ML20094P659

Instructor Lesson Plan:Simulator Training for Senior Reactor Operators Operating Practices Training,Accident Analysis/Assessment Training

ML20094P659
Person / Time
Site:	Summer
Issue date:	05/18/1984
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20094P636	List: ML20094P633 ML20094P659 ML20094P669
References
NUDOCS 8408170313
Download: ML20094P659 (36)

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SOUTH CAROLINA ELECTRIC & GAS COMPANY  :

NUCLEAR OPERATIONS EDUCATION AND TRAINING INSTRUCTOR LESSON PLAN SIMULATOR TRAINING .FOR SRO's-OPERATING PRACTICES TRAINING ACCIDENT ANALYSIS / ASSESSMENT TRAINING Time: 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />

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Nuclear Operations Training

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PLANT CASUALTY TRAINING Day 1 Power Operations, Malfunctions Small RCS. Leak, Rod Control System Malfunction, Turbine Trip, Stuck Rod Overview In the Nuclear power industry there have been several utilities that have experienced small amounts of leakage from the Reactor

j. Coolant System (RCS). To prepare the operator-to properly identify and isolate such a leak, the student-will be exposed to a small RCS leak and will be required to identify and take proper corrective actions by following the Emergency Operating Procedures

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' Terminal Objective i

() The student will be able to disucss and describe indications of RCS leakage along with operator actions required to place the i plant in a safe and stable condition.

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c Enabline Objectives 1

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Upon completion of.this unit, the student shall be able to:  !

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discuss the Reactor Coolant System Abnormal Operating Procedure for reactor coolant leakage.

2) - describe indications of a small RCS leak.

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. recall RCS leakage technical specifications limits and their bases.

References

1. Virgil C. Su==er Training Simulator

2. SCE&G Phase II Training Material -

3. SCE&G Phase III Training Material

4. Westinghouse Phase III Training Material

5. Technical Specifications

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Abnormal Operating Procedures STP 114.002 N

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4 "3 ION LESSON PLAN

.. OUTLINE KEY AIDS INTRODUCTION A. UNIT TERMINAL OBJECTIVE:

The student will be able to recognize, diagnose,and respond. correctly to various plant malfunctions. This ability will be evaluated by instructor observation and the student's oral response to questions.

B. OPERATIONS PLAN:

Maintain Full Power Operation. .

Con 6:ct the scheduled' malfunctions.

C. MALFUNCTIONS SCHEDULED:

1. CVC-13-Letdown leak outside containment

-( ) 2. CRF-8-T.Ref failure in. Rod Control

3. CRF Stuck-Rod

4. EPS-9-Loss of unit Auxiliary Transformer

5. PRS Pressurizer Pressure Channel Failure (Protection)

. STATE THE NEED TO ASK QUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT REVIEW (Optional)

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-v. REVISI0tl LESS0tl PLAN OUTLINE. KEY AIDS II

I. PROCEDURE

A. Initialize at 1007. power and perform a shift turnover and explain plant conditions and obj ectives to students :

System lineupi 1 Plant-parameters Operational' status Power history B. STPs scheduled-

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- NONE C. Initiate CVC-13, Letdown Leak outside Malf CVC-13 containment, discuss: 3*U b

• y, p E0P-12 Actions Time =300sec T.S. Leak Rate-LCO b

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fcas Limitations of continued-operation with on). Inlet .

f TCV-charging and letdown isolated Clear malfunction after a rmasonable he time for repair -

D. Initiate PRS-5, Pressurizer Malf PRS-5 Pressure Channel Failure (Protection), Discuss:

• ]6 Failed Value Functions provided by channel =170 SI g

Tech Spec Requirements =0 (Caused by SOP-401 required actions Bad e pp Card Clear malfunction after a teasonable time for repair O

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LESS01PLM RE'/IS101 OUTLINE KEY AIDS E. ~ Initiate CRF-7, Stuck Rod HALF CRF - 7 I

' NOTE: Stuck Rod is in Shutdown Bank select variation B and.will not be noticed until

