ML20094P669
| ML20094P669 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/18/1984 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20094P636 | List: |
| References | |
| NUDOCS 8408170318 | |
| Download: ML20094P669 (240) | |
Text
{{#Wiki_filter:. = _. -.- - -.. . . . - .. SOUTH CAROLINA ELECTRIC & GAS COMPANY NUCLEAR' OPERATIONS EDUCATION AND-TRAINING.
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( t INSTRUCTOR LESSON PLAN SIMULATOR TRAINING FOR R0'S Time: 25 Days , 3 t i , .O i Recommend d '
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Nuclear Operations Training LO f
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PHASE III PRCGRAM PWR NORMAL PLANT CPERATICNS t UNIT B-5 Plant Heatup Overview - This unit will be aimed at commencing the plant heatu.p.
~ A,revi,ew of som,e technical specifications will also be conducted.
f 4 . () Terminal Objective Upon completion of this unit, the student will have demonstrated c ve effe ti communication and coordination between control room operatort. The student will also have acquired the knowledge required to place the plant in m and discuss the major steps in the overall evolution. Enabline Objectives . Upon completion of this unit, the student will be able to: } 1)- discuss the precautions and limitztions of a plant heatup , 2)- demonstrate effective communication between Control Room opel 3)- describe the major steps of a plant ,heatup. 4)- describe the primary system alignments in the refueling mode . t (s
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I l l Re ference s - I uf 1. Virgil C. Summer Training Simulator GOP-1, GOP-6, GOP-7, E0P-4, SOP-115, 50P-201, SOP-202, 50P-305, STP-102.001, STP-103.001, STP-134.001
- 2. 1/irgil C. Summer Phase III Training Material 3.
South Carolina Electric & Gas Company Phase II Training Material 4 Technical Specifications
- 5. '
Precautions, Limitations, and Setpoints Docu ent
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2::-- I') INSTRUCTOR'S LESSON PLAN Page 1 LESSON OUTLINE NCTES AND REFERENCES I. INTRODUCTION
- A .- UNIT TERMINAL OBJECTIVE:
Upon' completion of this unit, the student wil,1 have demonstrated effective cc=- munications and coordination between Control Roem operators. The student will . also have acquired the k'nowledge required to start plant heatup to hot shutdown - and discuss the major steps in the overall evolution. B. OPERATIONS PLAN: * . Initiate heatup to hot shutdown. - C. MALFUNCTIONS SCHEDULED:
, RHR-2, RHR heat exchancer flow control valve failure RHR-1, RhR pump trip '
CVC-10, VCT level transmitter (LT-112) failure MSS-13 atmospheric steam du p valve failure EPS-5 loss of ESF bus
- EPS-5 diesel generator failure STATE THE NEED TO ASK OUESTIONS AS THEY .
ARISE STATE EASIC PRESENTAT*0N FORMAT
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e Page 2 INSTRUCTOR'S LESSCN PLAN LESSON OUTLINE NOTES AND RE.:SESNCSS II. REVIEW (Optional) - A. Summarize the procedure by having a student give a basic outline of the major
, steps.
B. Review the plant heatup procedure, GOP-1, stressing the following: . Purpose
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Precautions Initial conditions Instructions Final conditions C. Review the Technical Specification 3/4.4.8 - D. Discuss the upcoming simulator operations II
I. PROCEDURE
() A. Place the plant in the SNAP at cold shutdown and conduct the shift turnover. . Shift: Plant conditions: Mode 5 ' + i B. Scheduled STPs -
- 1. STP-102.001 source range analog channel operation test
' 2. STP-103.001 RCS and pressurizer heatup/cooldown ' i l
- 3. STP-134.001 shutdown margin calculation 4
C. Commence plant heatup and secondary plant . ; startup per GOP-1. s 0953L:4 -
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,G V. INSTRUCTCR'S LESSON PLAN Pace 2 LESSON OUTLINE NOTES ANO RE.:ERENCES
' i O. Mal functions Initiate the following calfuncticns during the heatup , o RHR-1, RHR pump trip o RHR-2, RHR heat exchanger flow Control valve failure o CVC-10, VCT level transmitter (LT-112) failure o MSS-13, atmospheric steam dump valve failure o EPS-5, loss of ESF bus . o EPS-6, diesel generator failure For each malfunction: I o Discuss effect on operation (s ) o Evaluate response _ o Clear the malfunctien after a reasonable period of time - E. Continue plant heatup IAW G0P-001 and a establish the pressurizer bubble
- Have student perform a source range STP-102.001 analog channel test during the heatup .
F. Take a SNAP at the end of the shift to use as temorrow's IC
- 1 G. t Students conduct a shift turnover to the l instructor. Check for knowledge of -
l cur. rent plant condition. l IV. ' CRITIQUE - 1 Hour A. Review overall operations. B. Review calfunction responses. 0963L:4 ' 1 Rev 0 1/01
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J 50' TH CAROLINA ELECTRIC & GAS CCMPANY . PHISE III PROGRAM NORMAL MINOR OPERATICNS WITH MINCR MALFUNCTIONS
- Plant Heatup - Cold Shutdown to Hot Shutdown Overview The startup of a nuclear power plant proceeds in an orderly manner from cold shutdown condition to the operational mode.
Many systems must be aligned. Safety items must be tested and other requirements must be met and completed *
, in a timely manner.
Many operations are completed outside the control room, and effective operators communications to control those evolutions. must be established between the con
,O ~g This unit will be devoted to continuing the plant heatup from the cold shut-down condition.
Terminal Objective Upon completion of this unit, the student will have acquired the kncwledge to perfcrm a plant heatup to hot shutdown and be able to sume.arize the steps , involved. 4 1 0954L:4
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Enablino Objectives f f
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Upon completion of this unit, the student will be able to: 1)- demonstrate effective communications between the control room and work stations outside the control room. 2)- describe the steps in the procedure for plant heatup to h0t shutdown condition. 3)- discuss the precautions behind the procedure used to conduct a plant heatup. References . 1. Virgil C. Summer Training Simulator GOP-1, SOP-101, SCP-211, SCP-404, and STP-103.001 .
- 2. Virgil C. Summer Phase III Training Material 3.
South Carolina Electric & Gas Company Phase II Training Material
- 4. Technical Specifications f
- 5. Precautions, Limitations, and Setpoints Document 1
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'"- Page 1 ,,~ INSTRUCTOR'S LESSON PLAN U LESSON OUTLINE NOTES AND REFERENCES I. INTRODUCTION A. UNIT-TERMINAL OBJECTIVE:
Upon complet' ion of this unit, the student
- will have acquired the knowledge'to per-form a plant heatup to hot shutdown and be able to summarize the steps involved.
B. OPERATIONS PLAN: Commence plant pressurization and heatup . toward hot shutdown, including drawing a pressurizer bubble. C. MALFUNCTIONS SCHEDULED: FWM-3, emergency feedwater pump trip NIS-6, noisy SR channel PRS-2, pressurizer level channel failure ( NOTE: In addition to the above listed malfunctions, any of the malfunctions scheduled on previous simulator sessions can also be used. ' STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE EASIC PRESENTATION FORMAT a REVIEW (Optional) [' A. Review procedure GOP-1 Procedure , Supporting system procedures B. Summarize the procedure by having a n.
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student give a basic outline of the major steps. C. Review procedure GOP-2 . Purpose () 0964L:4. - Rev 0 1/83
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< Page 2 INSTRUCTOR'S LESSON PLAN O- LESSON OUTLINE NOTES AND REFERENCES Precautions Initial conditions Instructions Final conditions D .' Summarize procedure by having a student
{ give a general outline of ' t*< procedure E. Discuss-upcoming operations III. PROCEDURE . A. Set up plant in SNAP taken at the end of the previous shift and conduct shift turnover . Shift Initial conditions: yesterday's final
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conditions
- 8. Scheduled STPs
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STP-103.001 RCS and Pressuri:er Heatup/Cooldown C. Continue the plant heatup IAW GOP-1 Use STP-103.001 RCS and and GDP-2 Pressurizer Heatup/ Cool-down during entire heatup D. Malfunctions Initiatt the follwoing during the . heatup NIS-6, noisy SR channel ( i o o PRS-2, pressuriter level channel failure o FWM-3, emergency feedwater pump trip ( - For each malfunction o Discuss the effect on plant operations -() '
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# Page 3 INSTRUCTOR'S LESSON PLAN . ?[U LESSON OUTLINE NOTES AND REFERENCES
, o Evaluate the response o Clear the malfunction after a reasonable period of time E. At the end of the shift, take a SNAP to use as tomorrow's IC F. ' Students conduct a shift ~ turnover to instructor. Check for knowledge of current plant condition. IV. CRITIQUE 1 hour A. Review overall operations. B. Review malfunction responses. t O . i ( .
