ML022390347

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Draft - Outlines
ML022390347
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/11/2002
From: Hornick J
Constellation Nuclear
To: Conte R
NRC/RGN-I/DRS/OSB
References
50-317/02301, 50-318/02301
Download: ML022390347 (50)
v • d • e


Text

ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: Calvert Cliffs Date of Exam: 7/12/02 Exam Level: SRO Tier Group K/A Category Points Point Total K K KKK K A A A A G 1 2 3 4 5 6 1 2 3 4 *I

1. 1 4 3 3 6 24 Emergency & 2 3 1 25 3 16 Abnormal 3 0 0 M _ 1 _ 3 Plant 3 1_ll l_1____

Evolutions Tier 8 4 5 9 8 9 43 Totals

2. 1 3 1 1 . 3 2 2 19 Plant 2 1 0 3 2 2 3 1 2 1 1 1 17 Systems Sses 3 0 1 1 1 0 0 0 0 0 0 1 4 Tier 4 2 5 4 4 5 4 4 2 2 4 40 Totals Cat 1 Cat 2 Cat 3 Cat 4
3. Generic Knowledge and Abilities 5 6 4 2 17 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (ie., the "Tier Totals" in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by + I from that specified in the table based on NRC revisions. The final exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topic's importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities.

Enter the tier totals for each category in the table above.

NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE# / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points 000001 Continuous Rod Withdrawal /1 2.4.1 Knowledge of EOP entry conditions and immediate 4.6 1 action steps. SRO 000003 Dropped Control Rod /1 1.04 Knowledge of the operational implications of the effects 3.7 1 of power level and control rod position, on flux.

000005 Inoperable/Stuck Control Rod /1 2.01 Knowledge of the interrelationships between an 3.8 1 inoperable/stuck control rod and the controllers and positioners.

000011 Large Break LOCA /3 2.1.32 Ability to explain and apply all system limits and 3.4 1 precautions SRO 2.07 Ability to determine or interpret the equipment 3.4 1 necessary for functioning of critical pump water seals during a large break LOCA. SRO 000015/17 RCP Malfunctions /4 2.10 Knowledge of the interrelationships between RCP 2.8 1 malfunctions and the RCP indicators and controls.

CE/A13 Natural Circulation / 4 3.4 Knowledge of the reasons for the RO and SRO to 3.4 1 function as a team such that procedures are adhered to and license limitations are not violated, during natural circulation operations.

000024 Emergency Boration / 1 2.03 Ability to determine and interpret the correlation 3.0 1 between boric acid controller setpoint and boric acid flow. SRO 000026 Loss of Component Cooling Water /8 1.06 Ability to control and/or monitor flowrates to 2.9 1 components cooled by CCW, during loss of Component Cooling Water 000029 Anticipated Transient W/O Scram / 1 3.10 Knowledge of the reasons for manual rod insertion 4.1 1 during an ATWS.

000040 (CEIE05) Steam Line Rupture - Excessive Heat Transfer / 4 2.2.4 Ability to explain variations in control board layouts, 3.0 1 systems, instrumentation and procedural actions

__ between units.

NUREG-1021, Revision 8, Supplement 1

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ES PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (Cont.)

Kl K2 K3 Al A2 G K/A Topic(s) Imp. Points EIAPE# / Name / Safety Function 1.30 Ability to operate/monitor desired operating results 3.5 1 CE/A11 RCS Overcooling - PTS /4 during abnormal and emergency situations.

1.30 Knowledge of the operational implications of 3.2 1 annunciators, condition indicating signals, and remedial actions, as they apply to RCS overcooling.

000051 Loss of Condenser Vacuum / 4 2.02 Ability to determine and interpret condenser vacuum 4.1 1 conditions requiring a reactor and/or turbine trip. SRO 1.01 Knowledge of the operational impacts of battery 3.7 1 000055 Station Blackout / 6 discharge rates on capacity.

2.16 Ability to determine and interpret normal and abnormal 3.1 1 000057 Loss of Vital AC Electrical Instrument Bus / 6 Pressurizer levels for various modes of plant operation, as they apply to a loss of a Vital AC Instrument Bus.

2.02 Knowledge of the interrelationships between the 2.7 1 000059 Accidental Liquid RadcWaste Release /9 accidental release and the radioactive gas monitors.

000062 Loss of Nuclear Service Water / 4 2.1.8 Ability to coordinate personnel activities outside the 3.6 1 control room.

000067 Plant Fire On-site / 9 1.02 Knowledge of operational implications of firefighting. 3.9 1 2.08 Ability to determine and interpret SG pressure during 4.1 1 000068 Control Room Evacuation / 8 Control Room evacuation.

000069 Loss of Containment Integrity/ 5 2.1.33 Ability to recognize indications for system operating 4.0 1 parameters, which are entry level conditions to technical specifications.

(SRO ONLY) 1.03 Ability to operate and/or monitor fluid systems 3.0 1 penetrating containment, as they apply to a loss of Containment integrity.

NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group I (Cont.)

EIAPE# I Name I Safety Function Kl K2 K3 Al A2 G KWA Topic(s) Imp. Points 000074 Inadequate Core Cooling /4 2.4.6 Knowledge of symptom based EOP mitigation 4.0 1 strategies. SRO 000076 High Reactor Coolant Activity /9 3.05 Knowledge of the reasons for corrective actions as a 3.6 1 result of high fission product radioactivity levels in the RCS.

WE E EE E0 K/A Category Point Totals: 4 3 3 3 5 6 Group Point Total: 24 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE# / Name / Safety Function Kl K2 K3 Al A2 G K/A Topic(s) Imp. Points 000007 (CE/E02) Reactor Trip - Stabilization - Recovery /1 2.1 Knowledge of interrelationships between reactor trip 3.7 1 recovery and the components and functions of control and safety systems.

000008 Pressurizer Vapor Space Accident /3 2.4.11 Knowledge of abnormal condition procedures. SRO 3.6 1 000009 Small Break LOCA /3 1.02 Knowledge of the operational implications of the steam 4.2 1 tables during a small break LOCA.

~cW u~t... .........

000022 Loss of Reactor Coolant Makeup / 2 1.02 Knowledge of the operational implications of the 3.1 1 relationship of charging flow to pressure differential between charging and RCS.

000025 Loss of RHR System /4 1.01 Knowledge of the operational implications of a loss of 4.3 1 the RHR system during all modes of operation.

000027 Pressurizer Pressure Control System Malfunction / 3 1.02 Ability to operate and/or monitor SCR-controlled 3.0 1 heaters in manual mode during Pressurizer pressure control malfunctions.

000032 Loss of Source Range NI / 7 2.05 Ability to determine the loss of Source Range NI from 3.2 1 rapid survey of Control Room data. SRO 000033 Loss of Intermediate Range NI / 7 1.02 Ability to operate/monitor level trip bypass. 3.1 1 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (Cont.)

E/APE# / Name / Safety Function Kl K2 K3 Al A2 G K/A Topic(s) Imp. Points 000037 Steam Generator Tube Leak /3 1.11 Ability to operate and/or monitor Pressurizer level 3.3 1 indicator during a SG tube leak.

000038 Steam Generator Tube Rupture / 3 2.13 Ability to determine the magnitude of a Steam 3.7 1 Generator Tube Rupture. SRO 000054 (CE/E06) Loss of Main Feedwater /4 1.04 Ability to operate and/or monitor HPSI under total loss 4.5 1 of feedwater conditions.

000058 Loss of DC Power /6 3.01 Knowledge of the reasons for the use of DC control 3.7 1

_ power by the Diesel Generators.

000060 Accidental Gaseous Radwaste Release /9 2.3.9 Knowledge of the process for performing a 3.4 1

__ _ .containment purge. SRO 000061 ARM System Alarms / 7 1.01 Ability to operate and/or monitor automatic actuation of 3.6 1 Area Radiation Monitoring System alarms.

3.03 Knowing effects on plant operation of isolating certain 3.4 1 000065 Loss of Instrument Air / 8 equipment 2.2.11 Knowledge of the process for controlling temporary 3.4 1 CEIE09 Functional Recovery SRO 3 l 1 l 2 l 5 l 2 l 16 K/ACategory PointTotals:e NUREG-1021, Revision 8, Supplement 1

ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE# / Name / Safety Function Kl K2 K3 Al A2 G K/A Topic(s) Imp Points 000028 Pressurizer level Malfunction /2 2.03 Ability to determine and interpret the charging flow 3.3 1 indicator and controller. SRO 4 . E E gg% . E 000056 Loss of Off-site Power /6 1.32 Ability to operate the Pressurizer PORV handswitch. 3.4 1 CE/Al 6 Excess RCS Leakage /2 1.3 Knowledge of the operational Implications of the 3.5 1 annunciators and condition indicating signals and remedial actions for excess RCS leakage.

I....................