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-2=untrippable l Reactor Trip occurrs. ect ROD F.- Initiate CRF-8, TREF. failure in Rod Control B)

Discuss: MALF CRF - 8 E0P-10 Required Action select Failed

' - ' Rod Control System Control Valve = 557 F

- Signals and Response select Ramp Time Response of Plant-if no action was taken. -0 IE: Pressurizer Level and Pressure, SG o

1 Level, Steam Pressure, Turbine Load Clear malfunctions.after a reasonable time for repair G. If not Cleared. Clear Malf CVC-13 and have Charging and -

Letdown restored

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a. Initiaee EPS-9. toss of Unit AuxilierF Transformer, Discuss:

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Reactor Trip investigation,'cause of j trip E0P-5 Required Actions E0P-6 Required Actions ,

Tech Spec Requirements l -

ONO Preparation and Reporting

} Requirements I' I. Terminate exercise after plant is stable ,

SDM is verified, and all required Reporting and paperwork is completed.

J. Discuss with students plan of attack for l dealing with Transformer Failure and-Stuck j Rod.

K. Students conduct shift turnover to instructor t

~ IV. CRITIQUE

! A. Review overall operations conduct.

f B. Review malfunction responses j .

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[))' FRASE III PROGRAM PLANT CASUALTY TRAINING Day 2 Power Operations, Malfunctions Inadvertant Safety Inj ection Actuation, Loss of Site Power and Recovery, Establish Natural Circulation Overview Although it is unlikely for a major accident to occur in a nuclear plant,-the possibility does exits. Therefore, operators have to be knowledgeable of accident conditions, responses and procedures in order to place the plant in as safe and stable a condition as possible without causing further damage or public hazard. -

A loss of site power requires the control room operator to verify a safe shutdown condition and actuation of all required emergency components. In addition the operator will have to establish conditions which enhance natural circulation and monitor core

( }) conditions to ensure that core heat removal is adequate.

Terminal Objective Upon completion of this unit the student will be able to describe the symptoms and automatic actions during a loss of si,te power (blackout) . The student will also be able to perform and justify the immediate operator action required of a control room operator for a loss of site power and other plant malfunctions.

In addition, the operator will be able-to recognize an Inadvertant Safety Injection Actuation and take the proper actions to terminate it.

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Enabling Objectives-

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Upon completion of this unit the student will able to:

1)- List the symptoms or indications associated with a

= loss of site power (blackout).

.2)- describe plant response to a station blackout (loss of site power) including all automatic actions that will occur.

3)- list the immediate operator actions required following a loss of site power (blackout).

4)- demonstrate an ability to perform the immediate actions during control room operations.

5)- perform the subsequent operator actions while using the applicable procedures for a loss of site power (blackout) .

6)- discuss conditions which enhance natural circulation.

7) - Recognize an Inadvertant Safety Injection Actuation 8)- Perform the proper actions to terminate an Inadvertant Safety Injection.

O References

1. Virgil C. Summer Training Simulator EOP-4, SOP-306, STP 102.003

2. SCE & G Phase II Training Material *

3. SCE & G Phase III Training Material

! 4. Westinghouse Phase III Training Material

5. Technical Specifications l

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kJ REVISION LESSON PLAN OUTLINE KEY AIDS-INTRODUCTION l

- A. UNIT TERMINAL OBJECTIVE:

l The student will be able to describe the symptoms and automatic actions during a loss of site power. The student will also L be able to perform and justify the immediate

! action required of a control room operator

( for a lots of site power and other plant malfunctions. Successful completion of this t

unit will be based on satisfactory evaluation by the program insoructor based on obser- .

vation and the student's oral responses to questions.

B. OPERATIONS PLAN:

Initiate at 100 percent power equilibrium h_)s conditions and complete a shift turnover.

Initiate minor malfunctions as scheduled.