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l l SCUTH CIROEINA ELECTRIC & GAS ("^ . w-i PHASE III PROGRAM NORMAL PLANT OPERATIONS WITH MINCR MALFUNCTICNS Plant Heatup and Startup Overview ' It is desirable to accomplish the system heatup in a timely manner; therefore the main steam plant is normally warmed up at the same time as the reactor coolant system. The objective of the plant heatup is to have the steam plant warmed and available for,startup when the reactor coolant system has been heated up. (]) This unit will involve itself with continuing the plant heatup and performin a reac, tor startup. The plant will be loaded towards 100 percent pcwer in the time remaining. Terminal Objective I Upon ccmpletion of this unit, the student will be able to discuss :he proce-dura for a plant heatup and startup and the importance of each s*ep in tne
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total -evolut1on. . The student will also be able to discuss all of the prere-
- - quisities plant such heatups. as administra.ive require?.ents, precautions ar.d limitations f p.
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. 1 Enablino Objectives r
Upon completion of this unit, the student will be able to: 1)- describe the steps listed in the plant heatup procedures. ( 2)- answer the assigned homework questions.
- 3) review secondary plant - Heatup and Startup procedure.
References
- 1. Virgil C. Summer Training Simulator GOP-2, GOP-3, GOP-4, SOP-208, 50P-210, 50P-404, STP 103.001, end STP 123.002
- 2. Virgil C. Summer Phase III Trating Material
- 3. South Carolina Electric & Gas Phase II Training Material
- 4. Technical Specifications -
- 5. Precautions, Limitations, and Setpoints Document r
O . L o - I I 2 096SL:4 Rev 0 1/83
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l l 1 f1 I l Y EO ~ I I 1 I INSTRUCTOR'S GUIDE 5 d f 1 i ' ~ 6 , k 0968L:4
' ::::: i ---r- INSTRUCTOR'S LESSON PLAN Page 1 TN LESSON OUTLINE .O NOTES AND REFERENCES INTRODUCTION A. UNIT TERMINAL OBJECTIVE:
Upon completion of this unit, the student will be able to discuss the procedure for a plant heatup and reactor startup and the ( -importance of each step in the total evolution. The student will also be able to discuss all of the prerequisite administrative requirements, precautions and limitations for plant heatups. B. OPERATIONS plan: Continue plant heatup and perform a reactor startup and plant loading.(Start
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with snap taken at the end of the previous s simulator session). C. MALFUNCTIONS SCHEDULED: , NIS-4, 112 channel gamma compensation failure FWM-21, MF bypass valve failure FWM-2, condensate pump trip FWM-5, feedwater pump speed control oscillates NIS-3, PR channel failure ( AI problems QPTR problems, QPTR calculations NOTE: In addition to the above listed malfunctions, any of the malfunctions k scheduled on previous simulator sessions can also be used. STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT s 0968L:4 Rev 0 1/83
a b Page 2 p[ . INSTRUCTOR'S LESSON PLAN is l' V-LESSON OUTLINE NOTES AND REFERENCES T. REVIEW (Optional)
.A. Review the homework B. Review procedure'GOP-3 Purpose Precautions
(- Initial conditions Instructions Final conditions C. Review procedure GOP-4 ' Purpose
' Precautions -
Initial conditions
' Instructions
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Final conditions 4 p D. Discuss Tech Specs 3/4.5 O E. 0tscuss upcoming operations III. PROCEDdRE A. Put plant in SNAP taken at the end of the previous session and conduct a shift turnover Shift: Initial conditions: SNAP Load dispatch: 100 percent bp the end ( of the shift B. Scheduled STPs
- 1. STP 103.001 RCS and pressurizer heatup/cooldown
, k 2. STP 123.002 service water system pump test C. Continue the heatup IAW-GOP-2 and GOP-3 Continue using STP 103.001-D. Perform a reactor startup IAW GOP-3 RCS and Pressurizer Heatup/ E. While in IR initiate NIS-4, IR channel cooldown
-V[ gamma compensation failure s
Discuss effect on reactor startup 1 0968L:4 Rev 0 1/83
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' INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES F. Increase reactor power to POAH and start secondary plant -
G. Initiate FWM-21, MF bypass valve failure, (. - af ter -transfer from emergency feedwater Discuss effect on plant operation - Evaluate response Clear malfunction H. Continue plant leading to 100 percent
- Have students a service water system STP 123.002 pump tes I. Initiate FWM-2, condensate pump trip when
( more than one pump Discuss effect on plant operation Evaluate response Clear malfunction J. Initiate al problems K. Initiate QPTR problems L. Initiate FWM-5, feedwater pump control oscillates ( M. Continue loading as time permits N. Students conduct a shift .urnover to instructor. Check for knowledge of current plant conditions.
,. CRITIQUE 1 Hour -
A. Review overall operations. .
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B. Review malfunctions responses. 1
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(.f PHASE III PROGRAM
- NORMAL OPERATIONS WITH MINOR MALFUNCTIONS Overview
,During the normal operation of a nuclear power plant, it is periodically required to shutdown and cooldown the unit for either maintenance or refueling considerations. Since this occurs only once or twice per year, it is a '
relatively infrequent evolution. Hence it-becomes difficult for control room operatore to experience the operations required for taking the plant to a cold shutdown condition and the use of the applicable procedures designed to bring () the plant to this condition. j This and the following unit are designed to provide a review of the-I systems which are utili:ed during a plant cooldown. In addition, it will enable the student to apply the proper procedures and actually perform the plant shutdown and cooldown as a control room operator. I Terminal Objective i The ' student will be able to describe the series of events encountered in bringing a nuclear plant from full power operation to cold shutdown and manipulate the plant through these events. The program instructor's observation and the student's oral response to e,uestioning will be used in determining satisfactory co=pletion of the course objective. 1, ! ,) .,s
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'Enabline Objectives-
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'Upon completion of this unit the student shall be able to:
1)- describe the serie's of events in power reduction and reactor shutdown. 2)- discuss the different methods of cooling down the Reactor Coolant System (RCS).
-3)- describe how the Steam Dump System is used during plant cooldown.
4)- describe when and how the Residual Heat Removal (RHR) System is placed into service. ( 5)- describe shutdown margin requirements during each mode.
- 6) perform a plant shutdown and cooldown following the appropriate plant p rocedures.
References . 1. South Carolina ' Electric & Gas Company Phase II Training Material
- 2. Virgil C. Summer Phase III Training Material
- 3. Technical Specifications 4.
Virgil C. Summer Training Simulator GOP-4, COP-5, GOP-6, GOP-7, E0P-10, 50P-102, 50P-210, STP-103.001, and STP-134.001. L - G kJ g 2 0959L:4 Rev 0 1/83
O' 1 l C . INSTRUCTOR'S GUIDE i 1 4 l l [ k O s 0959L:4 1 l
_m w INSTRUCTOR'S LESSON PLAN Page 1 x ( ,
) LESSON OUTLINE NOTES AND REFERENCES I. INTRODUCTION -
A. UNIT TERMINAL CEJECTIVE: The student will be able to adequately describe the sertes of events encountered in bringing a nuclear plant from at full power operation to cold shutdown as evaluated by the program instructor's - observation and student's oral response to questions. B. OPERATIONS plan: Perform plant shutdown from previous power accent to hot standby. Commence cocidown. Place.RHR is service and establish N2 bubble in the pressurizer. Perform control board misalignments if O desired. C. MALFUNCTICNS SCHECULED . CRF-5 uncontrolled rod cotton ' FWM-4 feedwater flow transmitter failure CVC-9 plugged beric acid filter MSS-1 Steam Generator pressure transmitter failure (control) II. REVIEW (Optional) A. Present overview of i simulator operations: Unloading from 100 percent Reactor shutdown Commence cooldown g-s) Place RHR in service
.,5
\- Establish N2 bubble 005cL:4 Rev 0 1/83
g INSTRUCTOR'S LESSON PLAN #9' 2
)- LESSON OUTLINE 1 NOTES AND REFERENCES Begin recovery operations' '
Establish PZR bubble
- 8. Review use of EHC and turbine auxiliaries EHC o Manual
( - o Standby Auxiliaries o Motor suction pump o Turning gear oil pump - o Bearing lift oil pump C. Review use of steam du=ps/ atmospheric - reliefs during cooldown T,yg mode Steam pressure mode, manual controllers Atmospheric reliefs o When used o Auto setpoint o Manual control - D. Review technical specification 3/4.2 E. Review RHR system 1 - RCS cooldown Flow paths o ' Cold leg injection * ( o o Cold leg recirculation Hot leg recirculation F. Brief review of shutdown procedures GOP-4 - GOP-5 GOP-6 GOP-7 i 1 0959L:4 Rev 0 1/83
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- III'. PROCEDURE *
'A. . Set up plant.in previous day's snap.