K/A Category Point Totals: 1 0 0 1 1 0 Group Point Total: 3 NUREG-1021, Revision 8, Supplement 1

( (a ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System #Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 001 Control Rod Drive 2.15 Ability to predict the impact of 4.2 1 Quadrant Power Tilt on the CEDS, and mitigate the consequences. SRO 003 Reactor Coolant Pump 6.02 Knowledge of the effect that a loss or 3.1 1 malfunction of RCP seals and seal

_____ _____ water will have on the RCPs.

004 Chemical and Volume Control 1.07 Knowledge of the physical 2.9 1 connections or cause/effect relationships between the CVCS and

__ NI systems.

013 Engineered Safety Features Actuation 6.01 Knowledge of the effect that a loss or 3.1 1 malfunction of sensors and detector will have on the ESFAS.

014 Rod Position Indication 5.01 Knowledge of the operational 3.0 1 implications of the reasons for differences between the RPIS and step counter.

015 Nuclear Instrumentation 4.02 Knowledge of rod motion inhibits. 3.9 2 1.06 Ability to predict and/or monitor 2.9 changes in parameters to prevent exceeding design limits due to fuel

- - - burnup.

017 In-core Temperature Monitor 1.01 Ability to predict and/or monitor 3.9 1 changes in parameters to prevent exceeding design limits due to core

__ _ _exit temperatures.

022 Containment Cooling 2.01 Knowledge of power supplies for 3.1 2 Containment Cooling Fans.

4.02 Ability to manually operate and 3.1 monitor the CCS pumps in the Control

__ _Room. __

NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group I (Cont.)

System # Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KWATopic(s) Imp. Points

... .E.

E e... EE EE 026 Containment Spray 1.01 Ability to predict and/or monitor 4.2 1 changes in parameters to prevent exceeding design limits due to Containment pressure.

056 Condensate 2.04 Ability to predict the impacts of a loss 2.8 1 of Condensate pumps on the Condensate system. Mitigate the consequences. SRO 059 Main Feedwater 3.03 Ability to monitor automatic operation 2.6 1 of the feedwater pump suction flow pressure.

061 Auxiliary/Emergency Feedwater 1.05 Knowledge of the physical 2.8 2 connections or cause/effect relationships between the AFW and Condensate systems.

3.01 Knowledge of the effect that a loss or 4.6 malfunction of the AFW system will have on the RCS.

063 DC Electrical Distribution 2.1.11 Knowledge of less than one hour 3.8 1 Technical Specification action statements for systems. SRO 068 Liquid Radwaste 1.07 Knowledge of the physical 2.9 1 connections or cause/effect relationships between the Liquid Radwaste System and the sources of

__ _ liquid wastes.

NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2lGroup 1 (Cont.)

System # Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 071 Waste Gas Disposal 5.04 Knowledge of the operational 3.1 1 implications of the relationship between hydrogen/oxygen concentrations to flammability.

072 Area Radiation Monitoring 2.3.10 Ability to perform procedures to 3.3 1 reduce excessive levels of radiation and guard against personnel

__ exposure. SRO K/A Category Point Totals: j3 l 1 1 1 1 l 2 1 3 2 1 1 2 Group Point Total: [19 NUREG-1021, Revision 8, Supplement I

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PWR SRO Examination Outline Form ES-401-3 ES-401 Plant Systems - Tier 2/Group 2 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points System Name KI 2.2.2 Ability to manipulate the control 3.5 1 002 Reactor Coolant console controls as required to operate the facility between shutdown and designated power levels.

5.01 Knowledge of the operational 3.3 1 006 Emergency Core Cooling implications of the effects of temperature on water level indications.

6.04 Knowledge of the effect that a loss or 3.2 1 010 Pressurizer Pressure Control malfunction of the Quench Tank will have on Pressurizer pressure control.

4.03 Ability to manually operate and/or 3.1 1 011 Pressurizer Level Control monitor the Pressurizer heaters in the Control Room.

4.02 Knowledge of RPS design features 4.3 1 012 Reactor Protection which provide automatic reactor trip when RPS setpoints are exceeded, and the basis for each.

4.03 Knowledge of NNIS design features 2.9 1 016 Non-nuclear Instrumentation

___ _____which provide input to control systems.

5.01 Knowledge of the operational 3.4 1 027 Containment Iodine Removal implications of the purpose of charcoal fiters.

029 Containment Purge 3.01 Knowledge of the effect that aloss or 3.1 1 malfunction of the Containment Purge System will have on Containment parameters.

033 Spent Fuel Pool Cooling 3.03 loss or Knowledge of the effect that aPool 3.3 1 malfunction of the Spent Fuel Cooling System will have on spent fuel temperature.

NUREG-1021, Revision 8, Supplement 1

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PWR SRO Examination Outline Form ES-401-3 ES-401 Plant Systems - Tier 2/Group 2 (Cont.)

K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points System # I Name Kl K2 K3 3.02 Ability to monitor automatic operation 3.1 1 034 Fuel Handling Equipment the Fuel Handling System, including

.of load limits.

6.01 Knowledge of the effect that a loss or 3.6 1 035 Steam Generator malfunction of the MSIVs will have on the S/Gs.

Knowledge of the physical 2.7 1 039 Main and Reheat Steam 1.09 connections and/or cause/effect relationships between the MRSS and the RMS.

3.03 Knowledge of the effect that a loss or 3.9 1 062 AC Electrical Distribution malfunction of the AC distribution

____ _ _ _system will have on the DC system.

1.02 Ability to predict and/or monitor 2.8 1 064 Emergency Diesel Generator changes in fuel consumption rate with chan es in EDG load.

WUn*111 X IF 10mgg 2.01 Ability to predict the impacts of a loss 3.2 1 075 Circulating Water of intake structure on the Circulating Water system. Correct, control, or

_____ _mitigate the consequences. SRO _

2.01 Ability to predict the impact of cross 3.2 1 079 Station Air connection with Instrument Air, and to mitigate the consequences. SRO _

NUREG-1021, Revision 8, Supplement 1

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PWR SRO Examination Outline Form ES-401-3 ES-401 Plant Systems - Tier 2/Group 2 (Cont.)

System # Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp Points 6.04 Knowledge of the effect that a loss or 2.9 1 086 Fire Protection malfunction of the fire, smoke, and heat detectors will have on the Fire Protection system.

KWA Category Point Totals: 1 J 3 2 J 2 3 1 2 11 1 1 GroupPointTotal: l 17 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 System #I Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 007 Pressurizer Relief/Quench Tank 3.01 Knowledge of the effect that a loss or 3.6 1 malfunction of the Quench Tank will

._ have on Containment.

008 Component Cooling Water 2.02 Knowledge of bus power supplies to 3.2 1 the CCW pumps, including emergency

____ ________ ________ __________backups.

041 Steam Dump/Turbine Bypass Control 4.01 Knowledge of the Steam Dump 3.3 1 System design features associated

~

Vito,+rnliinc ~ - Io 076 Service Water 2.1.7 Ability to evaluate plant performance 4.4 1 and make operational judgements I based on operating characteristics, reactor behavior, int.-Mr~fi- QW1 and instrument K/ACategory PointTotals: I 0 l 1 1 1 0 l 0 l 0 l 0 0 l 0 l 1 l Group Point Total: 4 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 (Cont.)

Plant-Specific Priorities System / Topic I Recommended Replacement for:.... Reason Points Il I

.9 i I Plant-Specific Priority Total: (limit 10) I NUREG-1021, Revision 8, Supplement 1

and Abilities Outline (Tier 3) Form ES-401-5

..S-401

-_S-401 Generic Knowledge Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Calvert Cliffs Date of Exam: 7/12/02 Exam Level: SRO Category 1 KIA# Topic Imp. Points 2.1. 30. Ability to locate and operate components, including local 3.4 1 controls.

Conduct of 2.1. 22. Ability to determine Mode Of Operation 3.3 1 Operations 2.1. 24. Ability to obtain and interpret station electrical and mechanical 3.1 1 drawings.

2.1. 20. Ability to execute procedure steps. SRO 1 4.2 NEt'eEmAm 2.1. 18. Ability to make accurate, clear and concise logs, records, status 3.0 1 boards, and rep ors.

Total5 Category 2 K/A # Topic Imp. Points 2.2. 25. Knowledge of the basis in Technical Specifications for Limiting 3.7 1

______ l Conditions of Operations and Safety Limits. SRO l l_ l Equipment 2.2. 30. Knowledge of RO duties in the control room during fuel handling 3.3 1 Control such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in l__l___ support of fueling operations, and supporting instrumentation.

2.2. 13. Knowledge of tagging and clearance procedures. 3.8 1 2.2. 31. Knowledge of procedures and limitations included in initial core 2.9 1 loading. SRO 2.2. 1. Ability to perform pre-startup procedures for the facility, including 3.7 1 operating those controls associated with plant equipment that could affect reactivity. ll _ l 2.2. 27. Knowledge of the refueling process. SRO 3.5 1 Total I 6  !