Have the load dispatcher inform the control l room of a severe weather watch involving the possibilities of tornados. Initiate a station blackout. Respond to the blackout including observation and discussion of .

natural circulation flow in the RCS. Continue with subsequent plant recovery as time permits ,

l C. MALFUNCTIONS SCHEDULED:

1. NIS-3 Power range channel failure

2. PCS-15 Inadvertent Safety Injection

3. CRF-9 DRPI loss of voltage

4. PCS-15 DG Load Sequencer fails to complete

5. EPS-1 Station Blackout l

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LESSON PLAN OUTLINE lKEYAIDS NOTE: In addition to the'above listed malfunctions, any of the malfunctions scheduled on previous sessions may also be used.

STATE THE NEED TO ASK QUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT II. REVIEW (Optional)

II

I. PROCEDURE

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A. Set up the plant in (LATER) and conduct a Override shift turnover emphasizing the current X604C2 R6 conditions - steady state 100 percent SSPS A Train

,, power; STP 345.037 SSPS Train A TRBL

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l  ; Actuation Logic Test in progress Annunciator Power history To ON Systems status Test / evolutions in progress l -

Equipment inoperability ,

, B. STPs scheduled NONE C. Initiate a power range channel failure MALF NIS - 3 (NIS-3), such that the channel fails to a Select Channe:

minimum output.

-N42 Have the students explain how the channel signal is utilized in Rod [ailedValue=

Control, SGWLC and Rx Protection. Ramp Time = 0 Review tech specs limitations for PR channel failures Discuss differences in indication between failure.

Trip the associated bistables and initiate repairs.

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LESS0rl PLAN OUTLINE KEY AIDS D. Initiate a RPI loss of voltage (CRF-9), IALF CRF - 9

due to failed power supply to Group B. Select Coil Review RPI system to include non-urgentGr up B failure alarm, Data B failure,.and General Warning lights.

Discuss RPI system accuracy after a failure Review tech specs limitations for continued operation f -

When (If) requested to switch power supplies, clear the malfunction.

Otherwise continue plant operations with the failure as allowed by tech specs.

E. Initiate PCS-5, Inadvertent SI Actuation, Discuss:

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Reason for Actuation (IC Tech had 1

STP that was missing a page)

Termination Criteria Reporting Requirements EOP-1 Directions for Recovery F. Allow students to stabilize plant, calculate SDM, and complete Administrative Requirements.

G. Initiate PCS-15, DG Load Sequencer Fails to complete (will not be noticed until blackout)

H. Initiate a Station Blackout (EPS-1) , due MALF EPS - 1

to inclement weather. Select -

Discuss blackout recovery actions Without Delay Review vital loads which should start cnt a blackout.

I. Continue subsequent recovery actions from Clear Malf the blackouts as time permits. EPS - 1 Review tech specs for electrical power system.

Restore Plant Power if time permits x-

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SOUTH CAROLINA ELECTRIC & GAS PHASE III PROGRAM

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PLANT CASUALTY TRAINIMG Day 3 Power Operations, Malfunctions Steam Generator (S/G) Tube Leak which escalates to Tube Rupture, Pressurizer Steam Space Leak.

Overview Identification of nuclear plant faults, as evidenced in the past few units, requires the use of several interrelated indications. This unit is a continuation of the same type of faults. One indication or annunciator will be a symptom of the problem, but the identification of the specific problem requires operator awareness and knowledge of system in-terrelations. A steam generator (S/G) tube leak is one fault which will be identified by the association of several different indications.

Terminal Objectives

/~ The student will be able to discuss indications of steam

\ -} generator tube leakage or tube rupture along with operator actions required to place the plant in a stable condition.

l In addition he will be able to identify this type of fault as a control room operator and use the proper procedure as guidance in further plant operations.

The student will also be able to describe the symptoms and automatic actions during a pressurizer steam space leak.

Enabling Objectives Upon completion of this unit the student shall be able to:

1)- describe indications of a steam generator tube leak.

2)- identify the particular steam generator involved.

3)- describe aparator actions in response to a steam generator tube rupture.

4)- demonstrate an ability to perform actions as a control room operator during a steam generator tube rupture.

