3.4 1 A 412 Surveillance testing: Plant-Specific 1.3 3.2 1- ,

K 100 Knowledge of the physical connections and/or cause effect relationships between SECONDARY CONTAINMENT and the following K 101 Reactor building ventilation: Plant-specific

• 3.8 3.5 K 102 Primary containment system: Plant-Specific

• 3.1 3.6.

K 103 Radwaste building ventilation: Plant-Specific 1.5 2.7 1 K 104 SBcf 3.8 3.9 K 105 Auxiliary building ventilation: Plant-Specific 1.5 3.3 1  !

K 106 Auxiliary building isolation: BVR 6 1.5 3.6 1 K 107 Turbine building ventilation (steam tunnel): Plant-$oecific 1.5 3.1 1 K 108 Exhaust stack: BWR-2,3,4

• 2.5 3.3 K 109 Plant air systems

• 3.1 2.9 K 110 Auxiliary boiler system: bur 2,3,4 1.5 1.6' 1 K 200 Knowledge of electrical power supplies to the followir'g K 300 Knowledge of the effect that a loss or malfunction of the SECONDARY CONTAINMENT will have on the following K 301 Off-site radioactive release rates

• 3.8 4.4 K A00 Knowledge of SECONDARY CONTAINMENT design feature (s) and/or interlocks which provide i for the following K 401 Personnel access without breaching seconcary containment: Plant-System

• 3.8 3.8

K 402 Protection against over pressurization: Plant-System

• 3.3 3.5 l

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-* 2.5 2.9 K 403 ' Fluid leakage cottection 1.6 3.4 1 K 404- Auxiliary building isolation: BWR 6 K 500 Knowledae of the prational applications of the following concepts as they apply to - '

.,,-- SECONDA(Y CONTAINMENT 2.0 3.4 1

-( - 'K 501 vacuum breaker operation: BWR 4 1.8 2.2' 1 K 502 Flow measurement: BWR-3 i K 600 Knowledge of the effect that a loss or malfunction of the following will have on the SECONDARY CONTAINMENT Reactor buttding ventilation: Plant-Specific

• 3.8 3.6 -

K 601 K 602 Radwaste building ventilation: Plant Specific 1.6 2.6 1

• 3.8 4.0 K 603 SBGT K 604 Primary containment system

• 3.0 4.1 K 605 Auxiliary building ventilation: Plant-Specific 1.5 3.0 1 K 606 Turbine building ventilation: Plant-Specific - '1. 6 2.3 1 K 607 Auxiliary boiler system: BWR-3,4 2.0 2.0 1 K 608 Plant air systems

• 3.3 2.8 1.8 3.6 1 K 609 A.C. power: BWR-6 1.8 ' 3.9 1

SG 1 Knowledge of operator responsibilities during all modes of plant operation SG 2 Knowledge of system status criteria which require the notification of plant

• 2.6 3.9 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 2.8 4.5 outside agencies SG 4 Knowledge of system purpose and/or function

• 3.8 3.9 SG 5 Knowledge of limiting conditions f or operations and safety limits

• 2.8 4.2 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 3.0 3.8 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 3.5 3.8 ,

SG B Knowledge of the annunciator alarms and indications, and use of the response 1.1 1.5 1 instruct ions SG 9 Ability to locate and operate components, including local controls 1.5 3.6_ 1 SG 10 Ability to explain and apply all system limits and precautions -1.3 3.4 1 Ability to recognize indications f or system operating parameters which are

• - 3.0 4.2 SG 11 entry level conditions for technical specifications &

Abit.ty to verify system alarm setpoints and operate controls identified in the 1.1 3.5 ~1 SG 12 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.3 3.5 1 ,

of operation SG 14 Ability to perform without reference to procedures those actions that require 1.5 3.5 1 immediate operation of system components or controls SG 15 Ability to recognize abnormal indications for system operating parameters which are

• 2.8 4.1 entry-level conditions f or emergency and abnormat operating procedures -

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A.C. Electrical Distribution (262001)

APP ' L$to SRO NOTE NUM KNOWLEDGE s-ss . A 100 Ability to predict and/or make changes in parameters associated with operating the AC ELECTRICAL DISTRIBUTION controls including A 101 Effect on instrumentation and controls of switching power supplies .1.6 3.4 1' A 102 Effects of loads when energiring a bus 1.6 3.5 1 A 103 Bus voltage 1.3 3.1 1 1.3 .2.9 1 A ~104 Load currents 1.3 3.5 1 A 105 Breaker lineups ,

A 200 Ability to a) predict the impacts of the following on the AC ELECTRICAL ,

DISTRIBUTION, and b) based mitigate the consequences on those of those predictions,itions aMormal cond or operationsuse procedures to correct, or >

Turbine / generator trip 1.5 3.6 1 i A 201 2.0 3.9 1. l A 202 Loss of coolant accident A 203 Loss of off-site power 2.0 4.3 1 A 204 Types of loads that, if dcenergized, would degrade or hinder plant operation 1.6 4.2 1 1.3 3.3 1 A 205 Bus grounds 1.5 2.9 1 A 206 Deenergiring a plant bus A 207 Energizing a dead bus 1.5 3.2 1 1.3 3.6 1 A 208 opening a disconnect under load A 209 Exceeding voltage limitations 1.5 3.4 1 A 210 Exceeding current limitations 1.5 3.4 1 A 211 Degraded system voltages 1.3 3.6 1 A 300 Ability to monitor automatic operations of the AC ELECTRICAL DISTRIBUTION including 1.3 3.2 1  ;

A 301 Breaker tripping 1.3 3.3 1 A 302 Automatic bus transf er 1.3 3.5 1-A 303 Load shedding A 304 Load sequencing 1.3 3.6 1 ,

A 400 Ability to manually operate and/or monitor in the control room A 401 All breakers and disconnects.(including available switch yard): Plant-Specific 1.1 3.7 1 A 402 Synchroscope, including understanding of running and incoming voltages 1.1 3.4 1 A 403 Local operation of breakers 1.1 3.4 1 A 404 Synchronizing and paralleling of different A.C. supplies 1.1 3.7- 1 1.1 3.3 1 A 405 voltage, current, power, and f requency on A.C. buses K 100 Knowledge of the physical connections and/or cause-ef f ect relationships between AC ELECTRICAL DISTRIBUTION and the following Emergency generators (diesel / jet) 2.3 4.3 1 K 101 2.3 3.6 1 K 102 D.C. electrical distribution 2.3 3.8 1 K 103 off site power sources 1.8 3.4 1:

K 104 Uninterruptible power supply K 105 Main turbine / generator 1.8 3.2 1 K 106 Alternate shutdown system: Plant Specific 1.6 3.9 1 K 200 Knowledge of electrical power supplies to the following '

off-site sources of power 2.0 3.6 1 K 201 K 300 Knowledge of the ef fect that a loss or malfunction of the AC ELECTRICAL DISTRIBUTION will have on the following K 301 Major system loads - 2.0 3.7- 1 2.1 4.2 1 K 302 Emergency generators 1.8 - 3.2 1 i K 303 D.C. electrical distribution i

-1. 8 3.3 1 i K 3 04 uninterruptible power supply I

.)

1

K 305.- Off-site power system 2.3 3.5 1 ,

K 306 Reactor protection system 2.1 4.1 1 K 400 Knowledge of AC ELECTRICAL DISTRIBUTION design feature (s) and/or interlocks which provide for the following K 401 Bus lockouts 1.3 3.4 1 9 3.3 K 402 Circuit breaker automatic trips 1.3 1 K 403 Interlocks between automatic bus transfer and breakers 1.6 3.4 1 K 404 Protective relaying 1.5 3.1 1 ,;

K 405 Paralleling of A.C. sources (synchroscope) 1.3 3.6 1 ,

K 406 Redundant power sources to vital buses 1.8 3.9 1 K 500 Knowledge of the operational applications of the following concepts as they apply to -

AC ELECTRICAL DISTRIBUTION ,

K 501 Principle involved with paralleling two A.C. Sources 1.3 3.4 1 K $02 Breaker control 1.6 2.9- 1~

K 600 Knowledge of the effect that a loss or malfunction of the following will have on the AC ELECTRICAL DISTRIBUTION K 601 0.C. power 2.3 3.4 1 K 602 Off-site power 2.3 3.9 1 K 603 Generator trip 1.3 3.7 1 SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.6 4.0 1 SG 2 Knowledge of system status criteria wtiich require the notification of plant 1.8 3.8 ' 1 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 2.3 4.4 1 outside agencies ,

SG 4 Knowledge of system purpose and/or function 2.6. 3.5 CG S Knowledge of limiting conditions for operations and safety limits

• 2.3 3.9 4-SG 6 Knowledge of bases in technical specifications for limiting conditions fo- * .

2.5 3.7 p operations and safety limits '

SG 7 Knowledge of purpose and function of major system components and controts

• 2.1 3.5 ' I. '

SG B Knowledge of the annunciator alarms and indications, and use of the response 1.5 3.4 1 instructions i i

SG 9 Ability to locate and operate components, including local controls 1.3 3.6 1 SG 10 Ability to explain and apply all system limits and precautions 1.1 3.5 1 SG 11 Ability to recognize indications fo system operating parameters which are 1.6 3.9 1 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.1 3.3 1 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1,1 3.5 1 of operation SG 14 Ability to perfccm without reference to procedures those actions that require 1.5 3.6 1 immediate operation of system conponents or controls SG 15 Ability to recognize abnormal indications for system operating parameters which are 1.5 3.9 1 entry-level conditions for emergency and abnormal operating procedures 1

i

Emergency Diesel Generators (264000)

NUM KNOWLEDGE

. APP LSRO SRO ~ NOTE A 100 Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEL / JET) contorts including:

A 101 Lube oil tenperature 1.1~ 3.0 1 ,

A 102 Fuet constanption rate 1.1 2.3 1 A 103 operating voltages, currents, and temperatures 1.1 2.9 1 A 104 Crank case temperature and pressure 1.1 2.7 1 A 105 Cylinder temperature differentiat 1.1 2.4 1 A 106 Emergency generator room temperature 1.1 2.4 1-A 107 Cas generator temperature: Plant Specific 1.1 2.5 _1 A 108 Cas generator speed: Plant-Specific 1.1 2.5 1-A 109 Maintaining minimtsn load on emergency generator (to prevent reverse power) 1.1 3.1 1 A 200 Ability to (a) predict the inpacts of the following on the EMERGENCY CENERATORS (DIESEL / JET), and (b) based on those predictions use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A 201 Parattet operation of emergency generator 1.1 3.6 1 A 202 Unloading prior to securing emergency generator 1.1 3.1 - ~1 A 203 operating unloaded, lightly loaded, and highly loaded ' 1.1 3.4 1 A 204 Consequences of operating under/over excited 1.1 3.0' 1 A 205 Synchronization of the emergency generator with other electrical supplies 1.1 3.6 1~

A 206 opening normal and/or alternate power to emergency bus 1.5 3.4 1 A 207 Loss of off-site power during futt-load testing 1.3 3.7 1 A 208 Initiation of emergency generator room fire protection system 1.1 3.7 1 A 209 Loss of A.C. power 1.6 4.1 1 A 210 LoCA 1.8 4.2 1 A 300 Ability to monitor automatic operations of the EMERGENCY GENERATORS (DIESEL / JET) including:

A 301 Automatic starting of compressor and emergency generator 1.3 3.1 1 A 302 Minimum time for load pick un 1.3 3.1 1 A 303 Indicating lights, meters, and recorders 1.1 3.4 1 A 304 Operation of the governor control system on frequency and voltage control 1.1 3.1 1 A 305 Load shedding and sequencing 1.3 3.5 1 A 306 Cooling water system operation 1.5 3.2 1 A 400 Ability to manually operate and/or monitor in the controt room:

A 401 Adjustment of exciter voltage 1.1 3.4 1 A 402 Synchroscope i1 3.4 1 A 403 Transfer of emergency cor. trol between manual and automatic 1.1 3.4 'l

.A 404 Manual start, loading, and stopping of emergency generator: Plant Specific 1.1 3.7 1 A 405 Transfer of emergency generator (with toad) to grid 1.1 3.7 1 A 406 Droop setting 1.1 2.8 1 K 100 Knowledge of the physical connections and/or cause ef fect relationships between EMERGENCY GENERATORS (DIESEL / JET) and the following:

K 101 A.C. electrical distribution 2,3 4.1 1 K 102 D.C. electrical distribution 2.3 3.4 1 K 103 Fire protection system 2.1 3.2 1 K 104- Emergency generator cooling water system 1.8 - 3.3 1' K 105 Emergency generator fuel OIL supply system 1.8 3.3 1 K 106 Startir's system 2.0 ' 3.2 1 K 107 Emergency core cooling systems 2.3 4.1 1

l l

K 200 Knowledga of electrical power supplies to the following:

K 201 Air compressor 1.5 2.4 1 K 202 Fuel oil pumps 1.5 2.4 1-K 203 Turning gear (jet engine): Plant-Specific 1.3 2.3 11 K 204 Ignition system (jet engine): Plant specific 1.3 2.7 1 ';

K 205 Lube oil romps 1.3 . 2.4 1 i K 206 Battery charger 1.3 2.2 1. ,

K 207 Emergency generator field flash 1.3 2.3 1 K 300 Knowledge of the effect that a loss or malfunction of the EMERGENCY GEhERATORS (DIESEL / JET) will have on the following:

K 301 Emergency core cooling systems

• 2.8 4.4 K 302 A.C. electrical distribution 2.5 4.0 K 303 Major loads powered from electrical buses fed by the emergency generator (s) 2.3 4.2 1 l

K 400 Knowledge of EMERGENCY CENERATORS (DIESEL / JET) design feature (s) and/or interlocks which provide for the following:

K 401 Emergency generator trips (normal) 1.8 3.7 1 K 402 Emergency generator trips (emergency /LOCA) 2.3 4.2 1 K 403 Speed droop control 1.1 2.7 1 K 404 Field flashing 1.1 2.7 1.

K 405 Load shedding and sequencing 1.6 3.5 1 K 406 Governor control 1.1 2.7 1

'K 407 Local operation and control 1.1 3.4 1 K 408 Automatic startup 1.5 - 3.7 1 K 500 Knowledge of the operational apolications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL / JET):

K 501 Definition of frequency and synchronous frequency 1.5 2.1 1 ,

K 502 Reactive power control 1.3 2.1 .1

-(

b K 503 Real power control 1.1 2.4 1 K 504 Governor control 1.1 2.5 1 K 505 Paralleling A.C. power sources 1.1 3.4 :1 K 506 Load seque:ncing 1.6 3.5 1 K 507 Speed droop 1.1 2.4 1 K 600 Knowledge of the effect that a loss or malfunction of the following will have on the >

EMERGENCY GENERA 10RS (DIESEL / JET):

K 601 starting air 1.5 3.9 1 K 602 Fuel oil pumps 1.5 3.6 1 K 603 Lube oil pm ps 1.5 3.7 1 K 604 Turning gear (jet engine); Plant-Specific 1.5 2.5 1 K 605 Ignition system (jet engine): Plant-Specific 1.5 3.0 1 K 606 Battery charger 1.6 3.1 1 K 607 Cooling water system 1.B 3.9 1 K 608 A.C. power 2. 0 - 3.7 1 K ,609 D.C. power 2.0 3.5 1 SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.3 4.2 1 SG 2 Knowledge of system status criteria which require the notification of plant 1.6 3.8 1 personnel SG 3 Know!erige of which events related to system operation / status should be reported to 1.8 4.3 1 outside agencies SG 4 Knowledge of eystem purpose and/or function

• 3.0 3.8 I

• 2.5 4.1 SG S Knowledge of ilmiting conditions for operations and safety limits SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 2.5 3.9 operations and safety limits

• 2.6. 3.5

- SG . 7~ Knowledge of purpose and function of major system conponents ard controls .