and conduct shift turnover Shift: Plant Conditions: 25 percent power, unloading to shutdown B. Scheduled STPs STP-103.001 RCS and pressurizer heatup/cooldown STP-134.001 shutdown margin calculation C. Commence lead reduction -
- D. Initiate CRF-6, uncontrolled rod motion Discuss effects on AI, HCFs Evaluate response Clear malfunction E. Continue load reduction F.
Initiate FWM-4 feecwater flow transmitter 1 - Discuss effects on SGWLC Evaluate respense Do not clear until MSS-1 G. Initiate CVC-9, plugged boric acid filter Discuss effects on shutdown Evaluate response H. Initiate MSS-1, Steam Generator pressure ' transmitter failure (control) If this is the same loop as FVM-4 and the loop SGWL is low, a reactor trip might occur when bistables tripped . f] - If students miss this and cause a reac- .- ter trip, let them conduct E0P-5 and ' then reinitiate at just before the trip 0953L;4 Rev 0 1/83 L
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INSTRUCTOR'S LESSCN PLAN LESSON OUTLINE - NOTES AND RE.:ERENCSS Evalua:e respense Clear MSS-1 and FWM I. Continue shutdown as time permits Have students calculate shutdown =argin STP-134.001 If cooldown is ccmmenced initiate RCS STP-103.001 and pressurizer heatup/cooldown STP's J. At end of shift take a SNAP and use it as tomorrow's IC IV. CRITICUE 1 Hour A. Review overall operations. B. Review malfunction responses. A G [ L U ? I 1 09591.:4 l Rev 0 1/83
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J:<; 1 c SOUTH CAROLINA ELECTRIC & GAS-COMPANY n Qy * . PHASE III PROGRAM. NORMAL OPERATION 5 WITH MINOR MALFUNCTIONS h Plant Shutdown and Cooldown to Cold Shutdown Overview - During'the-shutdown and cooldown several systems are used as heat sinks for
'the reactor coolant system. During the unloading the main steam system and the turbine are used. Once the reactor shuts down, the steam. dumps are usid ,
, to cooldown to ~350*F. The reactor coolant system is then depressurized to ~380.psig and the RHR System is placed in service. The RHR System is b then used to cool down to the Cold Shutdown condition (mode V, T,yg
<200'F) or to the Refueling Mode (mode VI, Tavg 140'F).
This unit will be directed towards continuing the shutdown and cooldown of the power plant, along with reviewing the procedures necessary to perform those. operations. Terminal Ob.iective Upon completion of this unit, the student will be able to perform a reactor shutdown and plant cooldown using appropriate procedures. The student will also be able te discuss the importance of major steps in the total operation. Students will also be able to describe the performance of a shutdown margin (SDM) determination. ( . s (.J ' . 1 0962L:4 i Rey 0 1/33 )
~Enabline Cbjectives f
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Upon completion of this unit, the student will be able to: 1)- discuss shutdown margin determination calculation. 2)- describe the steps applied'to the reactor shutdown and plant cooldown procedures. 3)- describe integrated plant relationships involved with plant shutdown
,and cooldown.
4)- discuss core reactivity effects during plant cooldown. ( 5) perform a plant shutdown and cooldown. References 1. Virgil C. Summer Training Simulator GOP-4, GOP-5, G09-6, GOP-7, , 50P-101, SOP-102, 50P-202, STP-103.001, and STP-112.002,
- 2. Vi gii C. Summer Phase III Training Material
- 3. Curve Book
[ 4. Technical Specifications O s. . Prem4cns, umetions. eee Setniets Oxu=eet-6. South Carolina Electric & Gas Company Phase II Training Materia.1
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o - s i 2 ne62L:4 Rev 0 1/83
C INSTRUCTOR'S GUIDE 6 l 1 i o , 0962L:4 Rev 0 1/83
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J INSTRUCTOR'S LESSON PLAN Page 1 (} ea LESSON OUTLINE NOTES AND REFERENCES l I. INTRCDUCTION A. UNIT TERMINAL OBJECTIVE: Upon completion of this unit, the student will be able to perform a reactor shutdown and plant cooldown using appropriate ( procedures. The student will also be able to discuss.the importance of major steps in.the total evolution. Students will . also be able to describe the performance of a shutdown margin determination. B. OPERATIONS PLAN: Continue the plant shutdown /cooldown. C. MALFUNCTIONS SCHEDULED:
- 1. PRS-3, pressurizer spray valve failure
( (open) n V 2. PCS-6, inadvertent containment isola-tion phase A (Train A)
- 3. MSS-5, steam dump control valve -
4 CVC-19, seal injection flow centrol valve (HCV-186) failure NOTE: In addition to the above listed mal-functions, any of the malfunctions scheduled on previous simulator sessions can also be ' ( . u s ed'. STATE THE.NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT
. REVIEW (Optional)
A. Emphasi:e al control during shutdown B. Review procedure GDP Appendices B and 0 I C. Have students perform a SOM from known s V initial conditions. *
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1 [ INSTRUCTOR'S LESSON PLAN Page 2 LESSON OUTLINE NOTES AND REFERENCES O. Review tech spec 3/4.4.7 ' E. Otscuss upcoming simulator operations til. PROCEDURE A. Put plant in SNAP taken at end of last shift and conduct shift turnover ( - Shift: Plant status: continue cocidown from yesterday B. Scheduled STPs:
- 1. STP-103,001 RCS and pressuri:er ,
heatup/cooldown .
- 2. STP-112.002 reactor building spray puro test C. Continue cooldown Use STP-103.001
- 0. If still on steam dumps, initiate MSS-5, curing entire steam dum control valve cocidown Discuss effects on cocidown Evaluate response i E. Initiate PCS-6, inadvertent CISA (Train A)
Discuss effects on cocidown Evaluate response ( F. While RCPs are still in service, initiate CVC-19, seal injection flow control valve (HCV-156) failure Discuss effects on RCP Evaluate response G. When the pressurizer spray valve (s) is(are) opened to depressurize the RCS,
/ initiate PRS-3, pressurizer spray valve -
failure (open) ' 0962L:4 Rev 0 1/83
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g INSTRUCTCR'S LESSON PLAN Page 3 LESSON OUTLINE _l NCTES ANO RE.:SRENCSS Discuss effe:t en cocidewn Evaluate response Clear malfunction . H. Depressurize to ~3S0 psig and put RHR in Service. I. Continue plant cocidown to cold shutdown using the RHR system, and discuss the folicwing:
- SIE~112*002 Calculation of xenen-free cold shutdewn boren concentratten using shutdcwn margin caiculaticn Pressure /te perature limita: tens for the RHR system Interlocks asse:iated with the RHR
( ') system C :ic:an limits for the RCS and pressert:er Cooldown verifying cooldown rates using RCS & pressurizer heatup/ccoldown Verifica icn and adjustment cf RHR b:ren concentration Alignment of the RHR system during ' cecid:wn Collapsing the pressuri:er steam butble Let; wn ficw:ath while in EHR ccoling alignment J. Students conduct shift turnover to instructor. .
- l Check for knowledge of current plant j
conditions. CRITIQUE l ' l ' A. Review overall operations, i
- B.