5)- Demonstrate an ability to perform actions as a Control Room Operator during a pressurizer steam space leak.

References i

1. Virgil C. Summer Training Simulator

<- 2. SCE & G Phase II Training Material (s) 3. SCE & G Phase III Training Material

4. Westinghouse Phase III Training Material

5. Technical Specifications

6. Abnormal Operating Procedures 1

7. STP - 204.001

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LESSON PLAN REVISION OUTLINE - KEY AIDS INTRODUCTION

'A. UNIT TERMINAL OBJECTIVE:

The student will be able to recognize, diagnose and respond ~ correctly to various l_ plant malfunctions. This aiblity will be i

evaluated by instructor observation and the student's' oral response to questions.

B. OPERATIONS PLAN:

Maintain 100 percent power. Conduct the -

scheduled malfunctions.

C. MALFUNCTIONS SCHEDULED:

1. TUR First stage pressure

<~ transmitt'er failure

2. PRS Pressurizer Steam Space Leak

3. RCS Steam generator tube leak NOTE: In addition to the above listed malfunctions, any of the malfunctions scheduled on previous simulator sessions may also be used.

STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT L II

I. PROCEDURE

A. Initialize at 1007. power and perform a shift turnover. Explain plant conditions and

! objectives to students :

System lineups Plant parameters Operational status Power history l

B. STPs scheduled

,- NONE

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- s REtilSION LESSON PLAN OUTLIME I KEY AIDS I

C. Initiate TUR-12, first stage pressure MALF TUR-12 transmitter failure, discuss: (Select-Effect on all associated systems, i.e., Channel not P-13, P-7, C-5 , C-7, auto rod control being used)

Clear malfuncti.on after proper for Rod bistables have tripped and request Control Faile i for repair has been made Value = 0 Ramp Time = 0 D. Initiate PRS-8, Pressuri:cr Steam Space Leak, Discuss: 3%LF PRS - 8 Accident Symptoms Fa ed Value E0P-12 Required Actions Ramp Time' =

E0P-1 Required Actions 300 seconds E0P-01, Emergency Plan Requirements

,s Allow transient to continue until stable,

- (_) subcooled condition is established and cooldown has started using natural circualtion or forced circulation (if available).

E. Re-initialize at 1007. power explain plant conditions System lineups Plant parameters Operational status Power history

, F. Initiate RCS-2 steam generator tube leak, MLF RCS - 2 discuss: [ Leak Flow =

First indications versus determining 400 GPM indications, i.e., radiation alarms in Ramp Time =

conjunction with flow changes, and 3600 Sec.

apparent difficulties Leak-rate determination gelect SG = B S

or C l Proper procedure (EOP-12) l Initiation of SI and subsequent E0P-1 l Actions 1 Emergency Plan EPP-01 Actions

(} Continue Malfunction to end of class sesf on i

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LESSON PLAN OUTLINE KEY AIDS CRITIQUE A. Review overall operations conduct.

B. Review malfunction responses Enabling Objectives Upon completion of this unit the student will be able to:

1) - discuss the symptoms of a pressurizer steam space leak. .

2)- describe operator actions for a S/G Tube Leak 3)- describe what is meant by Condition III faults.

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4)- list the types of faults considered to be Condition III faults.

5)- Perform the subsequent operator actions while using the applicable procedures (s) for S/G Tube Leak.

References

1. Virgil C. Summer Training Simulator E0P-1 ,

E0P-2, E0P-5, E0P-12, SOP-404, SOP-403, STP 108.001

2. SCE & G Phase II Training Material

3. SCE & G Phase III Training Material

4. Westinghouse Phase III Training Material

5. Technical Specifications

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. 1 SOUTH CAROLINA ELECTRIC & GAS

() PHASE III PROGRAM MAJOR PLANT CASUALTY TRAINING Day 4 Loss of Secondary Coolant Inside the reactor building, Accident Analysis Review - Part 3 Overview In previous units, faults of increasing severity have been discussed. The remaining accident events to be considered are those included in Condition IV Events - Limiting Faults.