NUREG-1021, Revision 8, Supplement 1

-_S-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5

..S-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Category 3 K/A # Topic Imp. Points 2.3. 1. Knowledge of 10-CFR-20 and related facility radiation control 3.0 1 requirements. SRO Radiation 2.3. 9. Knowledge of the process for performing a containment purge. 3.4 1 Control SRO 2.3. 8. Knowledge of the process for performing a planned radioactive 3.2 1 release. SRO 2.3. 11. Ability to control radiation releases. 3.2 1 Total 4 Tier 3 Point Total 17 NUREG-1021, Revision 8, Supplement 1

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ES-401 Record of Rejected K/As Form ES-401-10 Tier / Group Randomly Selected K/A Reason for Rejection

(/ca)O AAi 0 qY Calveftc.S "&e,! rc ,1v_

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Ji~~~7" j - 'A~ti.c Lt,QA (\,c f-6~ 3~U- 4&, P 13 1A

____ ___ ;b3 tlisv or

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NUREG-1021, Revision 8, Supplement 1 46 of 46

ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Calvert Cliffs Date of Exam: 7/12/02 Exam Level: RO Tier Group K/A Category Points Point Total K K K KlK lK A A lAlA G 1 2 3 4 5 6 1 2 3 4 *

1. 1 2 2 2 3 4 3 16 Emergency & 2 4 2 2 3 3 7 / 3 17 Abnormal 3 1 0 0 1 1 0 Plant__ _ _ _ _

Evolutions Tier 7 4 4 7 8 6 36 Totals

2. 1 5 1 4 1 2 3 1 1 1 23 Plant 2 1 0 4 2 2 3 2 3 0 1 2 20 Systems 3 0 1 1 1 1 1 1 0 1 0 1 8 Tier 6 2 9 4 5 6 5 6 2 2 4 51 Totals I Cat 1 Cat 2 Cat 3 Cat 4
3. Generic Knowledge and Abilities 4 4 3 2 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (ie., the "Tier Totals" in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by + 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the KIA numbers, a brief description of each topic, the topic's importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities.

Enter the tier totals for each category in the table above.

NUREG-1021, Revision 8, Supplement 1

( ( I ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE# / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000005 Inoperable/Stuck Control Rod /1 2.01 Knowledge of the interrelationships between an 2.5 1 inoperable/stuck control rod and the controllers and positioners.

000015/17 RCP Malfunctions / 4 2.10 Knowledge of the interrelationships between RCP 2.8 1 malfunctions and the RCP indicators and controls.

CE/A13 Natural Circulation / 4 3.4 Knowledge of the reasons for the RO and SRO to 3.1 1 function as a team such that procedures are adhered to and license limitations are not violated, during

__ natural circulation operations.

000024 Emergency Boration / 1 2.03 Ability to determine and Interpret the correlation 2.9 1 between boric acid controller setpoint and boric acid flow.

000026 Loss of Component Cooling Water / 8 1.06 Ability to control and/or monitor flowrates to 2.9 1 components cooled by CCW, during loss of Component Cooling Water 000027 Pressurizer Pressure Control System Malfunction / 3 1.02 Ability to operate and/or monitor SCR-controlled 3.1 1 heaters in manual mode during Pressurizer pressure control malfunctions.

000040 (CE/E05) Steam Line Rupture - Excessive Heat Transfer /4 2.2.4 Ability to explain variations in control board layouts, 2.8 1 systems, instrumentation and procedural actions between units.

CE/Al1 RCS Overcooling - PTS /4 1.30 Knowledge of the operational implications of 3.0 1 annunciators, condition indicating signals, and remedial actions, as they apply to RCS overcooling.

000051 Loss of Condenser Vacuum / 4 2.02 Ability to determine and interpret condenser vacuum 3.9 1 conditions requiring a reactor and/or turbine trip.

000055 Station Blackout / 6 1.01 Knowledge of the operational impacts of battery 3.3 1 discharge rates on capacity.

000057 Loss of Vital AC Electrical Instrument Bus /6 2.16 Ability to determine and interpret normal and abnormal 3.0 1 Pressurizer levels for various modes of plant operation,

_ _ _ __.______ _ . .. as they apply to a loss of a Vital AC Instrument Bus. __

UUUU02 LOSS Ot Nuclear Service Water / 4 2.1.8 Ability to coordinate personnel activities outside the 3.8 1 cnntrnl rnnm NUREG-1021, Revision 8, Supplement 1

(

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (Cont.)

E/APE# / Name / Safety Function Ki K2 K3 Al A2 G K/A Topic(s) Imp. Points 000068 Control Room Evacuation /8 2.08 Ability to determine and interpret SG pressure during 3.9 1 Control Room evacuation.

000069 Loss of Containment Integrity / 5 1.03 Ability to operate and/or monitor fluid systems 2.8 1 penetrating containment, as they apply to a loss of

__ Containment integrity.

000074 Inadequate Core Cooling / 4 2.4.6 Knowledge of symptom based EOP mitigation 3.1 1 strategies.

Ma 000076 High Reactor Coolant Activity /9 am Xgm 3.05 Knowledge of the reasons for corrective actions as a 2.9 1 result of high fission product radioactivity levels in the RCS.

K/A Category Point Totals: 2 2 2 3 l4 3 Group Point Total: 16 NUREG-1021, Revision 8, Supplement 1

I (

(I ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE# I/Name I Safety Function Kl K2 K3 Al A2 G KA Topic(s) imp. Points 000001 Continuous Rod Withdrawal / 1 2.4.1 Knowledge of EOP entry conditions and immediate 4.3 1 action steps.

000003 Dropped Control Rod /1 1.04 Knowledge of the operational implications of the effects 3.1 1 of power level and control rod position, on flux.

uuuuur tuhI/uz) reatr I rip - Stabiiization - Recovery /1 2.1 Knowledge of interrelationships between reactor trip 3.3 j 1 recovery and the components and functions of control and safety systems.

UUUULz LOSS Of Reactor Coolant Makeup / 2 1.02 Knowledge of the operational implications of the relationship of charging flow to pressure differential I Ibetween charging and RCS.

Knowledge of the operational implications of a loss of I I I I Ithe PHR sLstem rdunrnn all --nd.c I .-.-. -

rf nrstn

. lUUC§ItlUII.

NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (Cont.)

E/APE# / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000029 Anticipated Transient W/O Scram /1 3.10 Knowledge of the reasons for manual rod insertion 4.1 1 during an ATWS.

000032 Loss of Source Range NI /7 . 2.05 Ability to determine the nature of a loss of Source 2.9 1 Range NI from rapid survey of Control Room data.

000037 Steam Generator Tube Leak /3 1.11 Ability to operate and/or monitor Pressurizer level 3.4 1

___ _ indicator during a SG tube leak.

000038 Steam Generator Tube Rupture /3 2.13 Ability to determine the magnitude of a Steam 3.1 1 Generator Tube Rupture.

000054 (CE/E06) Loss of Main Feedwater /4 1.04 Ability to operate and/or monitor HPSI under total loss 4.4 1 of feedwater conditions.

000058 Loss of DC Power /6 3.01 Knowledge of the reasons for the use of DC control 3.4 1 power by the Diesel Generators.

000059 Accidental Liquid RadWaste Release / 9 2.02 Knowledge of the interrelationships between the 2.7 1

__accidental release and the radioactive gas monitors.

000060 Accidental Gaseous Radwaste Release / 9 2.3.9 Knowledge of the process for performing a 2.5 1 containment purge.

000061 ARM System Alarms / 7 1.01 Ability to operate and/or monitor automatic actuation of 3.6 1 Area Radiation Monitoring System alarms.

K/A Category Point Totals: 4 2 2 3 3 3 Group Point Total: 17 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE# / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points 000028 Pressurizer level Malfunction /2 2.03 Ability to determine and interpret the charging flow 2.8 1 indicator and controller.

000056 Loss of Off-site Power /6 1.32 Ability to operate the Pressurizer PORV handswitch. 3.4 1 CE/Al 6 Excess RCS Leakage7.'g E

/2 W....'

13Knowledge 4' '" g.4 of the operational implications of the3. 1 CEAM6EcesRC ekaer213mnwedgel annunciatorsoftthesoperationa and condition indicating ImpSlickatinp fte.3 signals and K/AaCategory Point Totals: l1 l0 l 0 1 PointTotal:

s n cGroup s 3 NUREG-1 021, Revision 8, Supplement 1

(I (

PWR RO Examination Outline Form ES-401-4 ES-401 Plant Systems - Tier 2/Group 1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points System #I Name KI 1.04 Knowledge of the physical 3.2 2 001 Control Rod Drive connections or cause/effect relationships between the CEDS and RCS.