Review malfunctions responses. I 0962L: 4 l i
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1 s SOUTH CAROLINA ELECTRIC'&~ GAS COMPANY . ,a
. ,I PHASE III PROGRAM NORMAL OPERATIONS WITH MINOR MALFUNCTIONS Plant Startup - Hot Standby to Point of Adding Heat Overview The startup of the reactor is probably the most important single event in normal operations. This is a time when many large reactivity additions are made by the operator. Strict attention must be given to plant parameters at all times so that the operator can take decisive and prompt action in the event of any unexplained reactivity excursion. Precise control of the reactor must be maintained at all times.
A In this unit you will discuss the startup procedure, conducting a reactor startup, and proceding towards 2". power. The startup should be observed closely by those students not actually performing the evolution. During the course of this 25 day simulator training project each student will have the opportunity to perform at least 10 reactor startups. Terminal Objective Upon completion'of this unit the student will be able to discuss the basic procedure for a startup and the importance of each step in the total evolu-tion. The operator will also discuss all of the prerequisite administrative requirements, precautions, and limitations for reactor startups. The student will also gain familiarity with the control board and learn important equipment control locations at his particular work station. O 1 0955L:4 Rev 0 1/83
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~ Enabline Ob.iectives r~\- '
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Upon completion of this unit the student will be able to: 1)- describe the steps'of the reactor .startup. procedure in a chronological order. 2)- state the locations of various equipment controls and indications. [ 3)- discuss precautions and limitations of a reactor startup. 4)- describe control system interrelationships incorporated into the procedure. I(' 5)- demonsrate good watch standing practices.
~
- 6) perform a safe and controlled reactor startup.
References
, 1. Virgil C. Summer Training Simulator GOP-3, GOP-4
! 2. Virgil C. Summer Phase III Training Material
- 3. South Carolina Electric & Gas Company Phase II Training Material 4 Technical Specifications
- 5. Precautions, limitations, and Setpoints Document i
i i l (L . }- b I () . L 2 0955L:4 Rev 0 1/83
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LESSON OUTLINE NOTES AND REFERENCES I. INTRODUCTICN A. UNIT TERMINAL OBJECTIVE: Upon completion of this unit, the student " will be able to discuss the basic pro-cedure for.a startup and the importance of each step in the total evolution. The operator will also discuss all of the prerequisite administrative requirements,
~
i precautions and limitations for reactor startups. Students will also gain familiarity with the control board and " learn important equipment control loca-tions at his particular watchstation. B. OPERATIONS PLAN: q [) Perform a reactor startup to power in accordance with general normal operating procedures. Continue plant power increase as time permits. . 1 C. MALFUNCTIONS SCHEDULED: NONE STATE THE NEED TO ASK OUESTIONS AS THEY ARISE j STATE BASIC PRESENTATION FORMAT II. REVIEW (Optional) A. Review reactor theory h:mework
- B. Review procedure for shift'and relief turnover .
b Purpose Scope
~
Definitions ('~') Procedure 5 5 0955L:4 ' Rev 0 1/83
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I .,- INSTRUCTOR'S LESSON PLAN Page 2 V- LESSCN OUTLINE NOTES AND REFERENCES
~C. Review the major parts of the reactor
( - startup procedure ~, GOP-3,-stressing the following: ' Precautions and limitations . Initial conditions ( - Procedure Always attempt to orient the students to the basic procedure to help them attain a
" big picture" concept.
O. Summarize the reactor startup procedure by having a student give a basic ou,tline of . it: Check initial conditions and complete check lists Adjust Baron concentrations if necessary Announce reactor startup Block the high flux at shutdown alarm i Record source range counts Withd' raw control rods in manual to establish criticality Verify reactor suberitical at RIL Announce reactor criticality { - Proceed to 10 -8 amps at .75 DPM Block source range at P-6 Level power at 10 -8 amps. Record critical data.
. Increase power to 2 percent E. Review major parts of the plant operations ,
> 2 percent power, GDP-4, stressing:
Purpose Precautions . 0955L:4 Rev 0 1/83
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(~} y,n- INSTRUCTOR'S LESSON PLAN Page 3
. LESSON OUTLINE NOTES A.')D REFERENCES Initial conditions .
Instructions Final conditions F. Review operational control area guidelines Control areas in the control rcom
, Technical specifications manning requirements '
- ' Physical restrictions imposed upon the .
-operators G.
Review Technical Specifications para. 3.0.4 H. Discuss upcoming simulator operations , III. PROCEDURE A. Proceed to Control Room and discuss the following: ' Instructor / student relationship Communication between students and operators outside the control room
, Control room manning
- Shift turnover Control room terminology -
Simulator problems
- 8. Put plant in MOL, hot standby and conduct shift turnover
, Shift: 0000-0800 Initial conditions: Hot standby, 557'F, 2235 psig C.
Students should calculate an ECP and an SDM HOTE: Stress the importance of the ' reactor operator staying at his control station wita control rods in manual and off the bottom
,n '
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(~] V INSTRUCTOR'S LESSON PLAN Page 4 ! LESSON OUTLINE _ 1 NOTES AND REFERENCES
. Discuss technical specifications ^
requirements needed prior to . criticality (summari:ation) Para. 3.0.4 changing modes 2.2.1 limiting' safety system settings 3/4 1.3.1 group height . 3/4 1.3.2 position indicating system
- 3/4 1.3.4 red drop time.
,3/4 1.3.5 shutdown rod insertion limit 4
3/41.3.6 control red insertion limits '
,- 3/4 3.1.1 reactor trip system '
1 . instrumentation . Discuss log readings taken prior to pulling rods
], -
Discuss the following: o Operation of the rod control system in manual i
,o Suberitical multiplication *
- o Operation of source range nuclear instruments o Doubling 4
i o Minimum and maximum critical i postitions o Indications of criticality j 0. Scheduled STPs:
! None t
E. Increase power to 10~8 amp's and discuss: Source-intermediate range overlap Permissive P6 and blocking of the . source range high flux reactor trip Operation of intermediate range ' nuclear instruments J
.y-' te' 0955L:4 g Rev 0 1/n
) INSTRUCTOR'S LESSON PLAN Page 5 LESSON CUTLINE NOTES AND REFERENCES .
Data taken at 10~8 amp's and why it is taken , F. Increase power to 2 percent. Discuss: Indications at the point of adding heat ' Effects of moderator temperature and Doppler on SUR. Effect of increasing T avg on steam dump operation G. Final condition: 2 percent power H. Students conduct shift turnover to ' instructor. Check for knowledge of ' current plant condition IV. CRITIQUE A. Review o'verall operations and conduct. ' A V' L
\ I O
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p q SCUTH CAROLINA ELECTRIC & GAS CCMpANY v PHASE III PRCGRAM NORMAL OPERATIONS WITH MINOR MALFUNCTIONS Plant Startup - Hot Standby to Full Power Overview , Before performing a reactor startup, a calculation is required to help predict the point at which criticality will occur. This calculation is called an estimated critti.'al condition (ECC).- If we find that from this calculation ' (ECC) that the reactivity balance of the core has changed significantly, then a more structured approach toward criticality must be used. This is called an
- inverse count rate ratio plot (ICRR). These two cal'culations (ECC and ICRR) tell the operator that the reactor is responding properly (as predicted) during the startup and thus ensures the o;.erator that he is maintaining pre-cise control of the reactor. Both of these calculations require reference information which is obtained by the operators during the previous ~ critical operation.
This unit will review the procedures for taking reference critical data (RCO), calculating the ECC and performing an ICRR plot. A review of some items from technical specifications will also be conducted. Terminal Objective l Upon completion of this unit the student will be able to discuss the data collected and the performance o'f ECC, RCD AND ICRR plot calculations. Also, the student will recall thel function, composition and responsibilities of the Plant Safety Review Committee (PSRC) and Nuclear Safety Review Committee (NSRC).
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l Enablino Objectives f s f~}' k- Upon completion of this unit, the student will be able to: 1)- describe the steps taken that are necessary to perform an ECP, ICRR plot and RCD.
- 2)- discuss the importance of ECP, ICRR plot and RCD calculations.
~
3)- perform a safe and contro11ed reactor'startup. 4)- explain how a core reactivity balance is calculated. ( References
- 1. Virgil C. Summer Training Simulator GOP-4, GOP Appendix B, GOP Appendix C, GOP Appendix D, STP 125.002
- 2. Virgil C. Summer Phase III Training Material
- 3. Sou'.h Carolina Electric & Gas Company Phase II Training Material
- 4. Tecanical Specifications
- 5. Precautions, limitations, and Setpoints Document r
O .