These are the most drastic events. Although not expected to occur, these accidents are postulated because their consequences include the potential for radioactive material release. It is the Condition IV accident wh'ch i the plant is designed to protect'.

The plant's protection and safeguards systems will automatically provide initial safe shutdown; however, the operator is relied upon to correctly diagnose the accident and perform the required

(] actions specified in the emergency procedures.

The unit is designed to review the accidents in the Condition IV category and allow students to experience selected faults as control room operators. .

Terminal Obj ectives, Upon completion of this unit, the student will be able to describe the symptoms and automatic actions during a loss of secondary coolant (inside the reactor building) and other Condition IV events. '

The student will also be able to perform and justify the immediate operator actions required of a control room operator for a loss of secondary coolant accident and other plant malfunctions.

Successful completion of this unit will be based on a satisfactory evaluation by the program instructor based on observation and the student's oral response to questions, p

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. ' Enabling Objectives l .(9)..

Upon completion of this unit, theistudentishall be able-to:

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'l) . describe.what is meant by Condition IV events.

2)- list faults included in,the Condition IV. category.

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'3)- describe -indications~of a feedline' break inside the reactor building.

! 4)- discuss . assumptions ' used in. the feedwater break l ~ analysis.

5)- describe operator actions for a loss ^of secondary coolant.

6)- describe plant response to a steam.line rupture.

I~ 7)- describe the major indication differences between steam and feed breaks inside the. reactor building.

L 8)- ' perform the subsequent operator actions while using the applicable procedures .for a loss of secondary coolant. ' ,

References

() 1.

2.

Virgil C. Summer Training Simulator SCE&G Phase III Training Material

3. SCE&G Phase III Training Material 4 Westinghouse Phase III Training Material

5. Technical Specifications -

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'- REVISI0il LESS0ilPLAil OUTLlilE KEY AIDS I. INTRODUCTION A. UNIT TdRMINAL OBJECTIVE:

The student will be able to describe the symptoms and automatic actions '

during a loss of secondary coolant (in-side the reactor building). The student will be able to perform and justify the immediate operator actions required of a control room operator for a loss of secondary coolant accident and other plant malfunctions. Successful completion of this unit will be based on a satisfactory evaluation by the

() progr'am instructor based on obser-vation and the student's oral response to questions.

B. OPERATIONS PLAN:

Initiate at 50 percent power and complete a shift turnover. Initiate minor malfunctions as scheduled. Major accidents will include a steam break and a feed break inside the reactor building, with each event involving safety injection system actuation.

Discuss emergency plans with students for each major accident.

C. MALFUNCTIONS SCHEDULED:

1. CCW-1 Letdown Heat Exchanger Tube Leak

2. MSS-3 Steam break inside containmort

3. FWM-8 Feedwater Line Break inside

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~' R0ilSION LES300 PLAN OUTLINE KEY AIDS p

4. RC3-8 RTD failure (T - control)

5. FWM-3 Emergency feedN pump trip NOTE: In addition to the above listed ,

malfunctions, any of the malfunctions scheduled on previous simulator

' sessions may also be used.

STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT l III. PROCEDURE A. Set up plant in (Later)(50 percent power) .

B. Conduct a shift turnover emphasizing the current conditions 50 percent power; no testing in progress.

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Test / Evolutions in Progress l

Equipment Inoperability i

The instructor may initiate with ,

equipment inoperable as long as applicable survoillanco requirements

, are being met for continued plant operations.

C. Initiato plant loading toward 100 percent

. . power D. Initiato A LD Heat Exchanger Tube Leak 4ALF CCW-1 (CCU-1) , Discuss Select Leak E0P-9 Required Actions hau=20 g am E0P-12 Required Actions Time = 300 Sec Determination of Leak Location Determination of Leak Rato (v) 6i

LESS0tlPLAfl OUTLIllE KEY AIDS When leak is isolated, continue operation wit.h charging and letdo'.m isolated E. Continue plant loading; iniitiate a s l4ALF MSS-3 steamline break inside the reaccog Select Leak buildin (MSS-3) Recommend 6 x 10 lb/Hr aco=6x100LB/HR over a O minute ramp, elect Ramp Observe operator actions; diagnostics rimo = 600 see When students are in subsequent actions of E0P-2 freeze the conditions .

and critique the evolution.