2.15 Ability to predict the impact of 3.6 Quadrant Power Tilt on the CEDS, and mitigate the consequences.

5.04 Knowledge of the operational 3.2 2 003 Reactor Coolant Pump implications of RCP shutdown on secondary parameters.

6.02 Knowledge of the effect that a loss or 2.7 malfunction of RCP seals and bleedoff will have on the RCPs.

1.07 Knowledge of the physical 2.6 1 004 Chemical and Volume Control connections or cause/effect relationships between the CVCS and

__ NI systems.

3.03 Knowledge of the effect that a loss or 4.3 2 013 Engineered Safety Features Actuation malfunction of the ESFAS will have on Containment.

6.01 Knowledge of the effect that a loss or 2.7 malfunction of sensors and detector will have on the ESFAS.

4.02 Knowledge of rod motion inhibits. 3.7 2 015 Nuclear Instrumentation 1.06 Ability to predict and/or monitor 2.5 changes in parameters to prevent exceeding design limits due to fuel

___burnup. ____

NUREG-1021, Revision 8, Supplement I

( ( (;

PWR RO Examination Outline Form ES-401-4 V ES-401 Plant Systems - Tier 2/Group I (Cont.)

Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points System # Name 3.01 Knowledge of the effect that a loss or 3.5 2 017 In-core Temperature Monitor malfunction of the ITM will have on natural circulation indications.

1.01 Ability to predict and/or monitor 3.7 changes in parameters to prevent exceeding design limits associated with core exit temperatures.

OfIvowr eUJ1II enlvic n2 022 Containment Cooling 2.01 Cnowlenent UA~~I^

_ .~NUW~U n

aow Co F bUFF11s. 1 v.v Containment Cooling Fans.

I I I -I I - i i _ 1 _ b~l t-om n al~ p r t n 4.0~2A~~~ J.=.

4.02 Ability to manually operate and monitor the CCS pumps in the Control R,

Knowledge of the physical z 056 Condensate connections or cause/effect relationships between the Condensate and the Main Feedwater systems. 2.6 Ability to predict the impacts of a loss 2.6 of Condensate pumps on the Condensate system. Mitigate the

^U- -_

Ability to monitor automatic operation 2.5 059 Main Feedwater of the feedwater pump suction flow pressure.

Knowledge of the physical 2.6 2 061 Auxiliary/Emergency Feedwater connections or cause/effect relationships between the AFW and Condensate systems.

Knowledge of the effect that a loss or 4.4 malfunction of the AFW system will have on the RCS.

NUREG-1021, Revision 8, Supplement I

( ( (

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 (Cont.)

System # Name KI K2 K3 K4 KS K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 068 Liquid Radwaste 1.07 Knowledge of the physical 2.7 1 connections or causeleffect relationships between the Liquid Radwaste System and the sources of liquid wastes.

071 Waste Gas Disposal 5.04 Knowledge of the operational 2.5 2 implications of the relationship between hydrogen/oxygen concentrations to flammability.

2.02 Ability to predict the impact of a loss of 2.5 release monitors,radiation, gas flow rate and totalize on the Waste Gas Disposal System, and to mitigate the consequences.

072 Area Radiation Monitoring 3.01 Knowledge of the effect that a loss or 3.2 2 malfunction of the ARM system will have on Containment Ventilation Isolation.

2.3.10 Ability to perform procedures to 2.9 reduce excessive levels of radiation and guard against personnel exposure.

5 1

4 1 2 2 2 3 1 1 1 Group Point Total: 23 K/A Category Point Totals:

NUREG-1021, Revision 8, Supplement I

( ( (

ES-401 PWR RO Examination Outline Form ES-401 -4 Plant Systems - Tier 2/Group 2 System # Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 002 Reactor Coolant 2.2.2 Ability to manipulate the control 4.0 1 console controls as required to operate the facility between shutdown and designated power levels.

006 Emergency Core Cooling 5.01 Knowledge of the operational 2.8 1 implications of the effects of temperature on water level

__ indications.

010 Pressurizer Pressure Control 6.04 Knowledge of the effect that a loss or 2.9 1 malfunction of the Quench Tank will have on Pressurizer pressure control.

011 Pressurizer Level Control 4.03 Ability to manually operate and/or 3.3 1 monitor the Pressurizer heaters in the Control Room.

012 Reactor Protection 4.02 Knowledge of RPS design features 3.9 1 which provide automatic reactor trip when RPS setpoints are exceeded, and the basis for each.

014 Rod Position Indication 5.01 Knowledge of the operational 2.7 1 implications of the reasons for differences between the RPIS and step counter.

016 Non-nuclear Instrumentation 4.03 Knowledge of NNIS design features 2.8 1 which provide input to control systems.

026 Containment Spray 1.01 Ability to predict and/or monitor 3.9 1 changes in parameters to prevent exceeding design limits due to Containment pressure.

029 Containment Purge 3.01 Knowledge of the effect that a loss or 2.9 1 malfunction of the Containment Purge System will have on Containment parameters.

033 Spent Fuel Pool Cooling 3.03 Knowledge of the effect that a loss or 3.0 1 malfunction of the Spent Fuel Pool Cooling System will have on spent fuel temperature. _

NUREG-1 021, Revision 8, Supplement I

( ( (

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 (Cont.)

System # Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 035 Steam Generator 6.01 Knowledge of the effect that a loss or 3.2 1 malfunction of the MSIVs will have on

__ the S/Gs.

039 Main and Reheat Steam 1.09 Knowledge of the physical 2.7 1 connections and/or cause/effect relationships between the MRSS and the RMS.

055 Condenser Air Removal 3.01 Knowledge of the effect that a loss or 2.5 1 malfunction of the CAR system will have on the Main Condenser.

062 AC Electrical Distribution 3.03 Knowledge of the effect that a loss or 3.7 1 malfunction of the AC distribution system will have on the DC system.

063 DC Electrical Distribution 2.1.11 Knowledge of less than one hour 3.0 1 Technical Specification action statements for systems.

064 Emergency Diesel Generator 1.02 Ability to predict and/or monitor 2.5 1 changes in fuel consumption rate with

__ _ changes in EDG load.

073 Process Radiation Monitoring 2.01 Ability to predict the impacts of an 2.5 1 erratic or failed power supply on the PRMVS. Correct, control, or mitigate the consequences.

075 Circulating Water 2.01 Ability to predict the impacts of a loss 3.0 1 of intake structure on the Circulating Water system. Correct, control, or mitigate the consequences.

NUREG-1021, Revision 8, Supplement 1

( ( (

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 (Cont.)

System # Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KWA Topic(s) Imp. Points 079 Station Air 2.01 Ability to predict the impact of cross 2.9 1 connection with Instrument Air, and to I III mitigate the consequences.

086 Fire Protection 6.04 Knowledge of the effect that a loss or 2.6 1 malfunction of the fire, smoke, and heat detectors will have on the Fire Protection system.

K/A Category Point Totals: 4l[3[ 1 I20 1GroGrouPototal:

NUREG-1021, Revision 8, Supplement 1

( ( (

l ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 System #/ Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KWA Topic(s) Imp. Points 005 Residual Heat Removal 6.03 Knowledge of the effect that a loss or 2.5 1 malfunction of an RHR Heat Exchanger will have on RHR System.

007 Pressurizer Relief/Quench Tank 3.01 Knowledge of the effect that a loss or 3.3 1 malfunction of the Quench Tank will have on Containment.

008 Component Cooling Water 2.02 Knowledge of bus power supplies to 3.0 1 the CCW pumps, including emergency

__ backups.

027 Containment Iodine Removal 5.01 Knowledge of the operational 3.1 1 implications of the purpose of charcoal filters.

E E loll 034 Fuel Handling Equipment 3.02 Ability to monitor automatic operation 2.5 1 of the Fuel Handling System, including

__ load limits.

041 Steam Dump/Turbine Bypass Control 4.01 Knowledge of the Steam Dump 2.9 1 System design features associated with the Reactor Regulating System.

045 Main Turbine Generator 1.06 Ability to predict and/or monitor the 3.3 1 expected response of secondary plant

___ _ parameters following a T/G trip.

076 Service Water 2.1.7 Ability to evaluate plant performance 3.7 1 and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.

lo 0 ...... ...U N _ w K/A Category Point Totals: o 1 1 1 1 1 1 0 1 0 1 Group Point Total: 8 NUREG-1021, Revision 8, Supplement I

I

( C ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 (Cont.)

Plant-Specific Priorities System / Topic Recommended Replacement for:.... Reason Points t I t I1 t I t I-i i I i I i i I I I _________________________________________

Plant-Specific Priority Total: (limit 10) 1 NUREG-1021, Revision 8, Supplement 1

-ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5

£-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Calvert Cliffs Date of Exam: 7/12/02 Exam Level: RO Category I K/A # M 2.1. 30. Abilityto locate and operate components, including local 3.9 1 controls.