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T, i O' C INSTRUCTOR'S GUIDE r O. ( ! O . 0954L:4 I Rev 0 1/83 l l
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'j INSTRUCTOR'S LESSON PLAN Ed98 1 LESSON OUTLINE NOTES AND RE.:ERENCES I. INTRODUCTION
- A. UNIT TERMINAL OBJECTIVE:
Upon completion of this unit, the student will be able to discuss the data collected and the performance of ECC, RCO, and ICRR plot calculations. Also, the student will ' recall the function, composition and - i responsibilities of the Plant Safety Review Committee (PSRC) and Nuclear Safety Review Committee (NSRC). B. OPERATIONS PLAN: Perform a reactor startup to P0AH. Per-form a 1/M plot during the startup. Con-tinue plant power to increase to full load. C. MALFUNCTIONS SCHECULED: NONE STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT II. REVIEW (Optional) A. Review reactor theory homework B. Complete the review of GOP-4 (if required) C. -Review Reference Critical Data procedure GOP4 Appendix B Purpose Procedure 1
' Note to Instructors: Stress the imper-
!_ tance of having accurate data to perform , subsequent calculation. Have students fill out a sample worksheet of RCD 0954L:4 Rev 0 1/83
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\ss INSTRUCTOR'S LESSON PLAN Pace 2 l
1 LESSON OUTLINE NOTES AND REFERENCES I D. Review ECC Calculation procedure GOP Appendix C ' Purpose Procedure Note to Instructors: Have students calculate an ECC with the instructor providing data E. Review procedure for an ICRR plot, GCP Appendix D using a sample plot F. Review the administrative section of tech specs for the review and audit . G. Discuss upcoming simulator operations II
I. PROCEDURE
A. Put plant in IC E0L, Hot Standby and ({]) Conduct a shift turoover Shift Initial cenditions: Hot Stanchy, 557'F, 2235 psig B. Provide students with RCD; have the students calculate the ECCS and shutdown margin C. Direct' students to conduct a reactor startup guided by a 1/M plot, discuss: Tech specs requirements Criticality data Manual red control Suberitical multiplication Ocubling . Indications of criticality D. Scheduled STPs: () - STP 125.002 Diesel Generator '
. Operability Test .
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NOTES AND RE.:ERENCES E. Increase power to 10-8 amps, discuss: ' NIS overlap Permissive P-6 F. Increase power to about 2 percent,' discuss: Indicitions of the point of adding heat Effects of moderator temperature and doppler on SUR Effect's on increasing T,ygon steam dump operation G. Final condition: 2 percent power H. Studen s conduct shift turnover to instructor. Check for knowledge of current condition i IV. CRITIQUE O 4. aevie overen operuienseec e = =. i 1 J O *
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(,,e - PHASE III PRCGRAM NORMAL OPERATIONS WITH MINOR MALFUNCTIONS Plant Startup - Hot Standby to Full Power Overview Once the reactor is producing heat, the secondary plant may be aligned in preparation for starting the turbine generator. The goal of the operators is to make a smooth transition to a lead'ed generater, and to gradually increase ~ that load toward 100 percent power. Many systems will be operated in manual centrol until it becomes appropriate to transfer them to autcmatic con:rol. During power operatiens it is necessary to periodically check the nuclear () ' instruments for accuracy. This is acccmplished by performing a secondary heat balance calculation. In this unit you will discuss plant operations greater than 2 percent power, heat balance calculations, and the procedure for changing plant lead. A review of additional items frem the Administrative Section of the Technical
, Specifications will also be conducted.
Teriinal Objectives Upon completion of this unit, the student will have acquired the knowledge necessary for starting the turbine generator and loading.the plant to 100 percent power. The student will also be able to explain how to perform a secondary heat balance calculation. M
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I . Enablino Objectives
- f. l
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O_ Upon completion of this unit, the student will.be able to: 1)- discuss the startup of the turbine generator. 2)--describe the integrated plant rela'tionships that are involved with startup and loading of the plant. 3)- describe the steps supplied to the plant loading procedure.
- 4) perform a secondary heat balance calculation.
- 5) perform a plant loading to 100 percent power.
References
- 1. Virgil C. Summer Training Simulator GOP-3, GOP-4, Appendix 0, STP-102.002 and STP-122.002 -
- 2. Virgil C. Summer Phase III Training Material
- 3. South Carolina Electric & Gas Company Phase II Training Material
, 4. Technical Specifications
- 5. Precautions, Limitations, and Setpoints Document 1
i l l O . 2 0958L:4 Rev 0 1/83
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LESSON OUTLINE NOTES AND REFERENCES I. INTRODUCTION - ( A. UNIT TERMINAL OBJECTIVE: Upon completion of this unit, the student will have acquired the knowledge necessary for starting the turbine generator and ( loading the plant to 100 percent power. The student will also be able to explain how to perfor.n a secondary heat balance calculation. B. OPERATIONS PLAN: Perform a reactor startup to 2 percent
- power. Provide the students with the ECC. Perform a 1/M plot during the '
startup. Continue plant power increase to
' (
full load. Perform a secondary heat 3 balance calculation during the power increase. ' C. MALFUNCTIONS SCHEDULED: 1 NONE STATE THE NEED TO ASK O'JESTIONS AS THEY ARISE STATE SASIC PRESENTATION FORMAT ( REVIEW (Optional)
.A. Review the homework assignment B. Summarize the plant operations > 2 percent power by having a student present a basic outline.
C. Review plant load change procedures in GOP-4 Purpose r'T - Precautions Initial conditions - 0958L:4 , Rev 0 1/83
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/ INSTRUCTOR'S LESSON PLAN Page 2 V) LESSON OUTLINE NOTES AND REFERENCES
?
Instructions , Final conditions D. Review procedure for performing a secondary heat b'alance calculation c STP-102.002* Purpose Precautions . Initial conditions
- Procedure Note to Instructors: Stress importance ,
that initia'l conditions be met in order to ' obtain the desired accuracy. L E. Review the following technical . specifications (Administrative Section):
)
Responsibility (6.1)
~
Organization (6.2) Offsite (6.2.1)- Unit staff (6.2.2) ' F. Discuss upcoming simulator operations II
I. PROCEDURE
A. Put the ~ plant in IC set for M0L, hot stand-by and conduct a shift turnover B. Have the students calculate an ECC and . perform a startup guided by a 1/M plot, discuss: 3 Alarms received anc cleared during the course of the startup
- Technical specification requirements Various factors that can, affect the .
ECC such as o . Changing RCS baron concentration '- s s 095SL:4 Rev 0 1/83
- Oc ;7 i INSTRUCTOR'S LESSON PLAN Page 1 LESSON OUTLINE NOTES AND REFERENCES o Inadvertent opening of steam dump valves o Excessive feeding of steam generators Manual red control Doubling Indications of criticality C. Scheduled STPs:
STP-102.002 STP-122.002
- 0. Increase power to 10-8 amps, discuss:
Data taken at 10~0 amps, and why it is taken - Permissive P-5 (~') - NIS overlap d E. Increase power to 2 percent Indications of the point of adding heat Effects of doppler and eT n start ' up rate F. Secondary plant startup Start additional condensate pump Start a main fee: water pump Establish SGWLC with main feedwater bypass valves Secure and realign emergency feedwater Warm and roll main turbine Increase reactor power to 12-15 percent Synchronize generator to 5 percent G. Lead generator to 100 percent Increase load and reactor power to - 10 percent o Loading rate: 0.5 percent / min I x> p o P-10, P-13, P-7
)
o Block 1R Hi e, PR Hi o-Lo : 0958L:4 ! Rev 0 1/83
l l -r INSTRUCTOR'S LESSON PLAN Page 4 g LESSON OUTLINE NOTES AND REFERENCES Increase load to 140-145 MW, , reactor power to 15 percent o Rate: 0.5 percent / min o Shift from bypass valves to main feed reg valves o Verify plant co.puter AFD operable Increase load to 190 MW, , 20 percent reactor power o Place rods in Auto on:
+ C-5
+ T +
avg = Tref 1'F - o Steam dump in T mode avg Load to 50 percent power
, o Start remaining pumps:
(~~') + Condensate 'J
+
Feedwater booster
+ Feecwater o Perform Component Cooling Pump Test STP-122.002 o 38 percent power: P-8 o Remove condensate polishing system from service o Perform calorimetric at 50 percent STP-102.002 Lead to 75 percent (~ 710 MW, )
( o Borate / dilute to maintain AI I o MSR in full service o Perform calorimetric at 75 percent STP-102.002 Load to 90 percent (~ 900 MW, ) o AT 90 percent, put rods in manual k o Borate / dilute to maintain AI Load to 100 percent (~ 950 MW, ) Maintain T avg within control band o C') G o Perform calorimetric STP-102.002 . 0958L:4 Rev 0 1/83
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-g. INSTRUCTOR'S LESSON PLAN s. ' y '
LESSON OUTLINE NOTES AND REFERENCES H. Final condition: 100 percent power - I. Students conduct shift turnover to instructor. Check for knowledge of current plant condition IV. CRITQUE 1 hour ( A. Review overall operations and conduct. f t
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. SC'JTH CAROLINA. ELECTRIC & GAS COMPANY 7~3 ,.