F. Reinitiali::o at 50 percent power or a backup SNAP >50 percent power if desired

/7 to maintain previous plant conditions.

V NOTE: Remove the steamline break if inserted

! with time delay.

C. Continue plant loading; initiate a RTD failure such that loop 3 TH RTD fails low (RCS-8). '

Discuss indications of failura l (Tavg, AT analysis)

Discuss affects en Rod Control, par

, Level Control, RIL circuitry (AT)

Review Tech Specs operability requirements Trip selected histables and initiato repairs. i H. Initiate an Emergency Food Pump Failure

! (FWM-3) due to a feed breaker failure.

(Motor Pump Failure) i I

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This failure should be noticed I during subsequent SI and corrective action taken to attemot to start the.

pump locally.

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.I. Continue lant loading; initiate a 4ALF.FDI-8 feedline reak inside the reactor $ elect any S/G building (FWM-8); break is downstrearSelect Leak of check valve inside the reactor - Kate=6x106 LB/HR building. Leak rate of 6. x 10 lb/hr Select Ramo and a ramp of 10 minutes .are recomm- time =600 sec ended.

Observe operator actions: dia- -

gnostics When students are in subsequent actions of EOP-2, discuss overall operations eg -

Review Emergency Feed Pump

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• operability requirements (Tech Specs) .

J. Continue subsequent actions as time permits.

K.

Students instructor.

conduct shift turnover to j

Note to Instructor: The-simulator session should be conducted with as-many questions as possible being.

asked of the operators regarding plant systems, procedures, Tech Specs, 3 etc. The sessions _should be representative.of the fuel audit operational exam.

IV. . CRITIQUE'

' x. A. Review overall operations conduct.

B. Review malfunction responses I

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SOUTH CAROLINA ELECTRIC & GAS I l

m- PHASE III PROGRAM i'~') MAJOR PLANT CASUALTY TRAINING Day 5 Loss of Coolant Accident - Inadequate Core Cooling Overview The final major nuclear plant fault that must be discussed in detail and actually performed is a loss of primary coolant accident (LOCA). Although this particular accident and small Reactor Coolant System (RCS) leaks have been previously observed, the required actions for a loss of coolant accident have not been performed. During this unit, the Emergency Core Cooling .

Systems (ECCS) and operator actions during a loss of coolant

-accident will be discussed.

Terminal-Objective i

O Upon completion of this unit, the student will be able to describe the symptoms and automatic actions during a loss of coolant accident (LOCA) including systems used and mechanisms of heat removal. The students will also be able to perform ~

and justify the immediate operator actions required of a control room operator for a LOCA and other plane malfunctions.

Successful completion of this unit will be based on a satisfactory evaluation by the program instructor based on observations and the student's oral response to questions.

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' (_I Upon-completion of this unit, the student will be able.to:

1)- list indications of a loss of reactor coolant accident.

2) distinguish between primary and secondary-loss of coolant accidents.

3)- describe operator immediate actions for a LOCA.

4)- demonstrate an ability to perform 'immediate and subsequent.

actions as.a control room operator during a LOCA.

5)- describe ECCS flow paths , flow rates , and injection pressures for each ECC system.

6)- describe the basic steps required'to shift ECCS from injection mode to recirculation mode.

7)- discuss conditions that enhance natural circulation.

8)- discuss the problems associated with inadequate core cooling and how to combat those problems.

References

) 1. Virgil C. Summer Training Simulator EOP-1, SOP-ll5

2. SCE& G Phase II Training Material

3. SCE& G Phase III Training Material

4. Westinghouse Phase III Training Material

5. Technical Specifications O

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REVISION LESSON PLAN OUILINE lKEYAIDS i

I. INTRODUCTION '

A. UNIT TERMINAL OBJECTIVE:

.The student will be able to describe the symptoms and automatic actions during a .

loss of coolant accident (LOCA). The students will also be able to perform and justify the immediate operator actions required of a control room operator for a LOCA and other plant malfunctions.