SG 8 Knowledge of the annunciator alarms srd indications, and use of the response 1.1 3.6 ~ 1. '.

instructions .I i SG 9 Ability to locate and operate conponents, including local controls 1.1 3.9 1 p

-( -

sc 10 Ability to explain and apply att system limits and precautions 1.3 3.6 1- )

SG 11 Ability to recognize indications for system operating parameters which are 2.0' 4 '.1 1 entry-Leve! conditions for technical specifications ,

I sG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.1 3.5 1 alarm response manual .! P SG 13 Ability to perform specific system and integrated plant procedures during all modes- 1.1 3.7 1 of operation SG 14 Ability to perform without reference to procedures those actions that require 1.1 ; 3.7. ~1 imediate operation of system conponents or controls <

SG 15 Ability to recognize abnormal indications for system operating parameters which are 1.3 4.2 1 r entry-level conditions for emergency and abnormal operating procedures I

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Intermediate Rsnge Monitor (IRM) System (215003)

APP LSRO SRO NOTE NUM ' KNOWLEDGE

.A 100 Ability to predict and/or make changes in parameters associated with operating the IRM SYSTEM controls including 2.0 3.3 '1 A 101 Detector position '

102 Reactor power indication response to rod position changes

• 2.6 3.7

.A 2.3 3.7 1 A 103 RPS status

• 3.0 3.4 -

A 104 control rod block status A 105 SCRAM and rod block trip setpoints 2.1 3.9 1-A 106 Lights and alarms 2.1 3.2 1 A 200 Ability to a) predict the irrpacts of the following on the IRM SYSTEM, and b) based on those those predictions, abnormal condit ions or operationsuse procedures to correct, or mitigate the consequences of A 201 Power supply degraded 2.0 3.2 1 A 202 IRM inop condition 2.0 3.7 1 2.0 3.1 1 A 203 Stuck detector A 204 up scale or down scale trips 2.0 3.8 1 A 205 Faulty or erratic operation of detectors / system 2.0 3.5 1 A 206 Faulty range switch 1.6 3.2 -1 1.6 2.7 1 A 207 Failed recorder A 300 Ability to monitor automatic cperations of the IRM SYSTEM including 1.6 3.3 1 A 301 Meters and recorders A 302 Annunciator and alarm signals 1.5 3.3 1 A 303 RPS status 1.5 3.6 1 1.8 3.5 1 A 304 Control rod block status A 400 Ability to manually operate and/or monitor in the control room O' A 401 1RM recorder indication A 402 CRT display indications: Plant-Specific 2.0 1.6 3.3 2.8 1

1 A 403 IRM range switches 1.6 3.4 1 A 404 1RM back panel switches, meters, and indicating lights 1.5 3.3 1 A 405 Trip bypasses 1.5 3.4 1 A 406 Detector drives 1.5 2.9 1 A 407 Verification of proper functioning / operability 1.3 3.6 1 K 100 Knowledge of the physical connections and/or cause-effect relationships between IRM SYSTEM and the following K 101 PPS

• 3.0 3.9 K 102 Reactor manual control

• 2.8 3.6 K 103 Rod control and information system: Plrent-Specif ic 2.3 3.1 1 K 104 Process computer / performance monitoring system (SPOS/ERIS/CRIDS/00s): 1.6 2.8 1 Plant Specific K 105 Display control system: Plant-Specific 1.5 3.3 1 K 106 APRM SCRAM signals: Plant-Specific 1.5 4.0 1 K 107 Reactor vessel

• 3.3 3.0 K 200 Knowledge of electrical power supplies to the following K 201 IRM channels / detectors 1.3 2.7 - 1 I

K 300 Knowledfe the fot owing of the ef fect that a loss or malfunction of the IRM SYSTEM will have on K 301 RPS 3.5 - 4.0

. K 302 Reactor manual control

• 2.6 3.6 .

K 303 Rod control and information system: Plant-Specific

• 2.6 3.7 K 304 Reactor power indication

• 2.6 3.6 I

i

, _ _ _ . . _ _ _ . i

K 305 APRX: Plent Specific 2.0 3.8' 1 K 400 Knowledge of IRM SYSTEM design feature (s) and/or interlocks which provide for the t following

• - 2.8 3.7 -

K. 401 Rod withdrawat blocks K 402 Reactor SCRAM signals

• 2.5 4.0 K -403 Gamma compensation 1.8 2.4 1 K 404 Varying system sensitivity levels using range switches 2.1 2.9 1 K 405 Changing detector position 2.1 3.0 1 .

K 406 Alarm seat-in 1.6 2.6 1 K 500 Knowledge of the operational applicatioris of the following concepts as they apply to

• IRM SYSTEM K 501 Detector operation 2.1 2.7 1 K 502 Gamma discrimination 2.1 2.3 1-K 503 Changing detector position 2.1 3.1 1 K 600 Knowledge of the ef fect that a loss or malfunction of the following will have on the IRM SYSeEM K 601 Reactor protection system (power supply): Plant-Specific 1. 8 ' 3.8 1 K 602 24/48 volt D.C. power: Plant-Speci f ic 1.8 3.8' 1 K 603 Detector drive motor 1.8 2.9 1 K 604 Detectors 1.8 3.0 1 K 605 Trip units 1.8 3.2 -1 K 606 APRM 1.5 3.4 1 K 607 Recorder 1.5 2.3 1 SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.6 3.9 1 SG 2 Knowledge of system status criteria which require the notification of plant 1.8 3.7 '1 personnet SG 3 Knowledge of which events related to system operation / status should be reported to 1.8 4.1 1 outside agencies SG 4 Knowledge of system purpose and/or f unction

• 3.3 3.5 SG 5 Knowledge of timiting conditions for operations and safety limits

• 2.5 . 4.2 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 3.3 3.8 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controts

• 2.8 ~ 3.5 SG B Knowledge of the annunciater alarms and indications, and use of the response 1.5 . 3.4. .1 >

irstructions SG 9 Ability to tocate and operate components, including local controts .1.1 3.4 1 SG 10 Ability to explain and apply att system limits and precautions 1.3 3.4 1 SG 11 Ability to recognize indications for system operating parameters which are 2.1 4.1 1 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controts identified in the' 1.1 3.5 1 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during att modes 1.1 3.6 1 of operation SG 14 Ability to perform without reference to procedures those actions that require 1.5 3.4 - 1 frrrnediate operation of system conponents or controls SG 15 Ability to recognize abnormal indications for system operating parameters which are 1.5 3.9 1 entry-level conditions for emergency and abnormat operating procedures r

Nuclear Boller Instrumentation (216000)

NUM KNOWLEDGE

' APP LSRO SRO NOTE to redict and/or make changes in parameters associated with operating the g- A 100 AbilitgB01{ERINSTRUMENTATIONcontrolsi NUCLEA luding A 101 Recorders and meters 1.6 3.3 1 A 102 Removing or returning a sensor (transmitter) to service 1.5 3.1 1 A 103 Surveillance testing 1.5 3.2 1 A 104 System venting 1.5 2.8 1 A 200 Ability to a) predict the inpacts of the following on the NUCLEAR BolLER INSTRUMENTATION, and b) based on those predictions use procedures to correct, or mitigate the consequences of those abnormal condit, ions or operations A 201 Detector equalizing valve leaks 1.8 3.2 1 A 202 Instrument line plugging 1.8 3.0 1 A 203 Instrument line leakage 1.8 3.1 ' 1 A 204 Detector diaphragm failure or leakage 1.8 '3.0 1 A 205 Surveillance testing 1.5 3.1 1 A 206 Loss of power supply 1.6 3.1 1 A 207 Reference leg flashing 1.8- 3.5 1 A 208 Elevated containment temperature 1.6 3.4 1 A 209 Jet pump flow: Design Specific 2.0 ' 3.2 1 A 210 Rapid vessel depressurizations 1.8 3.5 1 Heatup or c.ooldown of the reactor vesset 2.0 , 3.3 1 r A 211 A 212 Instrment isolation valve closures 1.6 2.9 .1 A 213 Instrment isolation valve openings 1.6 3.0 1 A 214 Recirculation flow: Design-Specific 2.0 2.9 1 A 300 Ability to monitor automatic operations of the NUCLEAR BOILER INSTRUMENTATION including A 301 Relationship between meter / recorder readings and actual parameter values: 1.6 3.4 1 Plant-Specific ,

A -400 Ability to manually operate and/or monitor in the control room A 401 Recorders 1.1 3.1 1 A 402 Channel select controls 1.1 3.1 1 A 403 Process conputer: Design Specific 1.1 3.1 1 K 100 Knowledge of the physical connections and/or cause-effect relationships between NUCLEAR B0!LER INSTRUMENTATION and the following K 101 Reactor protection system 2.1 4.1 1

.]

K 102 PCIS/NSS$$ 1.5 4.0 1 1 K 103 Reactor core isolation cooling system: Plant-Specific 1.8 3.6 1 j

K 104 High pressure core spray system: Plant-Specific 1.5 4.0 1 i

K 105 Residual heat removal: Plant Specific 2.3 3.9 1 K 106 Low pressure core spray 2.3 3.9 1 K 107 Automatic depressurization system 1.5 4.1 1 K 108 Relief / safety valves 1.3 3.9 1 K 109 Redundant reactivity control / alternate rod insertion: Plant-Specific 2.1 4.0 1 K 110 Recirculation flow control system .

1.8 3.4 1 K 111 MSIV leakage control system: Plant Specific 1.3 2.8 1 K 112 Reactor water level control system 2.5 3.7 Feedwater systen, 1.5 3.5 1 K.113 1.3 4.1 1'  !

K 114 High pressure coolant injection: Plant-Specific K 115 Isolation condenser: Plant-Specific 1.3 4.1 1 K, 116 Main turbine 1.3 3.1 1 l 1

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~ .. .. -. . . - - . .. . .- . .

K 117 ' Emergency generators 2.1 3.7 .1 K 118 Analog trip system: Plant-Specific 11.3 3.1 1 K 119 Anticipated transient without scram system: Plant-specific 1.3 3.9 1' K 120 Process computer: Plant-Specific 1.3 2.8 _1

.1.3 2.9 1

K 121 SPDS/ERIS/CRIDS/ GDS: Plant-Specific .

2.1 3.8 1 K 122 Reactor vessel K 123 Recirculation system '2.0 3.4 1 K 200 Knowledge of electrical power supplies to the following K 201 Analog trip system: Plant-Specific 1.3 2.8 1 .i K 300 Knowledge of the effect that a loss or malfunction of the NUCLEAR BOILER INSTRUMENTATION will have on the following ,

K 301 Reactor protection system 2.0 4.3 1.

K 302 PCIS/NSSSS .1.6 4.3 1 K 303 Reactor core isolation cooling system: Plant-Specific 1.6 3.8 1 I K 304 High pressure core spray system: Plant-specific 1.3 4.0 1 K 305 Residual heat removal: Plant Specific 2.1 ' 3.9 1 K 306 Low pressure core spray 2.1 3.9 1 K 307 Automatic depressurization systen 1.3 4.1 1  !

K 308 Relief / safety valves 1.3 3.7 1 K 309 Redundant reactivity control / alternate rod insertion: Plant-Specific 1.8 4.0 1 K 310 Recirculation flow control system 1.6 3.3 1 K 311 MSIV leakage control system: Plant-Specific 1.3 2.8 1 K 312 Reactor water level control system 2.3 3.8 1 K 313 Feedwater system 1.3 3.5 1 K 314 High pressure coolant injection: Plant-Specific 1.3 4.2 1 K 315 Isolation condenser: Plant-Specific 1.3 4.2 1 i

1.3 3.1 1 K 316 Main turbine K 317 Emergency generators 1.8 3.7 1 K 318 Analog trip system: Plant-Specific 1.3 3.0 1 K 319 Anticipated transient without scram system: Plant Specific 1.3 4.0 1 K 320 Process computer: Plant-Specific 1.3 2.6 1 K 321 SPDS/ERIS/CRIDS/ GDS: Plant-Specific 1.3 ~ 2.8 1 K 322 Reactor vessel 2.3 3.3 1 K 323 vessel temperature monitoring 2.3 3.3 1 K 324 vessel level monitoring 2.3 4.1 1 K 325 Vessel pressure monitoring 2.0 4.1 1 K 326 Core flow monitoring 1.8 3.7 i K 327 Core differential pressure monitoring 1.8 3.1 1 K 328 Loose parts detection in the primary system: Plant-Specific 1.3 2.1 1 K 329 Jet pump flow monitoring: Plant-Specific 1.8 3.2 1 K 330 Recirculation system 2.0 3.3 1 K 400 Knowledge of NUCLEAR B0llER INSTRUMENTATION design feature (s) and/or interlocks which provide for the following K 401 Reading of nuclear boiler parameters outside the control room 1.3 3.6 1' K 402 Physical separation of sensors 1.3 3.2 1 K 403 Redundancy of sensors 1.3 3.6 1 K 404 Inputs to the reactor protection system 1.6 -3.8 1 f- g

( j)

K 405 Initiation of the emergency core cooling systems 2.1 4.1 1 K 406 Initiation of the PCIS/NS$$$ - 1.3 4.0 1

t K 407 Recirculation p m p prottetion: Plent-Specific 1.3 3.0 1 3.0

~

K 408 Protection for the main turbine from high moisture carryover 1.3 1 K 409 Protection against filling the main steam lines from the feed system 1.3- 3.3 1 K 410 Automatic recirculation pu m speed control: Plant Specific 1.3 3.1 -1 Inputs to the redundant reactivity control system /atternate rod insertion: 1.6 4.0 1 K 411 Plant-Specific K 412 Reactor vesset overpressure protection 1.3 3.9 1 K 413 Overpressure protection for various low pressure systems 1.6 3.4 1 ..

K 414 Temperature compensation for reactor water levet indication: Plant-Specific 1.6 3.4 1 K 500 Knowledge of the operational applications of the following concepts as they apply to NUCLEAR BOILER INSTRUMENTATION 1.6 3.2 1 K 501 vessel level measurement K 502 vesset pressure measurement 1.6 3.2 1 K 503 vesset temperature measurement 1.6 3.2 1 K 504 Vessel differential pressure measurement 1.6 2.9 1 K 505 vesset vibration measurement (toose parts monitor) 1.3 2.3 1 K 506 Rapid vessel depressurization effects on vessel level indications 1.3 3.6 i K 507 Elevated containment temperature effects on level indication 1.3 3.8 .1 1.3 3.2 1 K 508 Steam flow effect on reactor water level K 509 Recirculation flow effects on level indications: Design-Specific 1.6 2.9 1 K 510 Indicated levet versus actual vessel level during vessel heatups or cooldowns 1.3 3.3 1 K 511 Indicated vesset temperature response during rapid heatups or ceolcowns 1.3 3.3 1 K $12 Effects on level indication due to rapid changes in void fraction 1.3 3.3 1 K 513 Reference leg flashing: Design-Specific 1.3 3.6 1 K 514 Density 1.3 2.6 1 K 515 Static pressure 1.3 ' 2.2 1 K 516 Dynamic pressure 1.3 2.1 1 K 600 Knowledge of the effect that a loss or malfunction of the following will have on the NUCLEAR BolLER INSTRUMENTATION '

K 601 A.C. electrical distribution 1.5 3.3 1 K 602 D.C. electrical distribution 1.5 3.0 1 K 603 Tenperature conpensation: Plant-Specific 1.5 2.8 i SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.3 3.8 1 SG 2 Knowledge of system status criteria which require the notification of plant 1.6 3.6 1 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 1.8 4.3 1 outside agencies SG 4 Knowledge of system purpose and/or function

• 2.1 3.6 4 SG 5 Knowledge of timiting conditions for operations and safety limits

• 2.3 4.2 4 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 2.3 3.9 4 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controts

• 2.1 3.6 4-SG B Knowledge of the annunciator alarms and indications, and use of the response 1.3 3.4 1 +

instructions SG 9 Ability to locate and operate conponents, including tocal controls 1.3 3.6 1 SG 10 Ability to explain and apply att system limits and precautions 1.3 3.3 1 SG 11 Ability to recognize indications for system operating parameters which are 2.0 4.2 1 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.3 3.4 1 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.3 3.6 1 of operation SG 14 Ability to perform without reference to procedures those actions that require 1.3 3.5 1 imediate operation of system components or controls

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R*Ector Protection System (212000)

APP LSRO. $%0 NOTE

,NUM KNOWLEDGE

.- . - A 100 Ability to predict and/or monitor changes in parameters associated with operatire the REACTOR PROTECT 10N SYSTEM controts including A 101 RPS motor-generator output voltage 1.3 2.9 1 A 102 RPS motor-generator output anps '1.3 2.9 1 1 A 103 RPS motor-generator uutput frequency: Plant-specific 1.3 2.5 1 A 104 RPS bus voltage: Plant-Specific 1.3 3.0 1 A 105 RPS bus frequency: Plant-Specific 1.3 2.7 1 A 106 Reactor poder 1.6 4.2 '1 A 107 Rod position information 1.6 3.4 1 A 108 Valve pod tion 1.3 3.4 1 A 109 Indivisual relay status: Plant-Specific 1.3 3.0 1 A s10 Process conputer 1.3 2.4 1 A til System status tights and alarms 1.3 3.3 1 A 200 Ability to (a) predict the inpacts of the following on the REACTOR PROTECTION SYSTEM, and mitigate the (b) based onof consequences those thosepredictions ( use procedures abnorma conditions to correct, control, or or operations A 201 RPS motor-generator set failure 1.3 3.9 1 A 202 RPS bus power supply failure 1.3 3.9- 1 A 203 Surveittance testing 1.6 3.5 1 A 204 Nuclear instrunent system f ailure 1.6 3.7 1 A 205 Nuclear boiler instrument system failure 1.6 3.7 1 A 206 High reactor power 1.3 4.2 -1 A 207 High reactor pressure 1.3 4.2 1 13 4 '.2 1 g A 208 tow reactor level 1.3 4.3