PHASE III PROGRAM i NORMAL OPERATIONS WITH MINOR MAL.:UNCTICNS Power Operations and Reactor Trip Recovery Overview Occasionally during nuclear plant operation, conditions will arise which r result in automatic shutdown of the unit. The automatic actions will place the nuclear plant in a safe condition. However, proper operator response is
- l required to place the plant in a stable shutdown condition.
This unit will provide a review of plant and system response to a reactor trip () and subsequent recovery. It will discuss preper operator actions following a unit trip along with subsequent requirements and actions'in returning the plant to operation. ~ Terminal Objective The student will be able to describe nuclear plant response to a reactor trip including precautions and requirements for plant reccvery ane return to power. i Evaluation will be performed by the program instructor's observation and ' student's oral response to questions.
. e s
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l Enabline Objectives m.
.f t
Upon completion of this unit, the student shall be able to: 1)- describe automatic actions which occur following a reactor trip. - 2)- describe, in general terms, the operator actions required to place the
' unit in a stable condition following a reactor trip.
3)'- describe the precautions for performing a reactor startup. 4)- describe ECC requirements for reactor startup.following a trip. 5)- describe the sequence of events.during a reactor startup. ( 6)- describe reactor plant response upon return to power operation in relation to boron and xenon concentrations. *
- 7) perform a reactor trip recovery from power, applying the appropriate off-normal or emergency procedures.
References
. 1. Virgil C. Summer Phase III Training Materials
- 2. Technical Specifications
[s
- 3. South Carolina Electric & Gas Company Phase II Training Materials
- 4. Precautions, Limitations, and Setocints Document
- 5. Virgil C. Summer Training Simulator ECP-5, GOP-2, GOP-3, GOP-4, SOP-102, SOP-403, 50P-404, STP 122.002, and 134.001 k
() - 4 2 0957L:4 Rev 0 1/83
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. INSTRUCTOR'S LESSON PLAN Page 1 LESSON OUTLINE NOTES AND RE.:ERENCSS I. INTRCOUCTION '
A .' UNIT TERMINAL 0 EJECTIVE: The student will be able to describe nuclear plar.t response to a reactor. trip including precautions and requirements for plant recovery and return to power. Eval-uation will be performed by the program instructor's observation and student's oral response to questions. B. CpERATIONS PLAN: Perform plant shutdown from previous day's operation
- C. MALFUNCTIONS SCHEDULED
+
Selected meter failure () - CVC-14 seal injection filter plugged
,RCS-3 RCS RTD failure (T , high)
H TUR-12 Turbine impulse pressure trans-mitter failure - NIS-5 Scurce range hi voltage failure , to disconnect j - FWM-15 Pd centrol valve pcsition failure NOTE: , In addition to the above listed mal- , functions, any of the malfunctions scheduled ' on previous simulator sessions can also be used. ' i STATE THE NEED TO ASK CUESTIONS AS THEY ARISE STATE EASIC PRESENTATION CORMAT II. REVIEW (Optional) A. Review reactor theory homework ' 4 ( t 0357L:4 . Rev 0 1/83
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(] A/. INSTRUCTOR'S LESSON PLAN Page 2 LESSON OUTLINE NOTES AND RE.:ERENCES B. Present overview of simulator operations
- - Plant shutdown from 50 percent Reactor trip liet Standby RCO, SOM, ECC Reactor startup
- Turbine loading C. Discuss system response and operation following a reactor trip Main steam system -
o Steam valves o Atmospheric reliefs, safeties o ' Extraction steam check valves {} - Steam dumps o T,y , Pressure control Feecwater system ' o Feedwater isolation o Feedwater pumos Emergency feedwater o Auto start o Flow control o Operator actions . Reactor coolant system and pressurizer, factors which help limit pressure excursicn o ' Control heaters off o Pressurizer sprays . o PORV o Safeties -
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.p INSTRUCTOR'S LESSON PLAN Page 3 V l LESSON OUTLINE NOTES AND RE.:ERENCEE Review xenon transient following ' reactor trip and return to power o Buildup o Decay . o Burnout D. Discuss SOP-404 NIS malfunction Off-Normal Symptoms Automatic actions Immediate corrective actions Followup actions Use of instrument failure guide E. Discuss reactor trip, E0P-5 Symptoms Automatic actions Immediate actions Followup actions F. Review ECC requirements Data for calculation Time requirements G. Review GOP-03 startup precautions H. Discuss Technical Specification 3/4.3.1 ' NIS Instrumentation requirements for S/U III. PROCEDURE A. Set up plant in IC from previous day and conduct shift turnover Shift Initial conditions:n 50 percent, MOL Load dispatch orders: shutdown by end of shift - . B. Scheduled STPs STP-122.002 Component Cooling Pump Test ( 0957L:4 Rev 0 1/R1
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.!v ! INSTRUCTCR'S LESSCN PLAN LESSON OUTLINE NOTES AND REFERENCES STP-13?.001 Shutdown Margin Calculations C. 'Have students continue plant shutdown D. Fail selected meter (s) for each operator and allow him to detect and determine meter via instrument failure E. Return meter to service after detected F. Initiate CVC-14, seal injection filter plugged -
Discuss effects on RCP, seals Ensure student contact auxiliary operator for repair G. Initiate NIS-5, source range hi voltage failure to disconnect, below P-10 H. Initiate RCS-3, RCS RTD failure (T control
-( ]) H channel,high)
Discuss effects on control, protection Ensure students contact I&C tech for ' repair, bistable trips . 1 I. Initiate TUR-12, turbine impulse pressure transmitter failure Discuss effects on control Ensure students contact turbine building operator for repair . J. Respond to reactor trip IAW EGP-5' Have students perform a Shutdown STP-134.001 Margin Calcula:ica before beginning reactor startup K. Perform a reactor startup, discuss . precautions and expected NIS response Ouring startup have 80p do a Component STP-122.002 - Cooling Pump Test s' 0957L:4 Rev 0 1/83
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$_ INSTRUCTOR'S LESSON PLAN Page 5 LESSON OUTLINE NOTES AND REFERENCES At 10 -8 amps discuss actions for NIS-5' l
L. ' and effects on operation M. Continue to POAH and com.mence secondary plant startup and turbine loading N. Initiate FWM-15, FW control valve position ( failure O. Following shiftover to main feed reg valve . , and discovery of faulty FRV, discuss: Actions taken Possible causes Note in procedure to verify proper ~ valve response Clear malfunction ' P. Continue plant loading as time permits () Q. Students conduct shift turnover to instructor. Check for knowlege of current plant situation IV. CRITIQUE ' 1 hour A. Review oyerall operations. B. Review malfunction responses. r ks . () I l . 0957L:4 Rev 0 1/83
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SCUTH CAROLINA. ELECTRIC & GAS COMPANY O n PHASE III PROGRAM NORMAL OPERATIONS WITH MINOR MALFUNCTIONS . Reactor Startup During Xenon Transients OVERVIEW - I Nuclear plant startups are significantly affected by certain variables. Xenon, a reactivity variable over which the operator has no control, is the major variable for which the operator calculates and compensates. In order to ' perform a startup within the Estimated Critical Condition calculation (ECC) i guidelines, the operator has to be familiar with the calculations and procedures involved. , In addition, he has to insure all requirements are ! [" ) established for a startup, and be aware of maintenance tasks in progress so that he can adequately estimate plant startup time. This unit is designed to allow the students to perform the required calculations and reactor startup during a xenon transient, thus experiencing the uniqueness of a startup which requires a timely. completion of the , procedures. Terminal Objective 4 The student will be able to satisfactorily explain and analy:e xenon transient ' effects on reactor startups as evaluated by the' program instructor's . observation and oral response to questioning. i3 im )- E l 1
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- l Enabline Objectives
,' j.