Conduct of E1g1=

Operations ~~~.~:" 4' 2.1. 24. Ability to obtain and interpret station electrical and mechanical 1 drawings. 2.8 2.1. 20. Ability to execute procedure steps. 1 4.3 2.. 18. Ability to make accurate, clear and concise logs, records, status 1 boards, and reports. 2.9 Total 1 4 54 ~ .54.~ ~ .. 552.54 Category 2 K/A #Topic Imp. Points 2.2. 11. Knowledge of process for controlling temporary changes. 25 1

". __S N-

-quipment 2.2. 30. Knowledge of RO duties in the control room during fuel handling I Control such as alamms from fuel handling area, communication with fuel 3.6 storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

2.2. 13. Knowledge of tagging and clearance procedures. 40 1 2.2. 1. Ability to perform pre-startup procedures for the facility, including 3.7 1 operating those controls associated with plant equipment that could affect reactivits.

Total = 4 NUREG-1021, Revision 8, Supplement 1

=-S-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Calvert Cliffs Date of Exam: 7/12/02 Exam Level: RO Category 3 K/A #Topic Imp. Points 2.3. 1. Knowledge of 10-CFR-20 and related facility radiation control 2.6 1 requirements.

Radiation 2.3. 9. Knowledge of the process for performing a containment purge. 2.5 1 Control 2.3 11. Ab ility to control radiation releases. 2.7 1

.. , 3 Category4 l K/A# I Topic I Imp. I Points I I

I Tier 3 Point Total (RO) l 13 NUREG-1021, Revision 8, Supplement 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs 1 and 2 Date of Examination: 7/15/02 Examination Level SRO Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject Description 1. ONE Administrative JPM, OR

2. TWO Administrative Questions A. 1 Shift Staffing JPM K/A 2.1.5 /13.4 Ability to locate and use procedures requirements and directives related to shift staffing.

Security Question K/A 2.1.13 I/ 2.9 Knowledge of facility requirements for controlling vital/controlled area access Question K/A 2.1.14 113.3 Knowledge of system status criteria which require notification of plant personnel A.2 Maintenance Question K/A 2.2.24 113.8 Ability to analyze the effect of maintenance activities on LCO status.

Question K/A 2.2.17 /13.5 Knowledge of the process for managing maintenance activities during power operations.

A.3 Knowledge of facility JPM K/A 2.3.2 H 2.9 Requirements for performing a task ALARA program in the Aux. Building A.4 Emergency action JPM K/A 2.4.41 114.1 Knowledge of emergency action levels and levels and classifications classifications

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs 1 and 2 Date of Examination: 7/15/02 Examination Level: RO Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject Description 3. ONE Administrative JPM, OR

4. TWO Administrative Questions A. 1 Plant parameter JPM K/A 2.1.25 / 2.8 ability to obtain and interpret verification station reference materials such as graphs, monographs, and tables which contain performance data

-perform shutdown margin verification.

Shift turnover JPM K/A 2.1.31 114.2 ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Complete Checklists from NO-1-207.

A.2 Tagging and Question K/A 2.2.13. //3.6 Qualifications to pull Control clearances Room panel fuses/slide links Question K/A 2.2.13. // 3.6 Effects of tagging activities on Control Room Annunciators A.3 Knowledge of facility JPM K/A 2.3.2/I 2.5 Requirements for performing a task ALARA program in the Aux. Building A.4 Emergency JPM K/A 2.4.43 //2.8 Knowledge of emergency communications communications system and techniques.

ES-301 Control Room and Facility Walk-Through Test Outline Form ES-301-2 Facility: Calvert Cliffs Units 1 and 2 Date of Examination:July 15, 2002 Exam Level: RO/SRO(l) Operating Test No: 1 B. 1 Control Room Systems System / JPM Title Type Safety Code* Function

a. 062 Parallel OC Diesel to 24 4KV Bus D/ S 6 A4.06 / 3.9
b. 059 Recover From automatic feedwater isolation S / D/ A 4 (secondary)

A4.11 //3.4

c. 013 Respond to an inadvertent CIS S/M/ A 2 A2.06 //3.7
d. 071. Waste Gas Discharge RMS checks S./ N / A 9 A3.03 H 3.6
e. 002 Use procedures to correct Loss of Forced S/N/L 4 (primary)

Circulation A2.0311 4.1 f 015 Monitor DNB S/N 7

. A1.05 113.7

g. 007 Bleed and feed operation to cool the Quench S/N 5 Al.Ol thru Tank per 01-lB 1.03 // 2.9, 2.7, 2.6 B.2 Facility Walk-Through
a. 029 Align system for alternate containment purge N/ R/L 8 per 01-36 A2.03 / 2.7
b. 014 Monitor CEA positions per AOP 7H, alternate N/A 1 method. A2.02 113.1
c. 061 Take local control of AFW pumps to feed N 4 (secondary)

S/Gs A2.04 H13.4

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrolroom, (S)imulator, (L)ow-Power, (R)CA

ES-301 Control Room and Facility Walk-Through Test Outline Form ES-301-2 Facility: Calvert Cliffs Units 1 and 2 Date of Examination:Julv 15, 2002 Exam Level: SRO(U) Operating Test No: 1 B. I Control Room Systems System / JPM Title Type Safety Code* Function

a. 062 Parallel OC Diesel to 24 4KV Bus D/S 6 A4.06 113.9
b. 071. Waste Gas Discharge RMS checks S./N/A 9 A3.03 /13.8
c. 013 Respond to an inadvertent CIS D/S 2 A2.061H4.0 d

e.

f.

g.

B.2 Facility Walk-Through

a. 029 Align system for alternate containment purge N/R /L 8 per 01-36 A2.03 /t3.1
b. 014 Monitor CEA positions per AOP 7H, alternate N/ A 1 method. A2.02 //3.1 C.
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrolroom, (S)imulator, (L)ow-Power, (R)CA

Simulation Facility Calvert Cliffs Scenario No.: 1 (Spare) OpTestNo.: 1 Examiners: Operators: SRO RO BOP To evaluate the applicants' ability to conduct a unit power increase, to implement the ARMs, Ols, AOPs, as Objectives: appropriate, for malfunctioning systems and/or controls including failure of 11 CCW Pp. the PZR pressure control channel and selector switch, an RCP seal and the ADV controller. After the ADV controller fails the remaining seals fail on the affected RCP resulting in an RCS leak. After EOP-0 is entered, the RCS leak causes a SIAS actuation. SIAS 'A' fails to actuate requiring 11 or 12 HPSI Pump to be started manually to establish HPSI flow. As EOP-0 progresses, a steam leak begins in CNMNT from 12 SG requiring EOP-8 be implemented. 11 AFW pump will trip upon start and AFW will have to be established by starting 12 or 13 AFW Pump.

Initial Conditions: The plant is at 100% Power, EOC 12 Main CPU is failed for 12 SG DFWCS 11 CCW Head Tank Makeup CV is isolated due to leakby.

13 HPSI Pp is OOS.

13 CCW Pp is OOS INSTR AIR COMPR(S) alarm (K-25) hanging.

Turnover: Present plant conditions: 100% power, MOC; Unit 2 is in MODE 5 - no CW Pps and 23 AFW Pp unavailable.

Power history: 100% power for previous 68 days.

Equipment out of service:

1) 12 Main CPU is failed for 12 SG DFWCS. System engineer is investigating.
2) 13 HPSI Pp motor bearing failure during STP. It is disassembled, expected to be returned to service in 2 days. T.S. 3.5.2 Action Statement entered 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago.
3) 11 CCW Head Tank Makeup CV is isolated due to leakby.
4) 13 CCW Pp has a broken shaft, expected repair tomorrow-noon.
5) Alarm K-25 INSTR AIR COMPR(S) is hanging. No problems with the compressors, I & C is investigating, alarm card has been swapped out.

Surveillances due: STP-0-29 (CEA Movement Test) due by end of shift. SM will discuss with CRS shortly after turnover.

Instructions for shift:

1) Maintain 100% power.

0201.dococ

Event I Malf. I Event I Event No. No. Type* Description Preload FWOOL_03 12 Main CPU on 12 SG DFWCS OOS.

ESFA002_01 SIAS 'A' fails to actuate automatically and manually.

ESFAOO1_01 SI 002_03 13 HPSI Pp OOS.

CCW002_03 13 CCW Pp OOS.

PNL OVD Pressurizer Press Controller Selector Switch in channel X.

PNL OVR INSTR AIR COMPR(S) alarm hanging.

K-25 CCW002_01 C CRO About 3 minutes after the crew takes the watch, 11 CCW Pp trips. The CRO will acknowledge the alarms, inform the CRS and refer to the ARM. The crew will check for common mode failure and the CRS will direct the CRO to start 12 CCW Pp. The CRS should refer to AOP-7C and T.S. 3.7.5. The CRS contacts the OWC for assistance.

2 RCS023_01 I RO PRZR Press Channel 1OX fails high. The RO should acknowledge the alarms, (high) inform the CRS and refer to the ARM. The RO should note the lowering RCS pressure and the open spray valves. Pressure control should be shifted to channel Y and the spray valves verified shut. The RO should note the spray valves did not shut. The CRS should direct the spray controller be taken to manual and the spray valves closed. The CRS should contact the OWC for assistance.