'( A 209 High conta'inment/drywell pressure 1. -

A 210 Reactor / turbine pressure control system low pressure: Plant-Specific 1.3. 3.8 1 9

1.3 4.1 1 A 211 Main steamline isolation valve closure A 212 Main turbine stop control valve closure 1.3 4.1 1 A 213 Low condenser vacuum: Plant-Specific 1.3 - 3.9 . 1 A 214 High SCRAM instrument volume water level 1.3 4.0 1' A 215 Load rejection 1.3 3.8 ' 1 A 216 Changing mode switch position 1.6 4.1 - 1 A 217 Main steamline high radiation 1.3 4.2 1 A 218 SCRAM air header low pressure 1.3 3.9 1 A 219 Partial system activation (half SCRAM) 1.6 3.9 1 A 220 Full system activation (full-SCRAM) 1.6 4.2 1 A 221 Failure of individual relays to reposition: Plant-Specific 1.3 3.9 1 A 300 Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including 1.6 4.4 1 A 301 Reactor Power A 302 Individual system relay status: Plant-Specific 1.3 3.5 1 A 303 Rod position .1.6 4.2' 1 A 304 System status lights and alarms 1.3 .3.8 1 1.3 3.9 1 A 305 SCRAM instrunent volume tevet 4 A 306 Main turbine trip: Plant-Specific 1.3 4.2 1 1.3 3.6 1-A 307 SCRAM sir header pressure Recirculatito pump trip 1.3 3.7 1 A.308 A 400 Ability to manually operate and/or monitor in the control room

I A 401' Provide manuat SCRA;4 signst(s) 1.3 4.6 1 l

A 402 Perform system functional test (s) 1.3 3.7 1 l

A 403 Provide manual select rod insertion: Plant-Specific 1.6 ' 3.9 1 A 404 Bypass SCRAM instrument volume high level SCRAM signal 1.3 3.9 1 1.6 4.3 1 A 405 Reactor power A 406 Control rod position 1.6 4.1- 1 A 407 System status lights and alarms 1.3' 3.9 1 f A 408 Individual system relay status: Plant Specific 1.3 3.4 1 1.3 3.8 1 A 409 SCRAM instrument voltrne level A 410 Main turbine trip: Plant Specific 1.3 4.0 =1 1.3 3.7 _ 1- ,

A 411 Rcram air header pressure A 412 close/open SCRAM instrument voltane vent and/or drain valves 1.3 ' 3.9 - .1 A 413 Perform trdividual control rod SCRAM testing 1.3 3.6 1 A 414 Reset system following system activation 1.3 3.8 1 A 415 Recirculation pump trip /EOC RPT 1.3 3.8 1 A 416 Manually actjvate anticipated transient without SCRAM circuitry /RRCS: 1.3 4.4 1 Plant-Specific A 417 Perform alternate reactivity / shutdown operations 1.3 4.1 1 ,

K 100 Knowledge of the physical connections and/or cause-effect relationships between _

REACTOR PROTECTION SYSTEM and the following [

2.1 3.9 1 K 101 Nuclear instrumentation -

2.0 3.9- 1 K 102 Nuclear boiler instrumentation K 103 Recirculation system 2.0 3.6 1 2.1 3.6 1 K 104 A.C. electrical distribution K 105 Process radiation monitoring system 2.0 3.6 1' K 106 Control rod drive hydraulic system 2.3 3.6 -1

[

O K 107 Relief / safety valves (Low-low-set logic): Plant-specific. 1.3 2.3 3.5 3.1 1-1 1

K 108 Control rod and drive mechanism K 109 Process computer 1.5 ' 2.4 1 1.3- 3.4' 1 K 110 Main turbine 1.3 3.5 1  ;

K 111 Condenser vacutsn K 112 Reactor / turbine p'ssure control system: Plant-Specific 1.3 3.6 1 K 113 containment pressure 1.3 3.6 1-K 114 Main steam system 1.3 3.7 1 K 115 SCRAM sir header pressure 1. 8 ' 3.9 1 K 200 Knowledge of electrical power supplies to the following K 201 RPS motor generator sets 1.6 3.3 1 K 202 Analog trip system logic cabinets 1.3 2.9 1 K 300 Knowledge of the effect that a toss or malfunction of the REACTOR PROTECTION SYSTEM will have on the following K 301 Process radiation monitoring 1.6- 3.2 1 K 302 Primary containment isolation system / nuclear steam supply shut-off: Plant Specific 1.5 3.9 1 K 303 Local power range pranitoring system: Plant-Specific 1.6 3.4 1  ;

K 304 Average power range monitoring system: Plant-Specific 1.6 3.6 1 K 305 RPS togic channels 2.0 3.8- 1-K 306 Scram air header solenoid operated valves 2.1 4.1 1 K 307 Reactor power (thermat heat flux) 2.0- 3.9 1 K 308 Reactor coolant primary system integrity' 1.6- 3.8 1~

l 1.6 3.6 1 K 309 The magnitude of heat energy that must be absorbed by the containment during ,

accident / transient conditions I

1 1

1 1

I l

?

K 310 The tbility of the core cooling systems to provide adequcte core cooling during loss 2.1 3.9 1 of coolant accidents ,

~K 311 Recirculation system 2.0 3.3 1 K 312 Secondary containment integrity 2.3 3.3 1 K 400 Knowledge of REACTOR PROTECTION SYSTEM design feature (s) and/or interlocks which provide for.the following ,

K 401 System redundancy and reliability 1.6 3.6 1 K 402 The prevention of a reactor SCRAM following a single conponent f ailure 1.6 3.7 1 K 403 The prevention of supplying power to a given RPS bus from multiple sources 1.3 3.1 1 simultaneously K 404 The prevention of supplying both RPS buses simultaneously from the alternate power 1.3 3.1 1 r source: Plant-Specific K 405 Functional testing of the system while maintaining power operation 1.3 3.6 1 K 406 Select rod insertion: Plant-Specific 1.5 3.0 1 K 407 Manual system activation (trip) 1.3 4.1 1 K 408 Complete control rod insertion following SCRAM signal generation 1.3 4.2 1 K 409 Control rod insertion following RPS system electrical failure 1.3 3.9 1 K 410 Individual rod SCRAM testing 1.3 3.6 i K 411 Operation with shorting links removed: Plant-Specific 1.6 3.5 1 .

K 412 Bypassing of selected SCRAM signals (manually and automatically): Plant-Specific 1.5 4.1 1 K 500 Knowledge of the operational applications of the following conepts as they apply to REACTOR PROTECTION SYSTEM K 501 Fuel thermal time constant 1.3 2.9 1 K 502 Specific logic arrangements 1.3 3.4 1 K 600 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR PROTECTION SYSTEM K 601 A.C. electrical distribution 2.0 3.8 1 2.1 3.9 '1 r K 602 Nuclear instrumentation K 603 Nuclear boiler instrumentation 2.0 3.7 1.

K 604 D.C. electrical distribution 2.0 3.1 1 K 605 RPS sensor inputs 1.8 3.8 1 SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.5 4.5 1 SG 2 Knowledge of system status criteria which require the notification of plant 1.6 4.3 1 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 1. 8 - 4.5 1 outside agencies SG 4 Knowledge of system purpose and/or function 2.1 4.3 4 SG 5 Knowledge of limiting conditions for operations and safety limits

• 2.3 I. 5 4 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 2.3 4.3- 4 operations and safety limits SG 7 Knowledge of purpose and function of major system conponents and controls 2.1 4.2 4 SG B Knowledge of the annunciator alarms and indications, and use of the response 1.5 4.2 1 instructions SG 9 Ability to locate and operate components, including local controls 1.3 4.2 1 SG 10 Ability to explain and apply all system limits and precautions 1.3 4.2 1 Ability to recognize indications for system operating parameters which are 1.8 4.5 1 SG 11 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.3 3.9 - 1-alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.3 4.1 1 of operation SG 14 Ability to perform without reference to procedures those actions that require 1.3 4.4 1 imediate operation of system conponents or controls 1.5 4.7 1.  !

SG 15 Abilit to recognize abnormal indications for system operating parameters which are entry evel conditions for emergency and abnormal operating procedures ,

Rod Position Information System (214000)

APP LS20 SRO , NOTE NUM KNOWLEDGE A 100 Ability to predict and/or raake changes in parameters associated with operating the R00 POSITION INFORMATION SYSTEM cont % s including O A 200 Ability to a) predict the impacts of the following on the ROD POSITION INFORMATION

-SYSTEM,andb)basedonthosepredictionslonsoroperationsuse procedures to correct, or mitigate the consequences of those abnormal condit 2.5 3.3 4 201 Failed reed switches

-t A 202 Reactor SCRAM

• 2.6 3.7 A 203 overtravel /in-out

• 2.5 3.9 A 300 Ability to monitor automatic operations of the R00 POSITION INFORMAfl0N SYSTEM inclucilng A 301 Full core display 1.8 3.3 1 A 302 Alarm and indicating lights 1.8 - 3.1 '1 A 303 verification of proper functioning / operability 1.8 3.7 1 A 304 RCIS: Plant-specific 1.8 3.8 1 A 400 Ability to manually operate and/or monitor in the control room A 401 RCIS rod action control bypass switches 1.8 3.3 1 1.8 3.8 1 'I A 402 Control rod position A 403 Control rod drive temperature 1.J 2.7 1 K 100 Knowledge of the physical connections and/or cause-effect relationships between ROD POSITION INFORMATION SYSTEM and the following K 101 RWM: Plant-Specific 2.1 3.2 1 K 102 RSCS: Plant-Specific 2.1 3.1 1 K 103 CRDM

• 2.6 3.1 K 104 RMCS: Plant-Specific

• 2.6 3.2 K 105 Futt core display: Plant-Specific

• 2.8 3.3 O

y K 106 RCIS: Plant Specific 2.3 2.1 3.4 3.0 1

1 K 107 Process computer K 108 CRIDS/ERIS/SPOS/GOS: Plant Specific 2.1 2.6 1 [

K 200 Knowledge of electrical power supplies to the following K 300 Knowledge of the effect that a loss or malfunction of the R00 POSITION INFORMAT!DM ,

SYSTEM will have on the following ,

K 301 RWM: Plant-Specific 1.8- 3.2 1 K 302 RSCS: Plant-Specific 1.8 3.1 1 K 303 RMCS: Plant Specific

• 3.0 3.2 K 304 RCIS: Plant Specific 1.8 3.3 1.

K 305 Process computer 1.8 2.6 1 K 306 CRIDS/ERIS/SPDS/CDS: Plant-Specific 1.8 2.5 1 K 400 Knowledge of R00 POSITION INFDRMATION SYSTEM design feature (s) and/or interlocks which provide for the fo! lowing ,

K 401 Reed switch locations

• 3.0 3.1 K 402 Thermocouple 2.0 2.5 1 K. 500 Knowledge of the operational applications of the following concepts as they apply to {

ROD POSITION INFORMATION SYSTEM j K 501 Reed switches

• 3.0 2.8 '

K 600 Knowledge of the effect that a loss or malfunction of the following will have on the ROD POSITION INFORMATION SYSTEM l

K 601 A.C. electrical power 2.3 2.6 1 K 602 Position indication probe

• 3.0 2.7 SG 1 Knowledge of operator responsibilities during all modes of plant operation 1.6- 3.5 1 SG 2 Knowledge of system status criteria which require the notification of plant 2.3 3.4 1 -j i

personnel I

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, .~ -- - _ .. . .- - - . - .

SG 3 Knowledgf of which evtnts related to system operation / status should be rsported to 1.6 4.0 1 outside agencies SG 4 Knowledge of system purpose and/or function

• 3.0 3.3 SG 5 Knowledge of limiting conditions for operations and safety limits

• 2.8 3.8 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 2.8 3.6 .

operations and safety limits SG 7 Knowledge of purpose and function of major system conponents and controls

• 3.0 3.5 SG 8 Knowledge of the annunciator alarms and indications, and use of the response 1.8 3.3 1 instructions SG 9 Ability to locate and operate components, including local controls 1.8 3.3 1 ,

SG 10 Ability to explain and apply all system '.imits and precautions 1.5 3.2 1 to recognize indications for system operating parameters which are

• 2.6 4.0 SG 11 Abilit{evel conditions for technical specifications entry-SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.5 3.1 1 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.5 3.2 1 of operatio SG 14 Ability to perform without reference to procedures those actions that require 1.5 3.1 i immediate operation of system components or controls SG 15 Ability to recognize abnormal indications for system operating parameters which are 1.5 4.0 '1 entry-level conditions for emergency and abnormal operating procedures (f a

. -. ,= _ __

Source Range Monitor (SRM) System (215004) ePn LSRO SRO NOTE-NUM KNOWLEDGE A 100 AbilitgTEM controls includingto predict and/or make changes in paraneters associated with operating the

. SRM SY A 101 Detector position

• 2.6 3.1 A 102 Reactor power indication

• 2.6 3.7 A 103 RPS status

• 2.6 3.5 A 104 control rod block status

• 3.0 3.5 4 A 105 SCRAM, rod block, and period alarm trip setpoints

• 2.8 3.8 A 106 Lights and alarna 2.0 3.1 1 A 200 Ability to a) predict the impacts of the following on the SRM SYSTEM, and b) based on those those predictions, abnornet condit ions or operationsuse procedures to correct, or mitigate the consequences of

• 2.5 2.9 A 201 Power supply degraded A 202 SRM inop condition

• 3.6 3.7.

A 203 Stuck detector 2.1 3.3 - 1 A 204 Up s~ ale and downscale trips 2.3 3.7 1

?

A 205 Faulty or erratic operation of detectors / system 2.3 3.5 1 A 206 Failed recorder 2.3 2.5 1 A 300 Ability to monitor automatic operations of the SRM SYSTEM including A 301 Meters and recorders 2.0: 3.2 1 A 302 Annunciator and alarm signals 2.0 3.3 - 1 A 303 RPS status 2.0 3.5 - 1'-

A 3D4 control rod block status ' 2.3 3.6 1 A 400 Ability to manually operate and/or monitor in the control room A 401 SRM count rate and period 2.0 3.8 1 A 402 SRM recorder 2.0 3.1 1 A 403 CRT displays: Plant- Spec i f i c - 2.0 2.7 1 A 404 SRM drive control switches 2.0 3.6 1 A 405 SRM back panel switches, neters, and indicating lights 2.0 3.2 1 A 406 Alarms and lights 2.0 3.1 1 A 407 verification of proper f unctioning/ operability

• 3.1 3.6 K 100 Knowledge SYSTEM and of thethe fol @lowingysical connections and/or cause effect relationships between SRM K 101 Reactor protection system

• - 3.1 3.7 -

K 102 Reactor manual control 3.3 3.4 -

K 103 Rod control and information system: Plant-Specific

• 3.0 3.0 K 104 Process computer / performance monitoring system (SPOS/ERIS/CRIDS/GOS): -2.3 2.6 1 Plant-Specific K 105 Display control system: Plant-Specific 2.3 3.0 1.

K 106 Reactor vessel 3.3 2.8 K 200 Knowledge of electrical power supplies to the following K 201 SRM channels / detectors 2.0 2.8 1 ,

K 202 Detector drive modules 1.8 2.3 1 K 203 Detector drive module control 1.8 2.1' 1 K 300 Knowledge of the ef fect that a loss or malfunction of the SRM SYSTEM will have on the following K 301 RPS

• ~ 3.1 3.4 r K 302 Reactor manual contrott Plant Specific

• 3.3 3.4 K 303- Rod control and infornation system: Plant-Specific *

. 3.1 3.3 i

-t K 3D4 Reactor power and indication

• 3.3 3.7 ,

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A K 400 Knowledes of SRM SYSTEM design feature (s) snd/or interlocks which provide for the following

• 3.6 3.7 K 401 Rod withdrawal blocks

• 3.1 3.5  ;

K '402 Reactor SCRAM signals l' K 403 Gamma conpensation 2.6 2.4 2 K 4 04 Changing detector position 3.0 2.9 s t

2.0 2.5 1 K 405 Atarm seal-in ,

• 2.6 3.2 ,'

K 406 IRM/SRM interlock K 500 Knowledge of the operational applications of the following concepts as they apply to SRM SYSTEM K 501 Detector operation

• 2.6 ~ 2.6 2.5 2.2 2 K 502 Gamma discrimination

• 2.6 2.8 K 503 Changing detector position K 600 Knowledge of the effect that a toss or malfunction of the following will have on the SRM SYSTEM 2.1 3.3 1 K 601 RPS K 602 24/48 volt D.C. power 2.1 3.3 1 2.1 2.4 1 K 603 Detector drive motor 2.1 2.9 .1 K 604 Detectors K 605 Trip units 2.3 2.8 1 K 606 Recorder 2.1 2.2 1 1 Knowledge of operator responsibilities during all rodes of plant operation 1.8 3.9 1 SG SG 2 Knowledge of system status criteria which require the notification of plant 2.5 3.6 ->

personnel ,

SG 3 Knowledge of which events related to system operation / status should be reported to 2.3 4.0 1 outside agencies ,

SG 4 Knowledge of system purpose and/or function

• 3.8 3.4 SG S Knowledge of limiting conditions for operations and safety limits .