Upon completion of this unit, the student shall be able to:
- 1) . describe xenon reactivity effects on a reactor startup.
2)- discuss how the operator can vari charging and letdown flow. 3)- recall. the technical specifications which apply to reactor startups. i 4)- explain the operator actions if criticality occurs outside ECC limits. 5)- manipulate the chemical and volume control system to compensate.for chances in core xenon concentrations.
'( References
- 1. Virgil C. Summer Training Simulator GOP-3, GOP-4, 50P-102, SOP-403, and STP 123.002.
- 2. Virgil C. Summer Phase III Training Material
- 1 3. Technical Specifications
- 4. South Carolina Electric & Gas Company Phase II Training Material
, 5. Precautions, Limitations, and Setpoints Document o
i f ( a
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INSTRUCTOR'S LESSON PLAN - LESSON OUTLINE - NOTES AND REFERENCSS ed . I. INTRODUCTION A. UNIT TERMINAL 0 EJECTIVE: The student will be able to satisfactorily exp. lain and analyze xenon transient effects on' reactor startups as evaluated, by the program instructor's observation and st'udents oral response to questioning. B. OPERATIONS PLAN: Perform plant startup from hot standby to , full power during xenon transient with simple malfunctions.
- C. MALFUNCTIONS SCHEDULED 1 CRF-4 Dropped rod (one) -
a- CVC-17 Charging pump trip [) CVC-7 Loss of normal letdown i STATE THE NEED TO ASK OUESTIONS AS THEY ARISE , STATE BASIC PRESENTATION FORMAT
- II. REVIEW (Optionai) +
! A. Review . reactor theory homework B. Present overview of simulator operations ' l- - Reactor startup at peak xenon 1 Continue secondary startup i - Turbine loading C. Review CVCS Letdown , o Valve and pump interlocks . o VCT level program i - Operation of: ' i o PCV -145
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NOTES AND REFERENCES Lt. . c TV -143 ' o TV -144 o LCV-115A Charging o Pumps ( o Flow paths ^ o Seal injection - 1 o Operation of
+ FV-122
+' HV-186 Excess letdown .
BCMS o Operation
, o Accuracy o Sample points Procedures
- o. CVCS Malfunction 50P-102 Note to Instructors: In the above discussions, ensure that the indications and operator actions for the following are covered:
LCV-115A failure
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PV -145 failure . ( - FV -122 failure o Loss of Seal Water ' s 1, o Loss of Normal letdown D. Review RCP Seal System Injection and' leakoff flow path Types of individual seals Seal pressure requirements
. Seal precautions- ,
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rs k) INSTRUCTOR'S LESSCN PLAN Page 3 LESSON OUTLINE NOTES AND REFERENCES ~ E. Xenon transient during startup Xe buildup Xe decay Xe. peak-III. PROCEDURE A. Set up plant in IC Set for HZP and conduct a shift turnover - Shift Initial conditions: Hot standby, about 4 hours after a reactor trip from ISO days of. continuous operation; ' T,yg = 557'F, P = 2235 psig, ARI Lead dispatch orders: 100 percent by the end of the shift B. Scheduled STPs [} - STP 123.002 Service Water System Pump Test C. Perform a reactor startup Students calculate ECC Discuss Xe transient due to reac:cr trip ar.d the effects of Xe burnout after power is achieved Increase power to 10-8 amps D. ' Increase pcwer to 2 percent E. Startup secondary plant Start additional condensate pump; one main feed pump
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Maintain S/G level with main feedwater bypass valves . Secure, realign emergency feedwater Warm, roll main turbine ~ 0356L:4 p.v n t ro,
INSTRUCTOR'S LESSON PLAN Page 4,
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LESSON OUTLINE NOTES AND RE.:ERSNCSS
. Increase reactor power to 12-15 percent .
Synchronize generator to 5 percent F. Load generator to 100 percent ' Increase load to 10 percent Initiate malfunction.CVC-7, loss of Evaluate using a copy of normal letdown - Attachment I; SGP-102 Increase load to l'5 percent - Clear CVC-7 Increase load to 20 percent o Rods in Auto >-15 percent o Steam dumps in T,yg mode '
- Increase load to 50 percent o Ccndensate, FW booster, and .
feedwater pu=ps o P-8 o Perform calorimetric o Perform Service Water System Pump STP-123.002 Test ' o Initiate malfunction CRF-4, one Attachment I dropped red at - 40 percent power 50?-403
+ Recognition
+
Corrective action
+
Clear malfunction Increase load to 75 percent o AT ~ 65 percent power initiate Attachment I mal function CVC-17, charging pump 50?-102 trip
+ Recognition
+
Corrective action- .
+ Tech specs
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Clear malfunction o Perform calorimetric at 75 percent j j l
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-r INSTRUCTOR'S LESSON PLAN age 5 LESSON OUTLINE NOTES AND REFERENCES Increase load to 90 percent
{'- o Borate / dilute for AI o Rods in manual at 90 percent Increase load to 100 percent G. Final condition: 100 percent power ( H. Students conduct shift turnover to instructor. Check for knowledge of
- current situation.
IV. CRITIQUE A. Review overall operations and conduct. B. Review malfunction response. - C
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SOUTH CAROLINA ELECTRIC & GAS COMPANY rs A,,) - PHASE III PROGRAM NORMAL OPERATIONS WITH MINOR MALFUNCTIONS Power Operations 'and Turbine Trip Recovery Overview ' Occasionally during nuclear plant operation, conditions will arise which result in automatic shutdown of the unit. The automatic actions will place the nuclear plant in a safe condition. However, proper operator response is ' required to place the plant in a stable shutdown condition. This unit will provide a review of plant and system ' response to a turbine trip ("') and subsequent recovery. It will discuss proper operator actions following a
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unit trip along with subsequent requirements and actions in returning the plant to operation. Terminal Objective The student will be able to describe nuclear plant response to a turbine trip including precautions and requirements for plant recovery and return to power. Evaluation will be cerformed by the program instructor's observation ' i and' student's oral response to questions. l' 4 1 4
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f j Enablino Objectives- - .' ~ . Upon completion of this unit, the student shall be able to: . 1)- describe automatic actions which cccur following a turbine trip.
-2)-L describe, . in general terms,~ the operator actions required to place the unit-in a stable condition following a turbine trip.
.3)- describe the precautions for performing a plant startup.
4)- describe ECC requirements for reactor startup following a trip. 5)- describe the sequence of. events during a reactor startup. 6)- describe reactor plant response upon return to power operation in relation to boron and xenon concentrations.
- 7) perform a turbine . trip recovery, applying the appropriate off-normal .
or emergency procedures.
' Re fe rence s -
- 1. Virgil C. Summer Phase III Training Materials 4
, 2. Technical Specifications 3.