3 RCS011_01 C RO Next, the lower seal (first stage) fails on 1 IA RCP. The RO should note the (0-100% over alarm, inform the CRS and refer to the ARM. The crew should determine the 3 min) lower seal on 1lA RCP has failed. The OMC and system engineer should be contacted.

. MS015 I CRO Two minutes after the notifications have been made the ADV controller fails (high) high causing the ADVs to open. The CRO will inform the CRS. The CRS should direct the CRO to take manual control of the ADVs and shut them. The RO should maintain reactor power less than 100%. The CRS should refer to AOP-7K. The CRS should contact the OWC for assistance.

5 RCS012_01 R RO After the CRS has referenced AOP-7K, the 1 IA RCP middle seal fails. The (0-100% over N CRO crew should implement ARM guidance and begin an expeditious shutdown.

2 min) The CRS should refer to OP-3 for guidance on for the shutdown.

6 RCS013_01 M All After power has been reduced at least 5%, the 11A upper seal begins to fail (100% over 2 followed shortly thereafter by the failure of the vapor seal. With all the seals min) failed RCS leakage begins via the seals. The CRS will trip the unit based on high RCP seal temperature and EOP-0 implemented. When SIAS actuates, RCS014_01 train A fails to automatically and manually initiate. To establish HPSI flow 11 (100% over 4 or 12 IHPSI must be started manually.

min) 7 MSO1O_02 M All After the first pass through the safety functions is complete, a steam break in (0-25% over CNMNT begins. When AFW is initiated 11 AFW pump trips. AFW can be 3 min) established using either 12 or 13 AFW pump. The CRS should recognize two events are taking place and implement EOP-8. After the Success Paths have AFW001_01 been selected and 12 SG isolated, the scenario can be terminated.

  • (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 0201.dococ

SCENARIO 1 OVERVIEW The candidates will take the shift at 100% power with instructions maintain.

After the crew has taken the shift, 11 CCW Pp trips. The CRO will acknowledge the alarms, inform the CRS and refer to the ARM. The crew will check for common mode failure and the CRS will direct the CRO to start 12 CCW Pp. The CRS should refer to AOP-7C and T.S. 3.7.5. The CRS contacts the OWC for assistance.

Several minutes later, PRZR Press Channel 1OOX fails high. The RO should acknowledge the alarms, inform the CRS and refer to the ARM. The RO should note the lowering RCS pressure and the open spray valves. Pressure control should be shifted to channel Y and the spray valves verified shut. The RO should note the spray valves did not shut. The CRS should direct the spray controller be taken to manual and the spray valves closed. Once the spray valves are closed, the RO should stabilize RCS pressure. The CRS should contact the OWC for assistance.

About 3 minutes after the crew has regained RCS pressure control, the lower seal (first stage) fails on 11A RCP.

The RO should note the alarm, inform the CRS and refer to the ARM. The crew should determine the lower seal on 1 A RCP has failed and monitor RCP parameters. The OWC and system engineer should be contacted.

Two minutes after the notifications have been made the ADV controller fails high causing the ADVs to open. The CRO diagnoses the open ADVs and inform the CRS. The CRS should direct the CRO to take manual control of the ADVs and shut them. The RO should maintain reactor power less than 100%. The CRS should refer to AOP-7K. The CRS contacts the OWC for assistance.

After the CRS has referenced AOP-7K, the 1IA RCP middle seal fails. The crew should implement ARM guidance and begin an expeditious shutdown in accordance with OP-3. The CRS should refer to OP-3 and direct the unit shutdown at a rate less than 300/o/hour. The appropriate notifications should be made.

After power has been reduced at least 5%/o, the 11A RCP upper seal begins to fail followed shortly thereafter by the failure of the vapor seal. With all the seals failed RCS leakage begins via the seals. The CRS will trip the unit based on high RCP Controlled Bleed Off temperature and EOP-0 implemented. When SIAS actuates, train 'A' fails to initiate automatically and manually. To establish HPSI flow 11 or 12 HPSI must be started manually.

After the first pass through the safety functions is complete, a steam break in CNMNT begins. When AFW is initiated 11 AFW pump trips. AFW can be established using either 12 or 13 AFW pump. The CRS should recognize two events are taking place and implement EOP-8. The crew will determine the appropriate Success Path for each Safety Function. After the Success Paths have been selected and 12 SG isolated, the scenario can be terminated.

0201.dococ

s' XT . I

. .p Simulation Facility Calvert Cliffs Scenano No.: 2 up IULesINU.. 1 Examiners: Operators: SRO RO BOP To evaluate the applicants' ability to conduct a unit power reduction and to implement the ARMs, Ols, AOPs, Objectives: as appropriate, for malfunctioning systems and/or controls including a failure of the Hotwell Level Controller, 11 Circulating Water Pp. and a VCT Level Transmitter with a failure of CVC-501-MOV to reopen, preventing realignment to the VCT. This scenario also evaluates the applicant's ability to respond to a leaking PORV and a condenser waterbox tube rupture requiring a rapid downpower to a target value of 300 MWe. Multiple CEA drops will require a reactor trip but an ATWS condition exists. In EOP-0 a SGTR begins in 12 SG. As the crew attempts to isolate 12 SG, 12 MSIV will fail to close from the Control Room and have to be closed locally by dumping the hydraulic fluid.

Initial Conditions: The plant is at 100% Power, MOC 13 HPSI Pp is OOS.

13 CCWPp is OOS 11 CCW Head Tank Makeup CV is isolated due to leakby.

INSTR AIR COMPR(S) alarm (K-25) hanging.

Turnover: Present plant conditions: 100% power, MOC; Unit 2 is in MODE 5 - no CW Pps and 23 AFW Pp unavailable.

Power history: 100% power for previous 68 days.

Equipment out of service:

1) 13 HPSI Pp motor bearing failure during STP. It is disassembled, expected to be returned to service in 2 days. T.S. 3.5.2 Action Statement entered 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago.
2) 13 CCW Pp has a broken shaft, expected repair tomorrow-noon.
3) 11 CCW Head Tank Makeup CV is isolated due to leakby.
4) Alarm K-25 INSTR AIR COMPR(S) is hanging. No problems with the compressors, I & C is investigating, alarm card has been swapped out.

Surveillances due:

None Instructions for shift:

Maintain 100% Power.

0202.doc 1

Event I Malf. Event [ Event No. j No. j _

Type*_ Description Preload S1002_03 13 HPSI OOS.

CCW002_03 13 CCW Pump OOS.

PNL OVR 12 MSIV fails to close.

PNL OVR HS for VCT remains in SHUT.

RPS005 ATWS.

RPS006 PNL OVR INSTR AIR COMPR(S) alarm hanging.

(K-25)

I CDO02 I CRO Several minutes after the crew takes the watch, the Hotwell Level Cont. (4405)

(high) fails high, dumping fully to the CST. The CRO will receive the Hotwell Level Low alarm, will inform the CRS and refer to the ARM. The CRO should determine 4405 has failed high, take manual control and restore hotwell level.

The OWC should be contacted for assistance.

2 CW001_01 C CRO After hotwell level control has been reestablished, 11 CW Pp trips. The crew will notice this via computer alarm. The CRS should direct the CRO to investigate. They will implement AOP-7L. The crew should monitor condenser delta T. The OWC should be contacted for assistance.

3 CVCS0O9 I RO Next, VCT Level transmitter LT-227 fails low. This causes Chg. Pp suction to (LO) shift to the RWT. The RO should inform the CRS. The CRS should direct the RO to shift Chg. Pp suction back to the VCT. RO should note the failure of VCT outlet (501-MOV) to reopen. The CRS should direct the plant boration be stopped by placing all Charging Pumps in PTL. The ABO may be dispatched to open CVC-501 locally. The crew should isolate letdown and set up charging to cycle on the backup pump. The OWC should be contacted for assistance.

'4 RCS021 C RO Next, PORV-402 starts to leak. The RO should acknowledge the Quench Tank (5% over 2 alarm and note on the acoustic monitor the indicated leakage. The ARM will be min) referenced and the CRS will direct the PORV Block Valve, RC-403 -MOV be closed. The CRS will refer to T. S. 3.4.11. The OWC will be conducted for assistance.

5 CDO09_04 R RO After T.S. have been addressed, a condenser tube ruptures in 12B waterbox.

N CRO This will first be noticed with a Turbine Plant Sample Alarm. Chemistry and the TBO should be dispatched. Once a tube rupture has been determined in 12B waterbox a rapid power reduction to 300MW should be started and water dropped in the box. Chemistry and other appropriate plant management notifications should be made.

6 CEDS012_35 M ALL After power has been reduced at least 5%/o, CEA 35 drops into the core. The CEDS012_37 crew should reduce turbine load to maintain Tc on program then about a minute later a 2nd CEA drops. The CRS should direct the unit be tripped and EOP-0 implemented. When the RO attempts to trip the reactor an ATWS condition exists and the RO must take ATWS actions.