• 4.1 3.9 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 4.1 3.7 operations and safety limits SG 7 Knowledge of purpose and function e mjor system components and controls

• 4.0 - 3.5 SG B Knowledge of the annunciator alarms and indications, and use of the response 2.1 3.4 1 i

instructi ons SG 9 Ability to locate and opersite components, including local controts

• 2.5 3.3 ,

SG 10 Ability to explain and apply all system limits and precautions 2.0 3.4 1 SG 11 Ability to recognize indications for system operating parameters which are

• 4.1 3.9 i entry level conditions for technical specifications .

SG 12 Ability to verify system alarm setpoints and operate controts identified in the 1.3 3.3 1 l

alarm _ response manual SG 13 Ability to perform specific system and integrated plant procedures during alt modes 1.3 3.3 1 ,

of operation SG 14 Ability to perform without reference to procedures those actions that require 1.3 3.2 1 immediate operation of system components or controls SG 15 Ability to recognize abnornet indications for system operating parameters which are

• 3.0 3.9  :

entry level conditions for emergency and abnormal operating procedures

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Fire Protection System (286000)

. APP LSRO S20 -NOTE NUM KNOWLEDGE I

-1 A 100 Ability to predict and/or make changes in parameters associated with operating the '

FIRE PROTECTION SYSTEM controls including O A '101 System pressure

!.5 1.5 2.9 2.5 1

1 A 102 System flow 1.5 3.1 1 A 103 Fire doors 1.3 3.1 1 A 104 Fire danpers 1.5 3.2 1 A 105 System lineups 1.3 3.0 1' A 106 Tank pressure: Piant-Specific A 200 Ability to a) predict the impacts of the following on the FIRE PROTECTION SYSTEM, and b) based on those predictions, use procedures to correct, or mitigate the 4 consequences of those abnormal conditions or operations t System logic failure: Plant Specific 1.3 2.9 1 A 201 D.C. distribution failure: Plant-Specific 1.6 2.7 1

-A 202 '

1.6 3.0 1-A 203 A.C. distribution failure: Plant-Specific A 204 Applicable component cooling water system failure: Plant-Specific 1.3 : 2.4 1 Fire protection diesel trips 1.3 3.3 1 A 205 A 206 Low fire main pressure: Plant Speelfic 1.3 3.2 1.

A 207 Inadvertent system iaitiation 1.3 2.9 1 A 208 Failure to actuate when required 1.3 3.3 1 A 209 valve closures: Plant-Specific 1.3 -2.8 1 A 210 valve openings: Plant Specific 1.3 2.7 1 Pump trips: Plant-Specific 1.3 3.2 1 A 211 A 212 tow diesel fuel supply: Plant Specific 1.3 3.3 '1-A 300 Ability to monitor automatic operations of the FIRE PROTECTION SYSTEM including ,

~ 1.3 3.4 - 1

( A 301 Fire water pmp start A 302 Fire main pressure 1.3 3.2 1 .

1.3 3.3 1  ;

A 303 Actuation of fire detectors A 304 System initiation 1.5 3.3 1 1.5 3.1 1 A 305 Fire doors A 306 Fire danpers 1.3 3.1 1 A 400 Abillty to manually operate and/or monitor in the control room A 401 System alarms and indicating lights 1.1 - 3.2 1 l

A 402 Applicable conponent cooling water system: Plant Specific 1.1- 2.5 1 A 403 Applicable conponent cooling water pressure 1.1 2.5 1 A 404 Fire main pressure: Plant-Specific 1.1 2.8 1 i

1.1 3.3 1 A 405 Fire pump A 406 Fire diesel 1.1 3.4 1 K 100 - Knowledge of the physical connections and/or cause-effect relationships between FIRE PROTECTION SYSTEM and the following K 101 Conponent cooling water systems 1.6 - 2.8 1 ~

Isolation condenser: Plant Specific 1.3 3.8 1- ,

K 102 K 103 Reactor water levels Plant Specific- 2.0 3.0 1 K 104 D.C. electrical distribution: Plant-Specific 1.6!-2.6 1 i K 105- Main generator hydrogen system: Plant Specific 1.3 3.1 1 ,

K 106 Auxiliary (boiler) steam system: Plant specific 1.3 2.3 '1 A.C. power supplies 1.6 2.9 1 K 107

[

'\ K 108 Intake canals: Plant Specific 1.1 3.0 '1 l K 109 Emergency generator rooms: Plant-specific 1.5 3.3 1 l

i 9

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I Hsin generator exciter: i 4nt. Specific 1.1 2.8 .1 K '110 K 111 Screen wash system: Plant-Specific 1.1 2.5' 1 l K 200 Knowledge of electrical power supplies to the following {

K 201 Fire protection supervisory circuits: Plant-Specific 1.1 2.5 1 d K 202 Pumps 1.5 3.1 1 K 203 Fire detection system: Plant-Specific 1.1 2.7 1 K 300 Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on the following ,,

f K 301 The obliity to detect fires 2.3 3.4 1 K 302 Personnel protection

• 2.5 3.4 K 303 Plant protection 1.3 3.8 K 400 Knowledge of FIRE PROTECTION SYSTEM design feature (s) and/or interlocks which provide for the following K 401 Adequate supply of water for the fire protection system 1.8 3.6 - 1 K 402 Automatic system initiation 2.1 3.5 .1 K 403 Maintenance of fire header pressure 1.6 3.4 i K 404 Personnet safety during halon and/or carbon dioxide system actuation 2.3 ' 3.7 1 K 405 Fire protection capability during loss of off-site power 2.3 3.8 1 K 406 Fire suppression capability that does not rely on the displacement of oxygen 1.5 3.4 1 (Halon): Plant-Specific K 407 Diesel engine protection 1.3. 3.3 - 1 K $00 Knowledge of the operational applications of the following concepts as they apply to FIRE PROTECTION SYSTEM K 501 Effect of carbon dioxide on fires 2.3 2.7 1 K 502 Effect of Halon on fires: Plant-Specific 2.3 2.6 1 K 503 Effect of water spray on electrical components

• 2.5 3.4 K 504 valve operation 1.3 2.9 1 K 505 Dieset operations l'3

. 3.1 1 K 506 Heat detection 1.5 2.7 1 K 507 Smoke detection 1.5 2.7 1 K 508 Gas refrigeration: Plant Specific 1.3 2.5 1' K 600 Knowledge of the effect that a loss or malfunction of the follcwing hill have on the FIRE PROTECTION SYSTEM K 601 A.C. electrical distribution: Plant Specific 1.6 3.1 1 K 602 D.C. electrical distribution 1.6 2.9 1 K 603 Applicable component cooling water system: Plant-Specific 1.1 2.5 1 K 604 Diesel fuel transfer system: Plant Specific 1.1 3.0 1 K 605 Screen wash system: Plant Specific 1.1 2.6 - 1 SG 1 Knowledge of operator responsibilities during all modes o M. ant operation 1.6 4.0 1 SG 2 Knowledge of system status criteria which require the notification of plant 1.6 3.8 1 personnel SG 3 Knowledge of which events related to system operation / status should'be reported to 1.6 4.3 .- 1 outside agencies SG 4 Knowledge of system purpose and/or function

• 2.5 - 3.9 -

SG 5 Knowledge of limiting conditions for operations and safety timits

• 2.1 3.9. 4 SG 6 Knowledge of bases in technical specifications for timiting conditions for

• 2.3' 3.8 4 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 2.5 3.9 SG 8 Knowledge of the annunciator alarms and indications, and use of the response- 1.3 3.6 ,

instructions SG 9 Ability to locate and Operate components, including local- controls 1.5 - 3.8 1 SG 10 Ability to explain and apply all system limits and precautions 1.1 3.5 1 SG 11 Ability to recognize indications for system operating parameters which are 1.5 4.1 1 entry level conditions for technical specifications i

SG 12. ~ Ability to verify system starm sstpoints crd operate controts identified in the 1.1 3.4 1 alcrm response manual SG 13 Ability to perform specific system and integrated plant procedures during att modes 1.1 . '3.3 1 of operation ,

1.6' 3.4 '

O - SG 14 Ability to perform without reference to procedures those actions that require 1 h -tmadiate operation of system components or controts SG 15 Ability to recognize abnormal indications for system operating parameters which are 1.8' 4.2 1 entry-level conditions for emergency and abnormat operating procedures 2

- =- - -

Fuel Hsndling Equipment (234000)

APP LSRO SRO NOTE NUM KNOWLEDGE A '100 Ability to predlet and/or make changes in parameters associated with operating the r FUEL HANDLING EQUIPMENT controls including i A 101 Spent fuel pool level

• 4.6 3.4 .{

A 102 Refuel floor radiation levels / airborne levels

• 4.5 3.8 l A 103 Core reactivity level

• 4.6 3.9 A 200 Ability to a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT, and b) based on those predictions, use procedures to correct, or mitigate the consequences of those abnormal conditions or operations A 201 Interlock failure

• 4.6 3.7  !

4.6 3.6 A 202 Loss of refueling platform air system A 203 Loss of electrical power

• 4.6 3.1 A 300 Ability to monitor automatic operations of the FUEL HANDLING EQUIPMENT including A 301 Crane / refuel bridge movement: Plant

• Specific 4.6 3.6 A 302 Interlock operation

• 4.6 3.7 i A 400 Ability to manually operate and/or monitor in the control room A 401 Neutron monitoring system

• 4.1 3.9 A 402 control rod drive system

• 4.1 3.7 K 100 Knowledge of the physical connections and/or cause-effect relationships between FUEL HANDLING EQUIPMENT and the following K 101 Fuel 4.8 3.7 K 102 Core components

• 4.8 3.3 l K 103 Spent fuel cask 4.8 2.9 K 104 Reactor manual control system: Plant-Specific

• 4.8 3.6 K 105 Reactor vessel components: Plant-Specific

• 4.8 3.3' K 106 RC & IS: Plant-Specific 0.0 1

\

K 107 fuel transfer tube system: Mark-III

• 3.1 3.4 K 108 Fuel pools configuration: Mark-Ill 3.1 3.0 [

K 109 fuel pool ventilation: Plant specific

• 4.1 2.9 K 200 Knowledge of electrical power supplies to the following K 300 Knowledge of the effect that a loss or malfunction of the FUEL HANDLING EQUIPMENT will have on the following ,

K 301 Reactor manual control system: Plant-Specific

• 4.3 3.3

• K 302 RC & IS: Plant Specific 0.0 1 K 303 Fuel handling operations

• 4.5 3.8 K 304 Core modifications / alterations 4.5 3.8 K 400 Knowledge of FUEL HANDLING EQUIPMENT design feature (s) and/or interlocks which provide for the following K 401 Prevention of core alterations during control rod movements *' 4'. 5 4.1 K 402 Prevention of control rod movement during core alterations

• 4.5 4.1 K 403 Protection against inadvertently lifting radioactive components out of the water

• 4.5 : 4.2 K 404 Movement of the spent fuel cask only over designated areas: Plant-Specific

• 4.5 3.3' K 405 Movement of fuel via fuel transfer tube: Mark-!!!

• 3.1 3.8 K 500 Knowledge of the operational applications of the following concepts as they apply to FUEL HANDLING EQUIPMENT K 501 Crane / hoist operation

• 4.5 3.4 K 502 Fuel handling equipnent interlocks

• 4.5 3.7 K 503 Water as a shield against radiation

• 4.5 3.4 K 504 Spent fuel pool design 4.5 3.1 K 505 Fuel orientation

• 4.5 3.7 j i

L i

i K 600 - Knowledge of the effset that a loss or malfunction of the following will have on the FUEL HANDLING EQUIPMENT

• ~ 4.5 3.2 K 601 Electrical power K 602 Reactor manual control system: -Plant Specific

• 4.5 3.5 r-f K 603 RC & IS: Plant-Specific 0.0 1 ,

K 604 Refueling platform air system: Plant Specific

• 4.5 3.7 *

• 3.8 3.3 ,

K 605- Upper fuel pool water inventory: Mark-111

• . 3.8 3.6 K 606- Fuel transfer tube interlocks: Mark-Ill .i

• 3.4- -- '

K 607 Fuel pool ventilation: Plant Specific 4.5

• 4.5 3.8.

SG 1 Knowledge of operator responsibilities during att modes of plant operation SG 2 Knowledge of system status criteria which require the notification of plant

• 4.5 3.9 -

personnel SG 3 Knowledge of which events related to system operation / status should be reported to

• 4.5 4.5 ,

outside agencies SG 4 Knowledge of system purpose and/or function

• 4.5 3.6 SG 5 Knowledge of limiting conditions for operations and safety limits

• 4.5 4.1 6 SG 6 Knowledge of bases in technical specifications for limiting conditions fer

• 4.5 3.7 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 4.5 3.7 8 Knowledge of the annunciator alarms and indications, and use of the response

• - 4.5 3.4 SG-instructions '

SG 9 Ability to locate and operate components, including local controls

• ' 4.5~ 3.6 SG. 10 Ability to explain and apply all system limits and precautions

• 4.5 3.5 ,

Ability to recognize indications for system operating parameters which are

• 4.7 3.9 SG 11 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the

• 4.5 3.3 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during att modes 4.5 3.3 of operation SG 14 Ability to perform without reference to procedures those actions that require

• 4.5 3.5 f immediate operation of system conponents or controls ,

SG 15 Ability to recognize abnormal indications for system operating parameters which are

• 4.7 - 4.1 .

entry-level conditions f or emergency and abnormat operating procedures 4

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Plent Vsntila' tion System (238000)

NUM KNOWLEDGE APP LSRO SRO NOTE l

~

A 100 Ability to predict and/or make changes in parameters associated with operating the O' PLANT VENTILATION SYSTEM controls including l U A 101 Filter differential pressure 1.8 2.2 1 A 102 Fan differential pressure 1.8 2.2 1 l

1.8 2.4 1-A- 103 Area temperatures l A 200 Ability to a) predict the impacts of the following on the PLANT VENTILATION SYSTEM, and b) based on those predictions, use procedures to correct, or mitigate the consequences of those abnormal conditions or operations A 201 Hlgh drywell pressure: Plant-Specific 1.8 3.4 1 A 202 Low reactor water level: Plant-Specific 1.8 3.6 1 A 203 Loss of coolant accident: Plant-Specific 2.1 3.7 1 A 204 High radiation: Plant-Specific

• 2.8 3.8 A 205 Extreme outside weather conditions: Plant-Specific 1.8 2.7 1 A 300 Ability to monitor automatic operetions of the PLANT VENTILATION SYSTEM including A 301 Isolation / initiation signals G 2.1 3.8 1 A 400 Ability to manually operate and/or monitor in the control room A 401 Start and stop fans 1.8 2.9 1 A 402 Area temperature 1.8 2.8 1 K 100 Knowledge of the physical connections and/or cause-effect relationships between PLANT VENTILATION SYSTEM and the following K 101 A.C. electrical 2.6 2.6

'* 2.8 3.4 K 102 Secondary containment K 103 Standby gas treatment 2.8 3.7 K 104 Applicable component cooling water system: Plant-Specific 2.1 2.6 1-K 105 Process radiation monitoring system

• 2.8 3.6 K 106 Plant air systems 2.5 2.7 K 200 f nowledge of electrical power supplies to the following K 201 Reactor building supply and exhaust fans: Plant Specific 2.5 2.4 2 K 202 Auxiliary building supply and exhaust fans (turbine building / radwaste building): 1.8 1.9 1 Plant-Specific K 300 Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION SYSTEM wiLL have on the following K 301 Secondary containment temperature: Plant-Specific

• 2.6 3.0 K 302 Reactor building temperature: Plant Specific

• 2.6 3.1-K 303 Auxiliary building temperature: Plant Specific 1.8 2.5 1 K 304 secondary containment pressure: Plant-Specific

~

2.6 3.3 K 305 Reactor building pressure: Plant-Specific 2.6 3.3 K 306 Auxiliary building pressure: Plant-Specific 1.S 2.4 1 K 400 Knowledge of PLANT VENTILATION SYSTEM design feature (s) and/or interlocks which provide for the following K 401 Automatic initiation of standby gas treatment system

• 2.8 3.9 K 402 ' Secondary contairment isolation 2.8 3.8 K 403 Automatic starting and stopping of fans

• 2.6 2.9 K 500 Knowledge of the operational applications of the following concepts as they apply to PLANT VENTILATION SYSTEM K 501 Airbo>ne contamination control

• 2.8 3.2 K 502 Differential pressure control ~ 2.8 ~ 3.4 K 503 Terrperature control

• 2.6 . 2.6-K 600 Krowledge of the effect that a loss or malfunction of the following will have on the PLANT VENTILATION SYSTEM

_. -_--_.-L_ _ .__:___ _

• 2.6 - 2.7 K 601 A.ti etsetrical

^2.3 2.5 1 KL 602 Applicable conponent cooling water system: Plant Specific K 603 Plant air systems 2.3 ' 2.7_ 1.