• Successful completion of this unit will be based on a satifactory evaluation by the program instructor based on observation

() and the student's oral response to questions.

B. OPERATIONS PLAN:

Initiate at 100 percent power and complete a shift-turnover. Initiate minor mal-functions as scheduled. The objective of this unit is to have the students identify and carry out the emergency procedure for a large LOCA including shiftover to recirculation mode of

, operation. Discuss emergency plans for each major accident.

C. MALFUNCTIONS SCHEDULED:

1. RCS Large LOCA (DBA)

2. PCS-15-DG Sequencer fails to complete

3. PCS Rx Trip breakers fail to open-at WS event

4. MSS Stm line break outside I containment (Optional)

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REVISIGH LESSON PLAN

'0UTLINE KEY AIDS

5. FWM-16-FW line break outside contain-ment.(Optional)

NOTE: In addition to the above listed malfunctions, any of the malfunctions scheduled on previous simulator sessions may also be used.

STATE THE NEED TO ASK QUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT o

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I. PROCEDURE

A. Set up the plant in (LATER) (.100 percent power, Equilibrium Xenon).

B. Conduct a-shift turnover emphasizing the

(~ current conditions - 100 percent load, equilibrium Xenon.

Power History Systems Status Tests / Evolutions in Progress Equipment Inoperability NOTE: The instructor may initiate with equipment inoperable as long as applicable surveillance requirements are being met for continued plant operations.

C. Initiate PCS-15, DG load sequencer MALF.PCS-15 fails to complete Select Train A Malfunction of sequencer and failure and failure or RHR Pump to auto-Start Sel et Failed will not be noticed until SI Step

• Step 2 actuation O

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A REVISION LESSON PLAN OUTLINE KEY AIDS D. Initiate a Large LOCA (DBA) in Loop 1  !!ALF RCS-5 (RCS-5). This evolutien.should take Select Leak 1.5 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Rate = D3A Carry out the immediate and subsequent actions to the point of waiting for shiftover-~to hot leg recirculation.

- -Simulate time lapse of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and shift to. hot leg' recirculation mode.

Discuss procedures, notes, and precautions as you handle this accident. -

Discuss loss of all emergency feed-water system and. alternate methods of_ feeding S/G's providing cooling

for the RCS.

() ,

Use system drawings /CRT's for emp-hasis during system realignment.

Discuss failure'of RHR Pumo to start and consequences if pump could not be manually started E. Reinitialize at 100 percent pouer; stabilize plant conditions-instructor can backup.

F. Initiate PCS-9, Rx Trip Breakers fail 1ALF PCS-9 to open ' Select both Irip Breakers G. Initiate TUR-1. inadvertent turbine Select-Fail to trip or other malfunctions, at the open Manual instructor's discretion, to initiate and Auto the ATUS event Discuss plant response to ATUS, Rod Rod Control, Steam Dump Terminate e'xercise when all Rods are inserted and stable hot stand-by conditions are reached.

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~ RE'/ISION LESS0 'LAN OUTLIHE KEY AIDS H. If time permits, reinitialize-at 100% MALF.FWM-16 power conditions and initiate FWM-16, Select Leak FW Line Break outside containment, Location =

discuss Optional Select' Leak Indicatio6s of Leak Location Rate = 6x100 LB/HR Required actions PER'EOP-2 Select Ramp Time = 300 secs I. If time permits, reinitialize at 10C 7.

power conditions and. initiate MSS-4. MALF FWM -4 Stm Break outside containment,. discuss : Select S/G -

Optional.

Indications of Break' Location-IRB Select Leak vs ORB Rate = 6x106 LB/HR CRITIQUE Select Ramp, A. Review overall operations con'.2uct. Time = 300 sec s-B. Review malfunctions response

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