7 MS002_02 M ALL During the performance of EOP-0 a SGTR begins in 12 SG. The crew is expected to diagnose the SGTR and implement EOP-6. While in EOP-6 the crew will cooldown to less than 515°F Th and isolate 12 SG. When the CRO attempts to close 12 MSIV it will not close and the ABO will be dispatched to close it locally. The scenario can be terminated after 12 SG is isolated.

\ (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 0202.doc 2

SCENARIO 2 OVERVIEW The candidates will take the shift at 100% power, MOL.

After the crew takes the watch, the Hotwell Level Controller (4405) fails high, dumping fully to the CST. The CRO will receive the Hotwell Level Low alarm, will inform the CRS and refer to the ARM. The CRO should determine 4405 has failed high, take manual control and restore hotwell level. The OWC should be contacted for assistance.

After hotwell level control has been reestablished, 11 CW Pp trips. The crew will notice this via computer alarm.

The CRS should direct the CRO to investigate. They will implement AOP-7L. The crew should monitor condenser delta T. The CRO will isolate the waterbox using guidance from OI-14. The OWC should be contacted for assistance.

Next, VCT Level transmitter LT-227 fails low. This causes Chg. Pp suction to shift to the RWT. The RO informs the CRS. The CRS directs the RO to shift Chg. Pp suction back to the VCT. RO should note the failure of VCT outlet (501-MOV) to reopen. The CRS should direct the plant boration be stopped by placing all Charging Pumps in PTL. The ABO may be dispatched to open CVC-501-MOV locally. The crew should isolate letdown and set up charging to cycle on the backup pump. The OWC should be contacted for assistance.

Next, PORV-402 starts to leak. The RO should acknowledge the Quench Tank alarm and note on the acoustic monitor the indicated leakage. The ARM will be referenced and the CRS will direct the PORV Block Valve, RC-403 -MOV be closed. The CRS will refer to T. S. 3.4.11. The RO should monitor RCS pressure and Quench tank parameters to be returning to normal values. The OWC will be conducted for assistance.

After T.S. have been addressed, a condenser tube ruptures in 12B waterbox. This will first be noticed with a Turbine Plant Sample Alarm. Chemistry and the TBO should be dispatched. Once a tube rupture has been determined in 12B waterbox a rapid power reduction to a target value of 300MW should be started and water dropped in the box. Additionally the waterbox should be isolated using OI-14. Chemistry and other appropriate plant management notifications should be made.

After power has been reduced at least 5%, CEA 35 drops into the core. The crew should reduce turbine load to maintain Tc on program then about a minute later a 2nd CEA drops. The CRS should direct the unit be tripped and EOP-0 implemented. When the RO attempts to trip the reactor an ATWS condition exists and the RO must take ATWS actions to trip the reactor and meet the reactivity control safety function.

During the performance of EOP-0 a SGTR begins in 12 SG. The crew is expected to diagnose the SGTR and implement EOP-6. While in EOP-6 the crew will cooldown to less than 515'F Th and attempt to isolate 12 SG.

When the CRO tries to close 12 MSIV it will not close from the Control Room and the ABO will be dispatched to close it locally. The scenario can be terminated after 12 SG is isolated.

0202.doc 3

Cliffs Calvert Cliffs Scenario No.: 3 Op Test No.: 1 Facility Simulation Facility Simulation Calvert Scenario No.: 3 Op Test No.: 1 Examiners: Operators: SRO

_ _BOP To evaluate the applicants' ability to conduct a unit power reduction, to implement the ARMs, Ols, AOPs, as Objectives: appropriate, for malfunctioning systems and/or controls including a failure of PRZR level control channel (ilOX) which causes a broken shaft on 12 Charging Pp, a failed FRV Controller (1121) and a SGFP oil leak causing a rapid power reduction. A loss of 11 BA Pp occurs at the start of the downpower. The crew will be forced to trip the unit when the running SGFP trips. Two stuck CEAs require boration to meet reactivity but a loss of 11 4KV Bus will force the crew to EOP-8 for reactivity not being met. In EOP-8, boration will be restored but 11 AFW Pp will trip resulting in a loss of feed. The crew can address the loss of feed in EOP-8 or transition to EOP-3.

Initial Conditions: The plant is at 67% Power, MOC (IC-17) 11 Chg Pp is OOS 12 AFW Pp is OOS 12 SGFP Pp is OOS.

11 CCW Head Tank Makeup CV is isolated due to leakby.

INSTR AIR COMPR(S) alarm (K-25) hanging.

Turnover: Present plant conditions: 67% power, MOC; Unit 2 is in MODE 5 - no CW Pps and 23 AFW Pp unavailable.

Power history: 67% power for previous 4 days.

Equipment out of service:

1) 11 Chg Pp packing replacement. Expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. All Chg. Pumps have been repacked, currently running in the packing on 13.
2) 12 AFW Pp exhibited excessive vibration during STP. It is disassembled, expected to be returned to service in 2 days.
3) 12 SGFP Pp to repair steam leak on LP poppets. It is disassembled, expected to be returned to service tomorrow
4) 11 CCW Head Tank Makeup CV is isolated due to leakby.
5) Alarm K-25 INSTR AIR COMPR(S) is hanging. No problems with the compressors, I & C is investigating, alarm card has been swapped out.

Surveillances due: 1B DG STP-0-8 due today. SM will bring STP to CR when ready.

Instructions for shift:

1) Maintain current power level. Perform 1B DG STP-0-8 when directed by SM.

1 0203 .doc 0203.doc 1

Event Malf. Event Event No. j No. Description I Preload FW004_02 12 SGFP xOS.

CEDSO1O_28 2 stuck CEAs.

CEDS010_42 Remote Func 11 CHG Pp OOS. (bkr rackout)

AFW001_02 12 AFW Pp OOS PNL OVR INSTR AIR COMPR(S) alarm hanging.

(K-25)

RCS026_01 I RO About 3 minutes after the crew has taken the watch, PRZR level contr. (1 l0X)

(low) fails low. The RO should acknowledge the alarm, inform the CRS and refer to the ARM. Level control should be shifted to channel Y and the OWC notified.

T.S. 3.3.10 should be entered.

2 CVCS003_02 C RO 12 Chg. Pp shaft breaks on start following 1 OX failure, however, the pump stops again when channel Y is selected. It is unlikely the crew will notice the failure here, but probably later during the downpower or boration to meet reactivity control in EOP-0. When discovered the crew is expected to attempt to ensure boration via another means and to contact the OWC for assistance.

3 FWO18_02 I CRO Next, 12 SG FRV Controller (1121) fails. The CRO should acknowledge the (LO) alarm and inform the CRS. The CRS should direct the CRO to maintain SG level and implement AOP-3G. The CRS should direct the CRO to place the controller switch in the Main Fail position. The CRS should direct the OWC to contact the System Engineer for assistance.

4 PNL OVR C CRO The CRO acknowledges the SGFP Conditioner Level Low Alarm, informs the (Conditioner R RO CRS and dispatches the TBO. Following the TBO report, a rapid downpower level low C RO will be initiated to take 11 SGFP off. (The crew may notice the charging pump alarm) N CRO malfunction at this time.) The OWC should be contacted for assistance and FW004_01 notifications. As the power reduction to take 11 SGFP off is begun, 1 BA Pp CVCS014_01 trips off when started. The RO will either use 12 BA Pp or gravity feed from the BASTs. At =50% power, 11 SGFP trips. The CRS should order the unit tripped due to loss of feed. EOP-0 is implemented, the RO notes 2 stuck CEAs and commences boration.

5 4KVOO1_01 M ALL After the RO reports on Pressure and Inventory, a loss of 11 4KV Bus occurs.

The CRS orders a reassessment of safety functions. The RO should determine reactivity is no longer being met due to no charging and direct the TBO to align 13 Chg. Pp to 14 bus. With the TBO being unsuccessful the CRS will enter EOP-8 for failure to meet reactivity.

6 AFWOO1_01 M ALL After EOP-8 is entered and the selected Success Paths begun, 13 Chg. Pp is successfully aligned to 14 bus. With boration now in progress, 11 AFW Pp trips. The CRS directs all RCPs and blowdown be secured. The CRS can remain in EOP-8 or transition to EOP-3. The crew begins a rapid cooldown to 465°F for loss of feed. The scenario will terminate when Booster Pump Injection or OTCC is established.

  • (N)ornial, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 0203.doc 2

SCENARIO 3 OVERVIEW The candidates will take the shift at =67% power.

About 3 minutes after the crew has taken the watch, PRZR level contr. (1 10X) fails low. The RO should acknowledge the alarm, inform the CRS and refer to the ARM. Level control should be shifted to channel Y and the OWC notified. T.S. 3.3.10 should be entered.

12 Chg. Pp shaft breaks on start following 1loX failure, however, the pump stops again when channel Y is selected. It is unlikely the crew will notice the failure here, but probably later in the scenario during the downpower or boration to meet reactivity control in EOP-0. When discovered the crew is expected to attempt to ensure boration via another means and to contact the OWC for assistance.