SG 1 Knowledge of operator responsibilities during all modes of plant operation 2.1 3.3 1 .[

?

SG 2 Knowledge of system status criteria which require the notification of plant

• 2.5 - 3.6 personnel SG 3 Knowledge of which events related to system operation / status should be reported to

• 2.5 4.0 outside agencies h, SC 4 Knowledge of system purpose and/or function

• 2.8 3.4 SG 5 Knowledge of limiting conditions for operations and safety limits

• 2.8 3.4

• 2.8 3.1 SG 6 Knowledge of bases in technical specifications for limiting conditions'for operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 2.8 3.4 SG 8 Knowledge of the annunciator alarms and indications, and use of the response 2.0 3.0 -1 instructions SG 9 Ability to locate and operate components, including local controls 2.0 3.0 .1 SG 10 Ability to explain and apply att system limits and precautions 2.1 2.8 '1 Ability to recognize indications for system operating parameters which are

• - 2.6 3.6 SG 11 entry-level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.8- 2.9 1 alarm response manual SG 13 Ability to perform specific system and integrated plant proceoures during all' modes 1.8 , 2.91 1 of operation 50 14 Ability to perform without reference to procedures those actions that require . 1.8 2.9 ' 1 inmediate operation of system conponents or controls ,

SG 15 Ability to-recognize abnormat indications for system operating parameters which are 2.0 3.6 .1 entry-Level conditions for emergency and abnormat operating procedures k

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i Rzdiation Monitoring System (272000) j APP LS20 SRO NOTE KUM KNOWLEDGE l

)

A 100 Ability to predict and/or make changes in parameters associated with operating the RADIATION MONITORING SYSTEM controls including Lights, alarms,' and indications associated with normal operations 2.0 3.2 1

% A 101 2.0 2.9 1 A 102 Lights, alarms, and indications associated with surveillance testing l I

A 200- Ability to a) predict the irnpacts of the following on the RADIATION MONITORING SYSTEM, and b) based on those predictions, use procedures to correct, or mitigate the consequences of those abnormal conditions or operations

.4

• 3.1 4.1 A 201 Fuel element failure A 202 Reactor protection system power failure 2.3 3.6 1 A 203 A.C. electrical failure 2.8 - 3.1 0.C. electrical failure

• 2.5 2.8 A 204 ,

A 205 Loss of dilution steam 2.0 2.6 .1 A 206 Downscale trips 2.3 2.9 1 A 207 Hydrogen injection operation: Plant-Specific 2.0 2.8 1:

A 208 offgas system failure 2.0 3.1 1 A 209 Low fuel pool level

• 3.1 3.3 A 210 Loss of coolant accident 3.0 4.1 A 211 Leakage and/or breaks from contaminated systems to atmosphere or to other process 2.5 3.7 systems A 212 Refuel floor handling accidents / operations

• 3.1 4.0 A 213 Low reactor water level during refueling operations *

' 3.1 3.8 A 214 Loss of, or inadequate, shielding

• 2.6 3.5 A 215 Maintenance operations 2.3 2.7 1 A 216 Instrment malfunctions 2.0 2.9 1-A 300 Ability to monitor automatic operations of the RADIATION MONITORING SYSTEM including ,

A 301 Main steam isolation indications 2.0 3.9 - 1 r

A 302 offgas system isolation indications 2.0 3.7 1 A 303 Liould radweste isolation indications 2.0 3.5 1 A 304 Radwaste handing interlocks 2.0 2.8 1 A 305 Refuel floor overhead crane operation interrupt: Plant-Specific

• 2.5 3.1 A 306 ventilation system isolation indications 2.0 3.4 1- >

A 307 Recorder indications 2.0 2.9 1' A 308 Meter indications 2.3 2.9 1 A 309 Containment isolation indications 2.0 3.5 ~1 ,

A 310 Lights and alarms 2.3 3.2 1 A 311 Circulating water system blowdown isolations: Plant specific 2.0 2.7 1 A 400 Ability to manually operate and/or monitor in the control room A 401 Recorder indications 2.0 2.9- 1. -

A 402 Meter indications 2.0 3.0 . 1-A 403 Power supply status indicators 2.0 2.6 1 A 404 SPDS/ERIS/CRID/GOS 2,0 2.7 -1 2.0 ' 3;7 ' 1 A 405- Convert process radiation monitor readings to offsite release rates: Plant-Specific A 406 Manually trip process radiation monitor logic 2.0 3.2 1  :

K 100 Knowledge of the physical connections and/or cause-effect relationships between RADIATION MONITORINu SYSTEM and the following K 101 Main steam system 2.0 3.8 1 K 102 offgas system (augmented offgas): Plant-Specific 2.0 3.5 1 K .103 Stack gas: Plant Specific 2.0 3.6 1.

K 104 -Applictble component cooling water system 2.0 2.9 1 K 105 Radw2ste system 2.0 ' 3.1 1 ,

K 106 Reactor building ventilation system: Plant-Specific

• 2.8 3.3 K 107 Isolation condenser: Plant Specific 0.0 0.0 1 K 108 Reactor protection system 2.3 3.9 1 K 109 Primary containment isolation system 2.0 3.8 1 K 110 Reactor building refuel floor . Plant-Specific

• 3.0 3.6 K 111 Reactor building overhead crane: Plant-Specific 2.6 2.4 2 K 112 Reactor building

• 2.8 3.2 K 113 Turbine building 2.0 3.0 1 K 114 Radwaste building: Plant-Specific 2.0 2.8 1 K 115 Filter building: Plant-Specific 2.0 3.0 1 K 116 Process computer 2.0 '2.3' 1 K 117 SPDS/ERIS/CRIDS/CDS: Plant-Specific 2.0 2.7 '1 K 118 Primary containment / containment building: Plant-Specific 2.0 3.1 1 K 119 Drywell

• 2.5 3.2-K 120 Auxiliary building: Plant-Specific 2.0- 3.0 1 K 121 Circulating water: Plant-Specific 2.0 2.4 1  ;

K 122 Fuel building: Mark-!!! 2.0 3.4 1 K 123 continuous air monitoring: Plant-Specific 2.5 3.3 K 200 Knowledge of electrical power supplies to the followir's K 201 Main steamline radiation monitors 2.0 2.8 1 K 202 offgas radiation monitoring system 2.0 2.8 1 K 203 Stack gas radiation monitoring system 2.0 2.8 1 K 204 Process liquid radiation monitoring system 2.0 2.5 1 K 205 Reactor building ventilation monitors: Plant-Specific

• 2.5 2.9 O- 2.5 2.2 2 K 206 Area radiation monitors K 207 Control room ventilation monitors: Plant-Specific 2.5 2.4 2 K 300 Knowledge of the effect that a loss or malfunction of the RADIATION MONITORING SYSTEM will have on the following K 301 Station liquid effluent release monitoring

• 2.5 3.8 K 302 Station gaseous effluent release monitoring

• 2.5 3.8 ,

K 303 Station area radiation monitoring 3.0 3.4 K 304 Main steam system 2.0 3.8 1 K 305 Offgas system 2.1 3.7 1 K 306 Reactor building ventilation: Plant-Specific

• 3.0 3.6 K 307 Reactor building overhead crane operation: Plant-Specific

• 2.6 3.0 K 308 Auxiliary building ventilation: Plant-specific 2.0 3.3 1 K 309 Radweste building ventilation: Plant-Specific 2.0 3.1 1-K 310 Control room ventilation: Plant-Specific

• 2.6 3.3' K 400 Knowledge of RADIATION MONITORING SYSTEM design feature (s) and/or. interlocks which provide for the following K 401 Redundancy 2.5 - 2.8 -

K 402 Automatic actions to contain the radioactive release in the event that the

• 3.0 4.1 predetermined release rates are exceeded K 403 Fall safe tripping of process radiation monitoring logic during conditions of

• 2.5 3.9 instrunent f anure .I i

K 500 Knowledge of the operational applications of the following concepts as they apply to ,

RADIATION MONITORING SYSTEM l

-( K 501 Hydrogen injection operation's effect on process radiation indications: 2.0 3.5- 1 I

Plant Specific l 1

1 i

K 300 Knowledet of the effset that a loss or malfunction of the following will have on the RADIATION MONITORING SYSTEM K 601 Reactor protection system

• 2.6 3.2 K 602 D.C. power

• 2.6 2.7 g

K 603 A.C. power 2.8 3.0 K 604 Process ccwputer 2.3 2.2 1 K 605 SPDS/ERIS/CRID/ GDS: Plant-Specific 2.0 2.4 -1

• 2.5 2.6 K 606 Continuous air monitoring: Plant. Specific ,

SG 1 Knowledge of operator responsibilities during all modes of plant operation 2.2 3.9- '1' SG 2 Knowledge of system status criteria which require the notification of plant 2.4 3.9 1 personnel SG 3 Knowledge of which events related to system operation / status should be reported to 2.4 4.5 1 outside agencies SG 4 Knowledge of system purpose and/or function

• 2.8 3.4 SG 5 Knowledge of limiting conditions for operations and safety limits

• 2.8 3.9 SG 6 Knowledge of bsses in technical specifications for limiting conditions for -

• 3.0 3.7 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 2.8 3.5 SG 8 Knowledge of the annunciator alarms and indications, and use of the response -2.2 3.5 1 instructions SG 9 Ability to locate and operate components, including local controts 1. 6 ' 3.5 1 SG 10 Ability to explain and apply all system limits and precautions 2.0 3.3 1-SG 11 Ability to recognize indications for system operating parameters which are'

• 2.6 4.2 entry-Level conditions for technical specifications SG 12 Ability to verify system alarm setpoints and operate controls identified in the 1.6 3.3 1 alarm response manual SG 13 Ability to perform specific system and integrated plant procedures.during all modes 1.6 3.4 1 of operation SG 14 Ability to perform without reference to procedures those actions that require 1.6 3.4 1-immediate operation of system components or controls

.O SG 15 Ability to recognize abnormal indications for system operating parameters which are 2.4 4.2 1 entry-level conditions for emergency and abnormal operating procedures l

1

= - - , ,-

Fuel Pool Cooling cnd Clsinup (233000)

APP LSRO SRO . NOTE NUM KNOWLEDGE A 100 Ability to predict and/or make changes in parameters associated uith operating the FUEL PDOL COOLING AND CLEANUP controls including ,

f" . 1 A 101 Surge tank level

• 3.3 2.9  ;

• 3.3 3.1 A 102 Pool level A 103 Pool temperature'

• 3.3 '3.3 i A 104 Punp discharge pressure

• 3.1 2.5 .

3.0 2.3 2 A 105 Filter / demineralize differential pressure A 106 System flow 3.0 2.4 2 A 107 System temperature 3.1 2.8 A 103 Pool chemistry 3.0 2.4 2 A 109 Pool clarity

• 3.3 2.6 A 110 Pool activity levels

• 3.1 2.6 Suppression pool chemistry: BWR-6 2.1 2.9 1 A 111 A 200 Ability to a) predict the impacts of the following on the FUEL POOL COOLING AND CLEANUP, and b) based on those predictions use procedures to correct, or mitigate the consequences of those abnormal conditio,ns or operations High pool-level 3.3 2.9 A 201 A 202 Low pool level

• 3.3 3.3 A 203 Low surge tant level /high level

• 3.0 3.0 A 204 Pump trip

• 3.0 2.7 A 205 Valve closures 3.0 2.5 A 206 Valve openings

• 3.0 2.5 A 207 High fuel pool temperature 3.3 3.2 A 208 Closed cooling water failure

• 3.1 3.1 A 209 A.C. electrical power failures 3.1 2.9 A 210 Refueling bellows seat high flow 3.3 3.3 Fuel pool gate seal high flow

• 3.3 3.2 A 211 A 212 High filter / demineralizer differential pressure 3.0 2.4 2 A 213 Low filter / demineralizer differential pressure 3.0 2.2 2 A 214 Low system flow 3.0 2.3 2 3.1 2.9 A 215 High system tenperature A 216 Loss of coolant accident signal

• 3.1 2.8 A 217 Fuel transfer tube drain tank high level / low level BWR*6 2.1 2.8 2 A 218 Low pool clarity 3.3 2.7 Inadequate system / pool chemistry 3.0 2.8 A 219 A 300 Ability to monitor automatic operations of the FUEL POOL COOLING AND CLEANUP' including A 301 valve operation

• 2.5 2.5 r

A 302. Ptsnp trip (s)

• 2.5 2.6 A 303 System indicating lights and alarms 2.6 2.6 A 400 Ability to manually operate and/or monitor in the control room A 401 System lights and alarms

• 2.6 2.6 A 402 System lineups

• 2.6 2.5 A 403 System flow 2.6 2.4 2

• 2.8 3.1 A 404 Pool level A 405 Pool temperature

• 2.8 3.1

% A 406 System tenperature

• 2.6 2.6 ,

2.5 2.3 2 A 407 System pressures .

2.5 2.2 2

.A 408 system differentist pressures 2.3 2.2 1 A 409 Pump operation

• 2.5 2.6 A 410 Tank levels A 411 Closed cooling water tenperature 2.3 2.5 1 ,'

( K 100 sical connections and/or cause-effect relationships between FUEL KnowledgeofthegANUPandthefollowing POOL COOLING AND Shutdown cooling system: Plant specific

• 3.3 2.9 K 101 K 102 Residual heat removal system: Plant Specific

• 3.3 3.0 K 103 Condensate storage tank 3.3 2.3 2 K 104 Process sampling system 3.3 2.0 2 K 105 Plant air systems 3.1 2.2 2 3.1 2.3 2 K 106 A.C. electrical power K 107 Condensate system: Plant-Specific 3.1 2.2 2 3.3 2.5 K 108 Condensate transfer K 109 Component cooling water systems 3.1 2.6 K 110 Containment drainage system: Plant

• Specific 3.1 2.3 2 Reactor building drainage system: Plant-Specific 3.0 2.4 . 2 K 111 K 112 Radwaste system 3.0 2.6 K 113 Suppression pool cleanup system: Plant-Specific 2.6 2.6 K 114 Reactor building ventilation

• 3.1 2.5 K 115 Storage pools

• 3.3 2.9 K 116 Emergency cooling water systems: Plant-Specific

• 3.3 2.8 K 200 Knowledge of electrical power supplies to the following Fuel pool cooling punps 3.0 2.2 2 K 201

• 3,0 2.9 K 202 RHR ptsnps K 300 Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLIG AND CLEANUP will have on the following Fuel pool temperature

• 3.3 3.4 K 301 K 302 Fuel pool water level 3.3 3.2 K 303 Fuel pool water clarity 3.3 2.8 K 304 Fuel pool water chemistry

• 3.3 - 2. 6 K 305 Fuel pool water fission product concentration

• 3.3 2.8

• 3.3 3.2 K 306 Area radiation levels .

K 307 Suppression pool chemistry: Plant-Specific 2.6 2.9 K 308 Refueting operations

• 3.3 3.5 K 400 Knowledge of FUEL POOL COOLING AND CLEANUP design feature (s) and/or interlocks which provide for the following K 401 Redundancy

• 3.1 2.6 '

K 402 Poot clarity 3.3 2.6 K 403 Maintenance of adequate pool tenperature 3.3 - 3.1 K 404 Overpressure protection for fuel pool cooling system filter 2.8 2.1 2 K 405 Net positive suction head requirements for fuel pool cooling pumps 2.8 2.2 2 K 406 Maintenance of adequate pool level

• 3.3 3.2

• K 407 Supplemental heat removat capability

• 3.1 2.9 K 408 Pool cooling during loss of coolant accident: BWR-6

• - 2.6 2.8-K 409 Maintenance of filter /demineraliter precoat during low flow conditions 2.6 2.4 2 K 500 Knowledge of the operational applications of the fo(lowing concepts as they apply to FUEL P WL COOLING AND CLEANUP K 501 Heat removal mechanisms

• 3.1 2.7 K 502 Pump cavitation 2.8 2.2 2

K 503 spent' fuel decay hsat stneration

• - 3.3 ' 2.8 i K ~ 504 Demineralizar lon exchenge 2.8 2.2 2 K 505 Mechanical filtration operation 2.8 2.2 2 K 506 Maxinum normal heat load

• 3.1 2.7

• 3.1 2.8 K 507 Maxinum (abnormal) heat load K 600 Knowledge of the effect that a loss or malfunction of the following will have on the FUEL POOL COOLING AND CLEANVP K 601 A.C. electrical power

• 3.0 2.7 ,'

• 3.3 2.5 K 602 Shutdown cooling system: Plant-Specific K 603 Residual heat removal: Plant specifir.

• 3.3 2.7 K 604 Condensate transfer 3.1 2.6 r (05 Condensate system 3.0 2.3 2 K 606 Condensate storage tanks 3.1 2.4 2 K 607 Corponent cooling water systems

• 3.1 2.8 ,

K 608 Plant air systems 2.8 2.4 2 K 609 Radwaste system 3.0 2.4 2 K 610 Reactor cavity seat f ailure 3.3 3.3 K 611 NSSSS/PCIS: Plant-Specific 2.8 2.6 SG 1 Knowledge of operator responsibilities during all modes of plant operation

• 2.6 3.4 SG 2 Knowledge of system status criteria which require the notification of plant

• 2.8 3.6 +

personnel

• - 2.8 4.1 SG 3 Knowledge of which events related to system operation / status should be reported to' outside agencies SG 4 Knowledge of system purpose and/or function

• 3.3 3.3 6 SG 5 Knowledge of limiting corxfitions for operations and saf ety limits 3.3. 3.4 SG 6 Knowledge of bases in technical specifications for limiting conditions for

• 3.3 3.4 operations and safety limits SG 7 Knowledge of purpose and function of major system components and controls

• 3.3 3.3

\

SG B Knowledge of the annunciator alarms and indications, and use of the response

• 3.3 3.2 itut ructions t SG 9- Ability to locate and operate components, including local. controls

• 3.3 3.2 SG 10 Ability to explain and apply all system limits and precautions

• 3.1 2.9 SG 11 Ability to recognite indications for system operating parameters which are *' . 3.3 ' 3.6 :

entry-level conditions for technical specifications

• 2.8 3.1 SG 12 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual SG 13 Ability to perform specific system and integrated plant procedures during all modes * -2.8 3.1 of operation SG 14 Ability to perform without reference to procedures those actions that require ~

• 2.6 3.1 imediate operation of system cocponents or controls SG 15 Ability to recognite abnormal indications f or system operating parameters which are

• 2.8 4.0 entry-level, conditions for emergency and abnormal operating procedures  ;

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$ttndby Gas Treatment System (261000)

NUM KNOWLEDGE APP. LSRO SRO NDTE A 100 Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including:

O A 101 System flow 1.6 1.6 3.1 3.2 1

1 A 102 Primary containment pressure A 103 off-site release tevels 2.1 3.8 1.

A 104 Secondary containnent differentall pressure

• 2.5 3.3 A 105 Primary containment oxygen level: Mark l&!! 1.5 2.9 1 A 106 Drywell and suppression chamber differential pressure: Mark-1 1.5 3.0 1.

A 107 SBGTS train tenperature 1.8 2.9 1 A 200 Ability to (a) predict the impacts of the following on the S1 ANDBY CAS TREATMENT ,

SYSTEM, and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations:

Low system flow 2.0 3.1 1 A 201 A 202 HiDh system flow 2.0 3.1 1' A 203 High train temperature 2.0 3.2 1 A 204 High train moisture content .2.0 . 2.7 1 A 205 Fan trips 2.3 3.1 1 A 206 Valve closures 2.3 2.9 1 A 207 A.C. electrical failure

• 2.5 2.8 A 208 0.c. electrical failure 2.5 2.7 ,

A 209 Plant air system failure 2.3 2.6 1 A 210 Low reactor water level: Plant-Specific

• 2.6 3.2 A 211 High containment pressure 1.8 3.3 1 A 212 High fuel pool ventilation radiation: Plant-Specific

• 2.6 3.4 A 213 High secondary containment ventilation exhaust radiation

• 2.5 3.7 A 214 High system pressure 2.0 3.2 1 A 215 High area radiation by refuel bridge: Plant-Specific

• 3.1 3.4 A 300 Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including:  ;

A 301 System flow 1.5 - 3.3 1 ,

1.5 3.1 1 A 302 Fan start A 303 Valve operation 1.5 2.9 1 A 304 System temperature 1.5 3.1 1 A' 400 Ability to manually operate and/or monitor in the control room:

A 401 off site release levels: Plant-Specific 1.5 4.0 1 1.5 3.1 1 A 402 Svetion valves A 403 Fan 1. 5 : 3.0 1 A 404 Primary contairment pressure 1.5 3.4 1-A 405 Drywell to suppression chamber / torus differentait pressure: Mark lM I 1.5 -- 3.2 1 A 406 Reactor building differentist pressure 1.6 3.6 -1 A 407 System flow 1.5 3.2 1 A 408 System temperature 1.5 2.7 1 A 409 Ventilation valves /danpers 1.6 2.7 1 K 100 Knowledge of the physical connections and/or cause-effect relationships between STANDBY CAS TREATMENT SYSTEM and the following:

Reactor building ventilation system

• 3.1 3.6

K 101 K 102 Orywell

• 2.8 3.4 :j

• 2.8 3.1  ;

K 103 Suppression pool I

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K 104 High radiation sampling system

• 2.8 2.3 K 105 Redwsste system: Ptsnt-Specific 2.1 2.4 1 ,

1.6 3.1 1

.K 106 High pressure coolant injection system: Plant Specific ,

• 2.5 3.2

. /* K 107 Elevated release stack K 108 Process radiation monitoring system

• 2.8 3.1 >

K 109 Primary containment isolation system 2.1 3.4 1 K 110 Plant air systems 2.1 2.3 1 K 111 Primary contairrnent pressure 1.6 3.3 1 -!

K 112 Primary contairvnent purge system Plant-Specific 2.0 3.2 1

'K 200 Knowledge of electrical power supplies to the following:

2.0 2.3 1' K 201 Fan power K 202 valve power 2.0 2.0 1 2.3 2.5 1 K 203 Initiation logic K 204 Heater power 2.0 1.9 i K 300 Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on the following:

secondary containment and environment differential pressrue

• 3.1 3.6 K 301

• 3.1 3.9 K 302 off site release rate K 303 Primary containment pressure: Mark-1&1l 1.6 ' 3.4 .

K 304 High pressure coolant injection system: Plant-Specific 1.5 3.1 1-

• 3.1 3.5 K 305 Secondary containment rediation/ contamination levels K 306 Primary containment oxygen content: Mark-I&ll 1.5 .3. 3 1 K 400 Knowledge of ST ANDBY GAS TREATMENT SYSTEM design f eature(s) and/or interlocks which provide for the following:

K 401 Automatic system initiation 3.1 3.8 '

K 402 Charcoal bed decay heat removal 2.3 2.8 - 1 O K 403 Moisture removal K 404 Radioactive particulate filteration 2.3 2.5 2.7 2.9 1

K 405 Fission product gas removal

• 2.8 . 2.8 2.3 2.6 1 K 406 Charcoal bed retention K 500 Knowledge of the operational applications of the following concepts as they apply to STANOBY CAS TREATMENT SYSTEM:

1.8 2.6 1 K 501 Heat removal mechanisms K 502 Air operated valves: Plant-Specific 1.6 .- 2.5 1 K. 600 Knowledge of the effect-that a loss or malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM:

• 2.5 3.0 K 601 A.C. electrical distribution

• 2.5 2.6 -

K 602 0.C. electrical distribution K 603 Emergency diesel generator system

• 2.5 - 3.1 K 604 Process radiation monitoring

• 2.8 3.1 K 605 Reactor protection system: Plant-Specific

• 2.6 3.2 K 606 Plant air systems 2.1 2.6 -1 K 607 Primary contalrunent atmosphere sampling system Plant-Specific 1.6 . 2.4 '1 -

K 608. Reactor vessel level: Plant-Specific

• 3.0 3.1 5 K 609 Primary containment high pressure: Plant-Specific 1.8 3.3 1 2.3 3.7. 1 SG 1 Knowledge of operator responsibilities during all modes of plant operation.

SG 2 Knowledge of system status criteria which require the notification of plant

• 2.5 3.7 personnel.

SG 3 Knowledge of which events related to system operation / status should be reported to

• 2.5 4.3

. outside agencies.

SG & Knowledge of system purpose and/or function.

• 3.3 3.7

SG 5 Knowledge of limiting conditions for operations and safety limits.

• 3.0 3.7 SG 6 Knowledge of basas in tschnical specifications for limiting conditions for

• 3.0 3.7 operations and safety limits.

SG 7 Knowledge of purpose and function of major system conponents and controls.

• 3.1 3.7 SG - 8 Knowledge of the annunciator alarms and indications, and use of the response 2.0 3.3 1 instructions. .

SG 9 Ability to locate and operate conponents, including local controls. 1.8 3.5 .1

. SG 10 Ability to explain and apply all system limits and precautions. 2.0 3.3 1 ,

t SG 11 Ability to recognize indications for system operating parameters which are 2.6 4.2 entry-level conditions for technical specifications.

G 12 Ability to verify system alarm setpoints and operate controls identified in the 1.5 3.3- 1 ,

alarm response manual.

SG 13 Ability to perform specific system and integrated plant procedures during all modes 1.5 3.5 1 of operation.

SG 14 Ability to perform without reference to procedures those action which require 2.0 3.3 1 insnediate operation of system components or controls.

SG 15 Ability to recognize abnormal indications for system operating parameters which are

• 2.6 4.3 entry-level conditions for emergency and abnormal operating procedures.

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High $scondary containment Area Radiation Levels (293033)  ;

WUM KNOWLEDGE APP LSIO SRO NOTE A 100 Ability to operate and/or monitor the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIAil0N LEVELS

-Og A 101 Area radiation monitoring system

• 3.3 4.0 A 102 Process radiation monitoring system

• 3.1 3.8

• 3.0 3.3 A 103 Secondary containment ventitation A 1D4 SBGT/FRVS

• 3.0 4.2 A 105- Af fected systems so as to isolate damaged portions

• 2.6 4.0 A 106 Portable radiation monitoring instruments

• 3.3 3.1 A 107 Personnet dosimetry

• 3.3 3.6 A 108 Control room ventilation: Plant-Specific

• 2.8 3.8 A 200 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTA!kMENT AREA RADIATION LEVELS A 201 Area radiation levels

• 3.3 3.9 A 202 Equipment operability

• 3.3' 3.2 A 203 Cause of high area radiation

• 3.3 4.2 K 100 Knowledge of the o prational implications of the following concepts as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS K 101 Component environmental qualifications

• 3.0 2.8 K 102 Personnel protection

• 3.3 4.2 K 103 Radiation releases

• 3.3 4.2 K 200 Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA RA0! ATION LEVELS and the following K 201 Area radiation monitoring system

• 3.3 4.0 K 202 Process radiation monitoring system

• 3.3 4.1 K 203 Secondary containment ventilation: Plant Specific

• 3.3 3.9 K 204 Standby gas treatment system /FRVS

• ' 3.3 4.2 K 300 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA RADI ATION LEVELS K 301 Emergency depressurization 2.3 3.5 K 302 Reactor SCRAM

• 3.0 3.6 '

K 303 Isolating affected systems 3.0 3.9 K 304 Personnel evacuation 3.3 4.4 K 305 Emergency plan

• 3.3 4.5 SG 1 Knowledge of system status criteria which require the notification of plant

• 3.3 4.2 personnel SG 2 Knowledge of which events related to system operation / status should be reported to

• 3.0 4.5 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits

• 3.3 - 4.1 SG 4 Knowledge of bases in technical specifications for timiting conditions for

• 3.3 3.5 operations and safety limits SG 5 Knowledge of the annunciator alarrs and indications, and use of the response

• 3.0 3.7' instructions SG 6 Ability to locate and operate components, including local controls

• 2.6 3.8 SG 7 Ability to explain and apply all system limits and precautions

• 2.8 3.6 SG 8 Ability to recognite indications for system operating parameters which are

• 3.0 4.2 entry-levet conditions for technical specifications SG 9 Ability to verify system alarm setpoints and operate controts identified in the

• 2.5 3.8 alarm response manual SG 10 Ability to perform without reference to procedures those actions that require

• 2.6 3.7 inrnediate operation of system conponents or controls SG 11 Ability to recognize abnormat indications for system operating parameters which are

• 3.0 4.5 entry-level conditions for emergency and abnormat operating procedures

e 3,3 4,4 i SG 12 Ability to utilize sywptom based procedures

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Rasetor Low Water Level (295031)

NUM KNOWLEDGE APP LSRO SRO ~ NOTE A 100 Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL 2.6 4.4 V . A 101 Low pressure coolant injection (RHR): Plant-Specific ,

A 102 High pressure (feedwater) coolant injection: Plant-Spec.ific 1.8 4.5 1 A 103 Los pressure core spray

• 2.6 4.4  :

A 104 High pressure core spray: Plant Specific 1.8 4.2 1 A 105 Reactor core isolation system: ' Plant-specific 2.1' .4.3 1 A 106 Automatic depressurization system 1.8 4.4 1 A 107 Safety / relief valves 1.8 3.7 '1 A 108 Alternate injection systemst Plant-specific -1.8 3.9 1 A 109 1sotr. ion condenser: Plant-Specific . 1. 8 3.5 L 1 .

t A 110 Gntrol rod drive

• 2.8 3.7

• 2.6 4.1 >

A 111 Condensate 2.3 4.1 1.

A 112 Feedwater A 113 Reactor water level control

• ' 3.3 4.3 .;

A 200 Ability to determine and/or interpret the following as they apply to REACTOR LOW -

WATER LEVEL

• 1 4.6 -

A 201 Reactor water level A 202 Reactor power

• 2.4 4.2 -

A 203 Reactor pressure 2.3 4.2 1- >

A 204 Adeavste core cooling 3.0 4.8 K 100 Knowledge of the operational imlications of the following concepts as they apply to.

REACTOR LOW WATER LEVEL K 101 Adequate core cooling 3.1 4.7 4" ~

• 3.1 4.1 -

K 102 Natural circulation: Plant-Specific K 103 Water level effects on reactor power 2.6 - 4.1 K 200 Knowledge of the interrelations between REACTOR LOW WATER LEVEL and the following K 201 Reactor water level indication 2.8 4.4 K 202 Reactor pressure 2.0 3.9 ~ l' K 203 Low pressure core spray 2.6' 4.3 K 204 Reactor core isolation cooling: Plant-Specific 1.8 4.1 '1 K 205 Low pressure coolant injection (RHR) -* 2.6 4.3 ,

K 206 High pressure (feedwater) coolant injection (FWC1/HPCI): Plant-Specific 1.8 4.2 1-K 207 High pressure core spray: Plant Specific - 1.8 : 4.1 1 K 208 Automatic depressurization system 1.8 ' 4.3 - 1 K 209 Recirculation system: Plant-Specific

• 2.6 ' 3.4 K 210 Redundant reactivity control: Plant-Specific

• 2.5 4.0 K 211 Reactor protection system

• 2.6 4.4 K 212 Primary containment isolation system / Nuclear steam supply shutoff 1.8' '4.5 1 K 213 ARl/RPT/ATVS: Plant-Specific 2.3 4.2. 1 K 214 Emergency generators

• 2.6 4.0 ,

i

'2.3 3.2 K 215 A.C. distribution: Plant Specific 1 4.1 -*

K . 216 Reactor water level control

• 3.0 K 300 Knowledge of the reasons for the following responses as they apply to REACTOR LOW' WATER LEVEL K 301 Automatic depressurization system actuation 2. 0 _ - 4.2 f 1 K 302 Core coverage

• 3.0 - 4.7 >

K 303 Spray cooling

~*

2.8' 4.4

J K 304 Steam cooling * . 2.5 4.3 K 305 Emergency depressurization 1.8 4.3 1 SG 1 Knowledge of system status criteria which require the notification of plant

• 2.5 4.2 -

.. s personnel j

- SG 2 Knowledge of which events related to system operation / status should be reported to

• 2.5 4.6  !

outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits

• 3.1 4.3 'I SG 4 Knowledge of bases in technicel speelfications for limiting conditions for

• 3.1 4.3 )

operations and safety limits SG S . Knowledge of the annunciator alarms and indications, and use of the response

• 2.5 3.8 instructions SG 6 Ability to locate and operate components, including local controls 1.8 3.9 1 SG 7 Ability to explain and apply all system limits and precautions 2.1 4.0 1 SG 8 Ability to recognize indications for system operating parameters which are