Next, 12 SG FRV Controller (1121) fails. The CRO should acknowledge the alarm and inform the CRS. The CRS should direct the CRO to maintain SG level and implement AOP-3 G. The CRS should direct the CRO to place the controller switch in the Main Fail position. The CRO will control level via the PDI. The CRS should direct the OWC to contact the System Engineer for assistance.

The CRO acknowledges the SGFP Status Panel alarm and determines the alarm to be a SGFP Conditioner Level Low Alarm, informs the CRS and dispatches the TBO. Following the TBO report of a bad oil leak on 11 SGFP pump, a rapid downpower will be initiated to take 11 SGFP off. (The crew may notice the charging pump malfunction at this time.) The OWC should be contacted for assistance and notifications. As the power reduction to take 11 SGFP off is begun, 11 BA Pp trips off when started for the initial boration. The RO will either use 12 BA Pp or gravity feed from the BASTs to borate. At z50% power, 11 SGFP trips. The CRS should order the unit tripped due to loss of feed. EOP-0 is implemented, the RO notes 2 stuck CEAs and commences boration.

After the RO reports the status of RCS Pressure and Inventory, a loss of 11 4KV Bus occurs. The CRS should order a reassessment of safety functions. The RO should determine reactivity is no longer being met due to no charging flow and direct the TBO to align 13 Chg. Pp to 14 bus. The TBO's attempts to realign the 13 Charging Pump will initially be unsuccessful. The CRS will enter EOP-8 for failure to meet Reactivity Control.

After Eop-8 is entered and the selected Success Paths begun, 13 Chg. Pp is successfully aligned to 14 bus. After boration is in progress, 11 AFW Pp trips; The CRS directs all RCPs and blowdown be secured. The CRS can remain in EOP-8 or transition to EOP-3. The crew begins a rapid cooldown to 4650 F for loss of feed. The scenario will terminate when heat removal has been reestablished by either Booster Pump Injection or OTCC.

0203.doc 3

Simulation Facility Calvert Cliffs Scenario No.: 4 (Spare) Op Test No.: 1 Examiners: Operators: SRO RO BOP Objectives: To evaluate the applicants' ability to conduct a unit power increase, to implement the ARMs, OIs, AOPs, as appropriate, for malfunctioning systems and/or controls including raising power, a failure of the SRW Controller for the Main Generator H2 Cooler, a failure of the letdown backpressure regulator and a dropped CEA. When the CEA drops the crew will implement AOP-1B. As the dropped CEA is being recovered a loss of 14 4KV Bus occurs. The crew will shift charging suction back to the VCT, stabilize the unit and implement AOP-71. Next, a loss of offsite power occurs and the Main Turbine does not Trip. The crew should determine a manual reactor trip is required, trip the unit and implement EOP-0. The 1A DG does not start and the OC DG Tie Bus is faulted resulting in a Station Blackout. The crew will implement EOP-7. As actions for EOP-7 are being performed 11 AFW Pp will trip. The crew will be able to restore AFW using 12 AFW Pump allowing them to remain in the optimal procedure.

Initial Conditions: The plant is at 75% Power, MOC (IC-18) 13 CCW Pp is OOS 12 Charging Pp is OOS INSTR AIR COMPR(S) alarm (K-25) hanging.

Turnover: Present plant conditions: 75% power, MOC; Unit 2 is in MODE 5 - no CW Pps and 23 AFW Pp unavailable.

Power history: 100% power for previous 190 days. Then reduced to z68% 3 days ago for 12 SGFP repairs.

Equipment out of service:

1) 13 CCW Pp has a broken shaft, expected repair tomorrow-noon.
2) Alarm K-25 INSTR AIR COMPR(S) is hanging. No problems with the compressors, I & C is investigating, alarm card has been swapped out.
3) 12 Charging Pp is OOS due to severe packing leakage. The packing is being replaced. Expected to be ready for PMT in about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Surveillances due: None.

Instructions for shift:

1) Unit 1 had been at z68% power the previous 3 days to repair a steam leak on 12 SGFP. Both SGFPs are operating in parallel. Continue raising power to 100% per OP-3.
2) Perform PMT on 12 Charging Pump when returned to service.

0204.doc 1

Event Malf. Event Event No. No. Type* Description Preload DGOC004 OC DG tie bus faulted.

DG002_02 IA DG start failure.

CCW002_03 13 CCW Pp OOS TGO02 Turbine fails to trip.

Remote Func 12 Chg Pp OOS PNL OVR INSTR AIR COMPR(S) alarm hanging.

(K-25)

I N/A R RO After the crew takes the watch, the CRS should brief the crew on the power N CRO increase to 100% per OP-3. After the brief the RO and CRO should coordinate to raise power while maintaining plant parameters within acceptable limits and Tc on program.

2 TGO30_01 I CRO After power has been raised at least 5%, the SRW controller for the Main (closed) Generator H2 cooler fails the valve shut. When the high temperature alarm is received, the CRO should acknowledge the alarm, inform the CRS and refer to the ARM. The CRO should determine TIC-1608 has failed low causing the CV to go shut, take manual control and restore H2 temperature. The OWC should be contacted for assistance.

3 CVCS005 I RO Next, Letdown backpressure transmitter PT-201 fails low. The RO acknowledges the alarm, informs the CRS and refers to the ARM. The CRS should direct the RO to take manual control, restore letdown flow and maintain letdown pressure. The OWC should be contacted for support.

4 CEDS012_34 C RO After the PT-201 failure CEA 34 drops. The RO should acknowledge the alarms, inform the CRS and refer to the ARM. The CRS should implement AOP-1B and address T.S. 3.1.4. The primary will be stabilized and realignment time determined. After notifying maintenance and correcting the cause, realignment will be commenced.

5 4KVOO1_04 C CRO As the CEA is being withdrawn 14 4KV Bus is lost. The crew should stop CEA withdrawl, diagnose the bus loss, shift Charging Pump suction back to the VCT and stabilize the unit. The CRS should implement AOP-7I. The CRO will perform APO-7I actions as directed by the CRS. The OWC should be contacted for support.

6 SWYD002 M ALL About 5 minutes after the bus loss, a loss of offsite power occurs. IA DG does not start and 14 4KV bus is locked out. The OC Diesel will not energize the OC Tie Bus due to a fault. The Main Turbine will not trip automatically. The crew should recognize a reactor trip is required and trip the unit manually. The crew will implement EOP-0 and diagnose a station blackout exists.

7 AFWOO1_01 M ALL In EOP-7, 11 AFW Pp will trip but they can restore AFW using 12 AFW Pump.

IA DG will become available and the 11 4KV Bus energized. After the bus is energized the scenario can be terminated.

  • (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient 0204.doc 2

SCENARIO 4 OVERVIEW The candidates will take the shift at -75% power with instructions to raise power to 100% per OP-3.

After the crew takes the watch, the CRS should brief the crew on the power increase to 100% per OP-3. After the brief the RO and CRO should coordinate to raise power while maintaining plant parameters within acceptable limits and Tc on program.

After power has been raised at least 50/o, the SRW controller for the Main Generator H2 cooler fails the SRW valve closed. When the generator H2 high temperature alarm is received, the CRO should acknowledge the alarm, inform the CRS and refer to the ARM. The CRO should determine TIC-1608 has failed low causing the CV to go shut, take manual control and restore H2 temperature. The OWC should be contacted for assistance.

Next, Letdown backpressure transmitter PT-201 fails low. The RO acknowledges the alarm, informs the CRS and refers to the ARM. The CRS should direct the RO to take manual control, restore letdown flow and maintain letdown pressure. The OWC should be contacted for support.

After the PT-20 1 failure CEA 34 drops. The RO should acknowledge the alarms, inform the CRS and refer to the ARM. The CRS directs the CRO to reduce turbine load as necessary to maintain Tc on program, implement AOP-1B and address T.S. 3.1.4. The primary will be stabilized and realignment time determined. After notifying maintenance and correcting the cause, realignment will be commenced.

As the CEA is being withdrawn 14 4KV Bus is lost. The crew should stop CEA withdrawl, diagnose the bus loss, shift Charging Pump suction back to the VCT and stabilize the unit. The CRS should implement AOP-71. The CRO will perform AOP-71 actions as directed by the CRS. The OWC should be contacted for support.

About 5 minutes after the bus loss, a loss of offsite power occurs. 1A DG does not start and 14 4KV Bus is locked out. The OC Diesel will not energize the OC Tie Bus due to a fault. The Main Turbine will not trip automatically.

The crew should recognize a reactor trip is required and trip the unit manually. The crew will implement EOP-0 and diagnose a station blackout exists.

In EOP-7 11 AFW Pp will trip but they can restore AFW using 12 AFW Pump. 1A DG will become available and the 11 4KV Bus energized. After the bus is energized the scenario can be terminated.

0204.doc 3

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