• 2.6 4.4 entry level conditions for technical specifications SG 9 Ability to verify system alarm setpoints and operate controls identified in the

• 2.5 3.9  ;

alarm response manual SG 10 Ability to perform without reference to procedures those actions that require 2.3 ~ 3.8 1 ininediate operation of system conponents or controls SG 11 Ability to recognize abnormal indications for system operating parameters which are

• 2.6 4.6 -

entry-level conditions for emergency and abnormal operating procedures SG 12 Ability to utilize symptom based procedures 2.3 4.5 1 6 i

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High Stcondary Containment Area Radiation Levels (295033)

WUM KNOWLEDGE APP LSRO SRO NOTE A 100 to o rate and/or monitor the following as they apply to HIGH SECONDARY AbilitgMENT CONTAI pREA RADIATION LEVELS A 101 Area radiation monitoring srStem

• 3.3 4.0

(

A 102 Process radiation monitoring system

• 3.1 3.8 A 103 Secondary containment ventilation

• 3.0 3.8 A 104 SBGT/FRVS

• 3.0 4.2 -

A 105 Affected systems so as to isolate damaged portions

• 2.6 4.0 A 106 Portable radiation monitoring instruments

• 3.3 3.1 A 107 Personnel dosimetry

• 3.3 3.6 A 108 Control room ventilation: Plant-specific

• 2.8 3.8 A 200 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS A 201 Area radiation levels 3.3 3.9 A 202 Equipment operability 3.3 3.2 A 203 Cause of high area radiation

• 3.3 4.2 K 100 Knowled e of the operational implications of the following concepts as they apply to HIGH SE ONDARY CONTAINMENT AREA RADIATION LEVELS K 101 Component envirorrnental qualifications

• 3.0 2.8 K 102 Personnel protection 3.3 4.2 K 103 Radiation releases

• 3.3 4.2 K 200 Knowledge of the interrelations between HIGH SECONOARY CONTAINMENT AREA RADIATION LEVELS and the following K 201 Area radiation monitoring system 3.3 4.0' K 202 Process radiation monitoring system

• 3.3 4.1 K 203 secondary containment ventilation: Plant Specific

• 3.3 3.9

]

%./ K 204 Standby gas treatment system /FRVS

• 3.3 4.2 K 300 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAthMENT AREA RADIAfl0N LEVELS K 301 Emergency depressurization 2.3 3.5 1 K 302 Reactor SCRAM

• 3.0 3.6 K 303 Isolating affected systems

• 3.0 3.9 K 304 Personnel evacuation

• 3.3 4.4 K 305 Emergency plan 3.3 4.5 SG 1 Knowledge of system status criteria which require the notification of plant

• 3.3 4.2 personnel SG 2 Knowledge of which events related to system operation / status should be reported to

• 3.0 4.5 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits

• 3.3 4.1 SG 4 Knowledge of bases in technical specifications for limiting conditions for

• 3.3 3.5 operations and safety limits SG 5 Knowledge of the annunciator alarms and irdications, and use of the response

• 3.0 3.7 instructions SG 6 Ability to locate and operate conponents, including local controls

• 2.6 3.8 SG 7 Ability to explain and apply all system limits and precautions

• 2.8 3.6 SG 8 Ability to recognize indications for system operating parameters which are

• 3.0 4.2 entry level conditions for technical specifications SG 9 Ability to verify system alarm setpoints ard operate controls identified in the

• 2.5- 3.8 alarm response manual SG 10 Ability to perform without reference to procedures those actions that require

• 2.6 3.7 immediate operation of system conponents or controls o

O; SG 11 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures

• 3.0 4.5

- - . ~ . . - . . . . - . - . - - . . . .- - . . . . . - . ~.. .- - ,

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• 3.3 4.4 .

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Secondary Containment Vent. High Rsdiation Levels (295034)

APP LSRO SRO NOTE NUM KNOWLEDGE A 100 Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION LEVELS

. 2.3 3.8 1 A 101 Area radiation monitoring system A 102 Process radiation monitoring system 2.3 4.0 1 A 103 Secondary containment ventilation 2.3 3.9 1 A 104 58GT/FRVS: Plant-specific 2.3 4.2 1 --

A 105 fuel building ventitation: Plant-Specific 2.3 3.8 1 A 200 Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION LEVELS

• 3.1 4.2 A 201 Ventitation radiation levels A 202 Cause of high radiation levels 3.1 4.2 .

K 100 Knowledge of the operational implications cf the following concepts as they apply to SECONDARY CONTAINMcNT VENTILATION HIGH RADIATION LEVELS

• 3.3 4.1 K 101 Personnel protection

• 3.3 4.4 K 102 Radiation releases K 200 Knowledge of the interrelations between SECONDARY CONTAINMENT VENTJLATION HIGH RADIATION LEVELS and the following Process radiation monitoring system

• 3.3 4.2 K 201 K 202 Area radiation monitoring system

• 3.3 3.9 K 203 SBGT/FRVS; Plant-Specific 3.3 4.5 K 204 Secondary containment ventitation

• 3.3 3.9.

K 205 Fuel building ventilation: Mark-Ill 2.3 3.7 1 K 206 PCIS/NSSSS: Plant-Specific 2.3 4.2 1 K 300 Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION LEVELS

• 3.3 4.1

\ K 301 Isolating secondary contairrent ventilation

• 4.1 K 302 Starting SBGT/FRVS: Plant-Specific 3.1 K 303 Personnel evacuation 3.3 4.4 . ,

K 304 Fuel building ventitation: Plant Specific

• 2.6 3.8 K 305 Manual SCRAM and depressurization: Plant-Specific 2.3 - 3.9  ; 1:

SG 1 Knowledge of system status criteria which require the notification of plant

• .3.3 4.2 personnel SG 2 Knowledge of which events related to system operation / status should be reported to 3.0 4.6 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits

• 3.3 3.9 Sc 4 Knowledge of bases in technical specifications for timiting conditions for

• 3.3 3.7 i

operations and safety limits SG 5 Knowledge of the annunciator alarms and indications, and use of the response 3.0 3.7 instructions SG 6 Ability to locate and operate components, including local controls

• 2.8 3.8 SG 7 Ability to explain and apply att system limits and precautions

• 2.5 3.5 -

SG 8 Ability to recognize indications for system operating parameters which are *

- 3.0 4.1 entry-level conditions for technical specifications SG 9 Ability to verify system alarm setpoints and operate controls identified in the *'

2.5 : 3.7 alarm response manual SG 10' Ability to perform without reference to procedures those actions that reautre

• 2.5 3.6 imediate operation of system components or controts SG 11 Ability to recognize abnormat indications for system operating parameters which are

• 3.0 4.3 -

entry-level conditions for emergency and abnormal operating procedures l SG 12 ' Ability to utilize syrnptom based procedures 2.8 4.4 w

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Secondary Containment High Differentist Pressure (295035)

NUM KNOWLEDGE APP LSRO SRO NOTE EA 100 Ability to oprate and/or monitor the following as they apply to SECONDARY

-(' CONTAINMENT HIGH OlffERENTIAL PRESSURE:

EA 101 Secondary containnent ventilation system 1.0 3.6 1 EA 102 SBGi/FPvs 1.0 3.8 i EA 200 Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH OlFFERENTIAL PRESSURE:

EA 201 Secondary containment pressure: Plant-Specific 1.0 3.9 1 1

EA 202 Off site release rate: Plant-Specific 1.0 4.1 1 EK 100 Knowledge of the oMrational implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:

EK 101 Secondary containment integrity 1.0 4.2 1-EK 102 Radiation release 1.0 4.2 1 EK 200 Knowledge of the interrelations between SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE and the following:

EK 201 secondary containment ventilation 1.0 3.6 1 EK 202 SBCT/FR$L 1.0 3.8 1 EK 203 off-site release rate 1.0 4.1 1 EK 2D4 Blow-out panels: Plant-Specific 1.0 3.7 1 EK 300 Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT HIGH OlFFERENTIAL PRESSURE:

EK 301 Blow-out panel operation: Plant-Specific 1.0 3.1 1 EK 302 Secondary containment ventilation response 1.0 3.5 1 SG 1 Knowledge of system status criteria which require the notification of plant 1.0 4.1 1 personnel SG 2 Knowledge of which events related to system operation / status should be reported to 1.0 4.4 . 1 outside agencies SG 3 Knowledge of timiting conditions for operations and safety limits 1.0 3.9 1 SG 4 Knowledge of bases in technical specifications for limiting conditions for 1.0 3.6 1 operations and saf ety limits SG 5 Knowledge of the annunciater alarms and indications, and use of the response 1.0 3.4 1 instructions SG 6 Ability to locate and operate components, including local controls 1.0 3.8 1 SG 7 Ability to explain and apply all system limits and precautions 1.0 3.5 1 SG 8 Ability to recognize indications for system operating parameters which are 1.0 4.1 1 entry-level conditions for technical specifications SG 9 Ability to verify system alarm setpoints and operate controts identified in the 1.0 3.5 1-~

alarm response manual SG 10 Ability to perform without reference to procedures those actions that require 1.0 3.3 1 irrmediate operation of system components or controls SG 11 Ability to recognize abnormal indications for system operating parameters which are 1.0 4.2 1 entry-level conditions for emergency and abnormat operating procedures SG 12 -Ability to utilize symptom based procedures 1.0 4.1 1-i s-.  !

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Partial or Couplete Loss of A.C. Powsr (295003)

APP LSRO $20 NOTE-NUM KNOWLEDGE AA 100 AblLity to operate and/or mor'itor the following as they apply to PARTI AL OR COMPLETE LOSS OF A.C. POWER:

'O AA 101 A.C. electrical distribution system 2.0 2.0 3.8 4.3 1

1 AA 102 Emergency generators 1.6 4.4 1 AA 103 Systems necessary to assure safe plant shutdown +

D.C. electrical distribution system 2.0 3.7 .1 AA 104 ,

AA 200 Ability to determine and/or interpret the following as they apply to PARTI AL OR '

COMPLETE LOSS OF A.C. POWER:

1.6 3.7 1 AA 201 Cause of partial or complete less of A.C. power 2.3 4.3 1 AA 202 Reactor power, pressure, and level 1.6 3.5 1 AA 203 Battery status: Plant Specific 1.8 3.7 1 AA 204 System lineups AA 205 Whether a partial or complete loss of A.C. power has occurred 1.6 4.2 1 AK 100 Knowledge of the operational Ipplications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER:

Effect of battery discharge rate on capacity 1.6 2.9 1 AK 101 1.8 3.4' 1 AK 102 Load shedding AK 103 under voltage / degraded voltage effects on electrical loads 1.8 3.2 1 AK 104 Electrical bus divisional separation 2.3 3.2 1 1.8 2.7 1 AK 105 failsafe component design AK 106 Station blackout: Plant Specific 1.8 4.0 1 AK 200 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF A.C. POWER and the following: ,

2.0 3.3 1 AK 201 Station batteries AK 202 Emergency generators 2.3 - 4.2 1 A.C. electrical distribution system 2.3 3.9 1 AK 203 2.3 3.5 1 AK 204 A.C. electrical loads Isotation condenser: Plant-Specific 1.6 4.0 1 AK 205 2.3. 3.5 1 i AK 206 D.C. electrical loads AK 300 Knowledge of the reasons for the following responses as they apply to PART!AL OR COMPLETE LOSS OF A.C. POWER:

2.0 3.5 1 ,

AK 301 Manuat and auto bus transfer

'2.0 3.1 1-AK 302 Selective tripping 2.3 3.6 1 AK 303 Load shedding 1.6 3.2 .1 AK 304 Ground isolation 2.0 3.7 1 AK 305 Reactor SCRAM 2.0 3.7 1 AK 306 Containment isolation AK 307 Initiation of isolation condenser: Plant-ipecific 1.6 4.0 1 SG 1 Knowledge of system status criteria which tequire the notification of plant ' 2.0 3.9 1 personnel SG 2 Knowledge of which events related to system operation / status should be reported to 2.1 4.5 - 1 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits 2.3 4.1 ~1 I SG 4 Knowledge of bases in technical specifications for limiting conditions for 2.3 - 3.8 . 1 operations and safety limits 1.6 3.6 1 SG 5 Knowledge of the annunciator alarms and indications, and use of the response instructions 1.6 4.0 1 SG 6 Ability to locate and operate cocoonents, including local controls 1.6 3.6 1 SG 7 Ability to explain and apply all system limits and precautions 2.3 4.2 1-SG 8 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications I

SG 9 Ability to verify system alarm setpoints snd operate controls idsntified in the 1.6 3.6 1:

starm response manuzt . .

SG 10 Ability to perform without reference to procedures those actions that require 1.8 4.1 1 immediate operation of system components or controts ,

SG 11 Ab1Lity to recognize abnormal Indications for system operating parameters which are 2.3 4.3 1 s

entry-tevet conditions for emergency and abnormat operating procedures F SG 12 Abltity to utilite symptom based procedures 1.8 4.2 1 i

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Low Resctor Water Level (295009)

APP LSRO SRO . NOTE.

NIM KNOWLEDGE A 100 Ability to operate and/or monitor the following as they apply to LOW REACTOR WATER LEVEL 2.0 '3.9 1

'% A 101 Reactor feedwater 2.0 4.0 1 A 102 Reactor water level control A 103 Recirculation system: Plant Specific 2.0 3.1 1 A 104 Reactor water cleanup 2.0 2.7 1'  ;

A 200 Ability to determine and/or interpret the following as they apply to LOW REACTOR ~

WATEP LEVEL

• 2.6 4.2 i A 201 Reactor water level 1.6 3.7 1.

A 202 Steam flow / feed flow mismatch A 203 Reactor water cleanup blowdown rate 1.6 2.9. 1 K 100 Knowledge of the operational implications of the following concepts as they apply to LOW REACTOR WATER LEVEL 1.6 2.9 1' K 101 Steam carryunder K 102 Recirculation pump net positive suction head: Plant-Specific 2.0 3.1 1 K 103 Jet pisnp net positive suction head: Not-BWR-1&2 2.0 2.7 1 K 104 Jet pump efficiency: Not-BWR 1&2 1.8 ' 2.4 1

• 2.5 3.4' K 105 Natural circulation K 200 Knowledge of the interrelations between LOW REACTOR WATER LEVEL and the following

• 2.5 4.0 K 201 Reactor water level indication 2.3 3.9 1 K 202 Reactor water level control K 203 Recirculation systen 2.3 3.2 1 2.3 2.6- 1 K 204 Reactor .ater cleanup K 300 Knowl'. m of the reasons for the following responses as they apply to LOW REACTOR  !

WATER LEVEL 1.6 3.3 -1 K 301 Recirculation ::-snp run back: Plant Specific ,

K 302 Reactor feedpunp runout flow control; Plant-Specific 1.5- 2.8 1 SG 1 Knowledge of system status criteria which require the notification of plant

• 2.5 .4.1 personnel SG 2 Knowledge of which events related to system operation / status should be reported to 2.1 4.6 1 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits

• 2.5 4.2 SG 4 Knowledge of bases in technical specifications for limiting conditions for 2.8 4.2 operations and safety limits SG 5 Knowledge of the annunciator alarms and indications, and use of the response 1.8 3.6 1.

instructions SG 6 Ability to locate and operate components, including local controls 1.5 3.9 1 SG 7 Abitity to explain and apply all system limits and precautions 1.5 3.4 1 SG B Ability to recognize indications for system operating parameters which are 2.3 4.4 1 >

entry level conditions for tecnnical specifications SG 9 Ability to verity system alarm setpoints and operate controls identified in the 2.0 3.7 -1 alarn response manual _,

SG 10 - Ability to perform without reference to procedures those actions that require 2.1 . 4.0 1 innediate operation of system components or controls SG 11 Ability to recognize abnormal indications for system operating parameters which are

• 2.5 4.5 entry-level conditions for emergency and abnormat operating procedures SG f2 Ability to utilize sy y tom based procedures 2.1 4.4 1 t

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Inadvertent Reactivity Addition (295014)

APP LSRO SRO NOTE WUM K20WLEDGE A 100 Ability to oprate and/or monitor the following as they apply to INADVERTENT h REACTIVTY ADDITION 1.5 4.1 1 s A 101 RPS 1.6 3.8 1 A-102 Recirculation flow control system 1.6 3.5 1 l A 103 RMCS: Plant-Specific A 104 Rod control and information system: Plant-Specif ic 2.0 3.3 1' A 105 Neutron monitoring system 2.1 3.9 1

• A 106 Reactor / turbine pressure regulating system 1.6 - 3.4 1 A 107 Cold water injection 1.6 ' 4.1 1 A 200 Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION A 201 Reactor power

• 2.6 4.2 i

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A 202 Reactor period

• 2.6 3.9 A 203 Cause of reactivity addition

• 2.8 4.3

• 2.6 4.4 A 204 Violation of fuel thermat limits A 205 Violation of safety limits

• 2.6 4.6 1

L K 100 Knowledge of the operational implications of the following concepts as they apply to 1 INADVERTENT REACTIVTY A001110N K 101 Prompt critical 3.0 3.8 i-K 102 Reactivity anomaly

• 3.0 3.7 K 103 Shutdown margin 3.0 4.0 K 1 04 PC10MR: Plant-Specific

• 2.5 3.4

• 2.8 4.2 -

K 105 fuel thernet limits K 106 Abnormal reactivity additions

• 3.0 3.9 K 200 Knowledge of the interrelations between INADVERTENT REACTIVITY ADDITION and the following

• 3.0 ~ 4.1 K 201 RPS

• 2.8 4.2 K 202 Fuel thermal limits

• 2.8 3.4 K 203 fuel temperature

• 2.5 3.3 K 204 Void concentration K 205 Neutron monitoring system 2.8 ' 4.1

• 2.8 3.5 K 206 Moderator temperature

• 2.8 3.9 K 207 Reactor power K 208 RMCS: Plant-Specific

• 2.8 3.5 K 209 Rod control and information system: Plant Specific

• 2.5 3.6

• 2.8 4.5 K 210 Safety limits 2.3 3.7 1 K 211 Recirculation flow control K 300 Knowledge of the reasons for the following responses as they apply to 1NADVERtENT REACTIVITY ADDITION

• 2.6 4.1 K 301 Reactor SCRAM

• 3.0 - 3.7 K 302 Control rod blocks SG 1 Knowledge of system status criteria which require the notification of plant

• 3.0 3.9 personnel

• 2.6 4.6 SG 2 Knowledge of which events related to system operation / status should be reported to .

outside agencies

• 3.0 4.3 SG 3 Knowledge of timiting conditions for operations and safety limits

• 3.0 4.2 SC 4 Knowledge of bases in technical specifications for limiting conditions for l operations and safety limits O SG 5 Knowledge of the annunciator alarms and indications, and use of the response instructi ons 2.3 3.7 1  !

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6'" Ability to locate and operate components, including local' controls 2.3 ~ 3.7 ~ '1

. SG

-SG - Ability to explain snd opply all system limits ard precautions ' 2.1 3.6 1 8' Ability to recognize indications for system operating parameters which are

• 2.6 - 4.3 SG entry-level conditions for technical specifications

SG 9 Ability to verify system alarm setpoints and operate controls identified in the 2.0 3.7 1

- alarm response manual SG 10 Ability to perform without reference to procedures those actions that require

• - 2.5 3.9 inrediate operation of system conponents or controls SG 11 Ability to recognite abnormal indications for system operating parameters which are

• 2.6 4.4 -

entry-level conditions for emergency and abnormal operating procedures SG 12- Ability to utilize synytom based procedures

• 2.5 4.3 O

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Partial or Co m lete Loss of Co m onent cooling Water (295018)

APP LSRO SRO NOTE NUM KNOWLEDGE AA 100 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

1.5 3.4 V AA 101 Backup systems 1

1.5 3.4 1 AA 102 System loads AA 103 Affected systems so as to isolate damaged portions 1.5 3.4 1 AA 200 Ability to determine and/or interpret the following as they apply to PARTIAL OR ,

COMPLETE LOSS OF COMPONENT COOLING WATER:

1.5 3.4 1 AA 201 Corponent tenperatures AA 202 Cooling water temperature 1.5 3.2 1 AA 203 Cause for partial or com lete loss 1.5 3.5' 1 AA 204 System flow 1.5 2.9 1 AA 205 System pressure 1.5 2.9 1 ,

AK 100 Knowledge of the operational implications of the following concepts as they apply to -

PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

AK 101 Effects on component / system operations 1.8 3.6 1 AK 200 Knowledge of the interrelations between PART!AL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:

AK 201 System loads 2.0 3.4 1 AK 202 Plant operations 2.0 3.6 1 ,

AK 300 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

Isolation of non-essential heat loads: Plant Specific 1.8 3.2 1 AK 301 AK 302 Reactor power reduction 1.5 3.4 1 AK 303 Securing individual components (prevent equignent damage) 2.0 3.3 1 AK 304 Starting standby pump 2.0 3.3 1 AK 305 Placing standby heat exchanger in service 2.0 - 3.3 1 AK 306 Increasing cooling water flow to heat exchangers 2.0 3.3 1

=

AK 307 Cross-connecting with backup systems 2.0 3.2 1 SG 1 Knowledge of system status criteria which require the notification of plant 2.0 3.6 1 personnel ,

SG 2 Knowledge of which events related to system operation / status should be reported to 1' 8

. 4.2 1 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits 2.1 3.9 - 1 SG 4 Knowledge of bases in technical specifications for limiting conditions for 2.1 3.5 - 1 operations and safety limits SG 5 Knowledge of the annunciator alarms and indications, and use of the response 1.5 3.5~ 1 instructions SG 6 Ability to locate and operate components, including local controls 1.5 3.4 1 SG 7 Ability to explain and apply all system limits and precautions 1.5 3.4 1 SG 8 Ability to recognize indications for system operating parameters which are 2.0 4.1 .1 entry-level conditions for technical specifications SG 9 Ability tn verify system alarm setpoints and operate controls identified in the 1.5 3.3 1 alarm response manual SG 10 Ability to perform without reference to procedures those actions that require 1.5 3.3 1 intnediate operation of system comonents or controls SG 11 Ability to recognize abnormal indications for system operating parameters which are 1.6 4.1 1' entry-level conditions for emergency and abnormal operating procedures SG 12 Ability to utilize sym tom based procedures 1.5 4.0 1 O

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Inadvertent Containment Isola' tion (295020) .

. NOTE i NUM KNOWLEDGE ~ APP LSRO SRO.

AA 100 Ability to operate and/or monitor the following as they apply to INADVERTENT y"'N CONTAlkMENT ISOLATION:

1.3 3.6 1 AA 101 PCIS/NS$$$

AA 102 Drywett ventitation/ cooling system 1.3 3.2 1 AA 103 Contalnment ventitation system: P1 ant-Specific 1.3 3.1 1 AA 105 Loss of drywett/contaircent cooling 1.6 3.6 1 AA 200 Ability to determine and/or interpret the following as they apply to INADVERTENT CONTAINHENT ISOLATION:

AA 201 Drywell/ containment pressure 1.3 3.7 1 AA 202 Drywell/ containment temperature 1.3 3.4 1 AA 203 Reactor power 1.3 3.7 1 AA 204 Reactor pressure 1.3 3.9 1 AA 205 Reactor water levet 1.3 3.6 1 AA 206 Cause of Isolation 1.3 3.8 1 AK 100 Knowledge of the operational implications of the follnwing concepts as they apply to INADVERIENT CONTAINMENT ISOLATION:

AK 101 Loss of normal heat sink 1.6 3.9 1 AK 102 Power / reactivity control 1.3 3.8 - 1 AK 103 Water chemistry 1.3 2.5 1 AK 104 Bottom head thermal stratification 1.6 2.8 1 AK 200 Knowledge of the interrelations between INADVERTENT CONTAINMENT ISOLATION and the following:

AK 201 Main steam system 1.3 3.7 1 AK 202 Sampling system 1.3 2.8 1-AK 203 D rywe t t / c ont a i nment vent i l a t i on/ cool i ng : Plant-Specific 1.3 3.3 1 AK 204 RWCU system 1.6' 3.1 1 AK 205 Isolation condenser: Plant-Specific 1.3 4.2 1 AK 206 HPCI: Plant

• Specific 1.3 3.8 1 AK 207 RCIC: Plant Specific 1.6 3.4 1 AK 208 Traversing in-core probes: Plant-Specific 1.6 2.6 ' 1 -

AK 209 RHR/ shutdown cooling: Plant-Specific 1.6 '3.3 1 AK 210 Drywell equipment / floor drain smps 1.6 3.1 1 AK 211 Standby gas treatment system /FRVS: Plant Specific 1.6 3.4 1 AK 212 Instrument air / nitrogen: Plant-Specific 1.3 3.2 1 AK 300 Knowledge of the reasons for the following responses as they apply to INADVERTENT CONTAINMENT ISOLATION:

AK 301 Reactor SCRAM 1.5 3.8 1 AK 302 Drywett/ containment pressure response 1.3 - 3.5 1 AK 303 Drywell/ containment temerature response 1.3 3.2 1 AK 304 Reactor pressure response 1.3 4.1 1 AK 305 Reactor water level response .1.3 3.9 - 1 AK 306 Suppression pool water level response ' 1.3 3.4 1 AK 307 Suppression pool temperature response 1.3 3.6 1 AK 308 Suppression chanber pressure response 1.3 3.5 1 SG 1 Knowledge of system status criteria which require the notification of plant 1.6 3.8 1 personnet e SG 2 Knowledge of which events related to system operation / status should be reported to 1.3 4.1 1 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits 1.6 3.9 1 i

l a

I SG 4 Knowledga of bases in technical specifications for limiting conditions for 1.6 .3.8 1

.f operations cnd safety limits )

SG 5 Knowledge of the annunciator alarms and indications, and use of the response 1.3 3.4 1 {

l instructions ,

SG 6 Ability to locate and operate components, including local controls 1.3 3.5 1 i SG 7 Ability to explain and apply all system limits and precautions 1.3 3.3 . 1 SG 8 Ability to recognize indications for system operating parameters which are 1.5 3.9 1 entry-Level conditions for technical specifications SG 9 Ability to verify system alarm setpoints and operate controls identified in the 1.3 3.3 1 alarm response manual SG 10 Abilf}y to perform without reference to procedures those actions that require 1. .' 3.5 1 imediate operation of system components or controls '

SG 11 Ability to recognize abnornel indications for system operating parameters which are 1.5 4.1 ~1 entry level conditions for emergency and abnormal operating procedures SG 12 Ability to utilize symptom based procedures 1.3 4.1 1 r

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l Loss of Shutdown Cooling (295021)

APP LSRO SRO NOTE NUM KNOWLEDGE A 100 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN

.- COOLING

'V A 101 Reactor water cleanup system 2.1 - 3.4 1 A 102 RHR/ shutdown coJting

• 2.5 3.5 i

A 103 Component cooling water systems: Plant *Spectfic 2.1 3.1 1 .i 1

2.1 3.7 1 A 104 Alternate heat removal methods ]

2.1- 3.0 1 A 105 Reactor recirculation l A 106 Containment / drywell temperature 2.1 3.0 1 A 200 Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING Reactor water heatup/cooldown rate 2.8 3.6 A 201 A 202 RHR/ shutdown cooling system flow 2.3 3.4 1

• 3.0 3.5 A 203 Reactor water level A 204 Reactor water temperature

• 3.0 3.6 A 205 Reactor vessel metal temperature

• 2.6 ' 3.5 I A 206 Reactor pressure

• . 2.5 3.3' 2.5 3.1 A 207 Reactor recirculation flow K 100 Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING K 101 Decay heat

• 3.0 3.8

• 3.0 3.4 K 102 Thermal stratification K 103 Adequate core cooling

• 3.0 3.9 K 104 Natural circulation

• 3.0 3.7 K 200 Knowledge of the interrelations between LOSS OF SNUTDOWN COOLING and the following

'5 K 201 Reactor water temperature

• 3.1 3.7 K 202 Reactor water cleanup 3.0 3.3 K 203 RHR/ shutdown cooling

• 3.1 3.6 K 204 Component cooling water systems: Plant-Specific 2.8 3.1 K 205 Fuel pool cooling and cleanup system

• 3.1 ' 2.8 K 206 Reactor vessel headspray: Plant-Specific 2.5 2.6

• 2.8 3.2 K 207 Reactor recirculation K 300 Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING K 301 Raising reactor water level

• 3.0 - 3.4 K 302 Feeding and bleeding reactor vessel

• 3.0 3.4' Increasing drywell cooling

• 2.6 2.9 K 303 K 304 Maximizing reactor water cleanup flow 3.0 3.4 K 305 Establishing alternate heat removal flow paths

• -3.0 3.8 SG 1 Knowledge of system status criteria which require the notification of plant

• 3.1 3.6 personnel SG 2 Knowledge of which events related to system operation / status should be reported to

• 2.8 4.1 outside agencies SG 3 Knowledge of limiting conditions for operations and safety limits

• 3.1- 3.6 SG 4 Knowledge of bases in technical specifications for limiting conditions for

• 3.1 3.6 operations and safety limits SG 5 Knowledge of the annunciator alarms and indications, and use of the response 2.1 3.4 1 instructions SG 6 Ability to locate and operate components, including local controls 2.1 3.5 1 SG 7 Ability to explain and apply all system limits and precautions 2.1 3.2 1 SG 8 Ability to recognize indications for system operating parameters which are

• 3.0 3.9 entry-level conditions for technical specifications

r' SG 9 Ability to verify system alarm sstpoints and operate controls idmtified in tha - 2.1 ~ 3.3 1 alarm rssponsa manu2L SG 10 Ability to perform without reference to procedures those actions that require 2.1 3.3 1 immediate operation of system components or controls

' 2.3 3.8 pj SG 11 Ability to recognize abnormal indications for system operating parameters which are entry-tevel conditions for emergency and abnormal operating procedures 1

$G 12 Ability to utilize symptom based procedures 2.1 4.0 1 b

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Refuting Accidents (295023) 'l NUM KNOWLEDGE APP LSRO SRO NOTE-A 100 Ability to operate ard/or monitor the following as they apply to REFUELING ACCIDENTS s

A 101 Secondary containment ventitatton

• 3.8 3.5 A 102 Fuel pool cooling and cleanup system

• 4.5 3.1 A 103 fuel handling equipment

• 4.5 - 3.6.

A 104 Radiation monitoring equipment

• 4.5 3.7 ,

A 105 Fuel transfer system: Plant-Specific

• 4.5 3.5 A 106 Neutron monitoring

• 3.8 3.4 A 107 Standby gas treatment /FRVS

• 3.8 3.6 A 108 Containment buitding ventitation: Mark-III

• 3.3 3.4 A 200 Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS A 201 Area radiation levels 4.5 4.0 A 202 Fuel pool level

• 4.5 3.7

• 4.5 3.8 A 203 Airborne contamination levels A 204 Occurrence of fuel handling accident

• 4.5 4.1 ,

A 205 Entry conditions of emergency plan

• 4.5 4.6 t

K 100 Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS K 101 Radiation exposure hazards

• 4.5 4.1 K 102 Shutdown margin

• 4.5 3.6 K 103 Inadvertant criticality

- 4.5 4.0 K 200 Knowledge of the interrelations between REFUELING ACCIDENTS and the following K 201 Fuel handting equipment

• 4.5 3.7  ;

K 202 Fuet pool cooling and cleanup system 4.5 3.2 >

k K 203 Radiation monitoring equipment 4.5 3.6 i K 204 RMCS/ Rod control and information system

• 4.3 3.4 K 205 Secondary containment ventilation

• 4.5 3.7

• 3.3 3.8 K 206 Contairment ventilation: Mark-111 K 207 Standby gas treatment /FRvS 4.5 3.9 K 300 Knowled e of the reasons for the following responses as they apply to REFUELING ACCIDEN $

K 301 Refueling floor evacuation 4.5 4.3 Interlocks associated with fuel handling equipment

• 4.5 3.8 K 302 K 303 Ventilation isolation 4.5 3.6 4.5 3.5 K 304 Non-coincident SCRAM function Initiation of SLC/ shut-down cooling: Plant-Specific (bur-1)

• 4.0 4.0 K 305 SG 1 Knowledge of system status criteria which require the notification of plant

• 4.5 4.2 personnel SG 2 Knowledge of which events related to system operation / status should be reported to 4.5 4.5 outside agencies SG 3 Knowledge of timiting conditions for operations and safety limits

• 4.5 3.8 SG 4 Knowledge of bases in technical speelfications for limiting conditions for

• 4.5 3.8 operations and safety limits SG 5 Knowledge of the annuncistor alarms and indications, and use of the response

• 4.5 3.6 instructions SG 6 Ability to locate ard operate components, including local controls

• 4.5 3.6 SG 7 Ability to explain ard apply all system limits and precautions

• 4.5 3.6 SG 8 Ability to recognize indications for system operating parameters which are 4.5 3.9 entry-level conditions for technical specifications '

SG 9 Ability to verify system alarm setpoints and operate controts identified in the

• 4.5 3.7' alarm response manual s

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• 4.5 3.9 inmediate operation of system conponents or controls SG 11 Ability to recognize abnormal indications for system operating parameters which are

• 4.5 '4.2 entry-level conditions for emergency and abnormat operating procedures SG 12 Ability to utilize symptom based procedures

• 4.5 4.2

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