' - V South Carolina Electric & Gas Company Phase II Training Materials 4 Precautions, limitations, and Setpoints Document 5. Virgil C. Summer Training Simulator SOP-102, 50P-118, 50P-214,
; .50P-403, 50P-404, and STP-105.004. 2 i
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INSTRUCTOR'S LESSON PLAN Page 1 LESSON OUTLINE NOTES AND REFERENCES I. INTRODUCTION - A. UNIT TERMINAL OBJECTIVE: The student will be able to describe nuclear plant response to a reactor trip including precautions and requirements for plant recovery and return to power. Evaluation will be performed by the program instructor's observation and student's oral response to questions. B. OPERATIONS PLAN: Perform plant unloading from 50 percent to 25 percent with simple malfunctions. C. MALFUNCTIONS SCHEDULED Selected meter failure 73 - CCW-1 letdown heat exchanger tube leak Y' - CRF-7 stuck rod TUR-1 inadvertent turbine trip NOTE: In addition to the above listed malfunctions, any of the malfunctions scheduled on previous simulator sessions can also be used. STATE NEED TO ASK OUESTICNS AS THEY ARISE STATE BASIC PRESENTATION FORMAT II. REVIEW (Optional) A. Review reactor theory homework ' B. Present overview of simulator operations . Plant unloading from 50 percent to 25 percent Turbine trip . Hot standby g. RCD, SOM, ECC l 09c0L4 Ree 0 1/83
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lNSTRUCTOR'S LESSON PLAN #9' O G LESSON OUTLINE NOTES AND REFERENCES-J Reactor startup
- Turbine. loading C. Discuss system response and operation-
#>llowing a turbine trip Reactor trip Main Steam System-o Steam valves o Atmospheric reliefs, safeties
) o Extraction steam check valves Steam dumps o - T,yg, pressure control Feedwater System o Feedwater isolation o Feedwater pueps ' i - Emergency feedwater
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o Auto start o Flow control o Operator actions ' t Reactor coolant system and pres-surizer, factors which help limit pressure excursion o Control heaters off o Pr.essuri:er sprays
- o- PORV i
o Safeties D. Review xenon-transient following reactor trip and return to power
- E. Discuss turbine trip in SOP-214.
l - Symptoms . Automatic action Immediate action - Subsequent action
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( l' INSTRUCTOR'S LESSON PLAN Page 3 LESSON OUTLINE NOTES AND REFERENCES F. Discuss CCW off normals in 50P-I8 ' s Symptoms . Automatic actions ~ Immeciate actions Followup actions G. ~ Discuss red control off normals in 50P-403 Symptoms
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Automaticactions Immediate actions Followup actions H. Discuss IR NIS off normals in 50P-404 - Symptoms Autcmatic actions Immediate actions Followup actions
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Review ECC requirements I. l Data for calculation Time requirements ' J. Review startup precautions K. DiscussiechnicalSpecifications6.6
- through 6.9 III. PRCCEDURE A. Put plant in IC set (later) and conduct shift turnover .
Shift Plant status: 50 percent, equilibrium xenon *
. Load dispatch orcers: 25 percent at end of shift .
B. Scheduled STPs STP-IO5.004'RHR pump test - C. (~ x Have students conduct plant unloading IAW .,5 GOP-4
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INSTRUCTOR'S LESSON PLAN Page 4 LESSON OUTLINE NOTES AND REFERENCES D. Fail selected meter (s) for each operator and allow him to detect and determine meter vice instrument failure - E. Return meter to service after detected F. Initiate CRF-7, stuck rod ( - Discuss effects on AI Ensure students consult procedures
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Evaluate response . Clear malfunction G. Initiate CCW-1, letdown heat exchanger tube leak Discuss effects on continued plant operation Ensure students notify auxiliary operator Evaluate response H. Initiate TUR-1, inadvertent turbine trip Discuss plant response Evaluate response I. Recover from trip and perform a reactor ' (' startup J. Initiate NIS-4, IR under compensation Discuss effects on operation Evaluate response ' ( K. Continue to POAH and begin secondary plant startup L. Discuss effects of xenon transient on startup s 0960L4 Rev 0 1/83
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LESSON OUTLINE - -
- NOTES AND REFERENCES -
M. Continue loading as time permits - N. Perform RHR pump. test STP-105.004
- v. CRITIQUE 1 Hour A. Review overall operations.
B. Review malfunction response 7 4 i 5 J i. 1 iO 1 J 1 4 ( . 4 i l0 0960L4 Rev 0 1/83
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, PHASE III PRC3 RAM PLANT TRANSIENT.RESFCNSE
, load Rejection Transients and Acciden: Assessment and Identification Overview .
During power operations a control room operator can be confronted w degrees of load rejections. e The op'rator should be able to determine .he " degree load. of change in system parameters .following variousn degrees o In addition to these transients, abnormal conditions sometimes occur
' which the control room operator will have to detect and evaluate. The d- seriousness of each event will largely depend upon the type of malfunction ,
However, the actions of the operator can significa:aly affect of that malfunction. nces the conse The operator is relied upcn to detect, identify and follow the correct emergency or abnormal procecure which s provides 1 for operation in returning the plant to a safe and stable condition . This unit will accomplish two goals: 1. It will provide the student with the experience of plant operation' (' - during load rejection under a wide range of initial conditions , thus ! improving transient. his ability to detect, evaluate and respond to this type o 2. This unit will present'the student with the various procedures available to enable him to identify and respond to various accident conditions. In addition, it will allow the students the opportunity i- to apply these procedures to actual accident or abnorma"l conditions ~ l ' . and increase his awareness of plant respense and control room atmoshphere during accident conditions.
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Terminal Objective ,) U When the student completes this unit he will be able to predict expected plant l parameter changes during varying degrees of load rejection. The student will be capable of detecting load changes and discussing system transient analysis associated with the major parameters. _The student will discuss plant technical specifications applying to systems and operations covered during this unit. The student will also be able to adequately explain the different types of procedures available in the control room and be able to correctly use the' applicable procedure during an accident or abnormal condition as evaluated by the program instructor's personal observation and questioning. Enablino Obiectives . Upon completion of this unit, the student shall be able to: 1) discuss automatic control system response to a 10 percent load step q C^ change.
- 2) discuss plant response to a 50 percent Icad rejection.
- 3) explain plant parameter changes during Icad changes.
4) discuss ;! ant response during load rejections when automatic control systems are in manual. 5) respond properly to a load rejection following the appropriate plant procedures.
- 6) describe the ba ic sections of the Emergency Procedures.
- 7) demonstrate an
.bility to use the Control Roca procedures during
(' accident or abnormal conditions. 8) identify the major accidents using the indications on the Main Control Board. ( References
- 1. Virgil C. Summer Simulater E0Ps.
- 2. Virgil C. Summer Phase III Training Material -
- 3. Virgil C. Summer Phase III Training Material.
'v' 4. Technical Specifications. 2
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Page 1 INSTRUCTOR'S LESSON PLAN k^ LESSON OUTLINE NOTES AND REFERENCSS
. INTRODUCTION.
- A. UNIT TERMINAL 0 EJECTIVE:
When the student completes this unit he will be able to predict the expected plant parameter change during varying degrees of { i ( load rejection.- T'he student will be able to detect load changes and discuss the system transient analysis associated with the major parameters. The student will discuss plant technical specifications , that apply to system and operations - covered during this unit. Explain the different types of procedures available in the control room and'be able to correctly use the applicable procedure during an accident or abnormal condition as evaluated by the program instructer's ' cersonal observation and questioning. B. OPERATIONS plan: Allow the students to maintain ' reactivity balance during 100 percent i power peak Xe burnout. Initiate 10 ( percent step changes to demonstrate response without auto red control or steam dumps.- Perform the same with 60 percent load rejection. ( - Allow the students the opportunity to experience the major accidents from an observer viewpoint. Report any ! accident as you feel necessary and - - i have students follow the emergency procedures. Slow simulator speed to l help students observe more indications . during the accident. Rev 0 1/83
Page 2 p[ INSTRUCTOR'S LESSCN PLAN LESSON OUTLINE NOTES AND REFERENCES C. MALFUNCTIONS SCHECULED: CVC-1 Boric acid flow transducer failure RCS-5 LOCA (large) - RCS-2 S/G tube break ( ,- MSS-3 FWM-8 Steam break inside containment Feed break inside containment ! STATE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATICN FORMAT . NOTE: In addition to the above listed malfune,tions, any of the malfunctions scheduled on previous simulater sessions can p also be used. N I. REVIEW (Optional) A. Present overview of simulater operations Lead rejection transients o 100 percent power peak xenon burnout ) o Transient response 10 percent step
+
Without auto red centrol * *
+
l 1 ( Without steam dumps o Transient respense 50 percent rtjection 1
+
With aute red centrol and + steam dumps I I
+ ,
Without auto red control
+ Without steam dumps 4
Accident identificatten/ assessment - o Observe plant response o Precedure use *
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i o Observe major accidents
+ LOCA
+ Tube break
+ Steam break
+ Feec break
( NOTE: The above presentation is to be evaluated by the instructor based upon the students knowledge of the diagram, effectiveness of his communication method, and ability to explair. system interrelations. ' gg B. Discuss plant response durir.g the following: 10 percent step reduction without auto red control o Steam dump o Makeup system o Nuclear power response o Reactivity effects o AI limits . ( 10 percent step reduction without steam dumps o Rod Control o Makeup system ! o Nuclear power response o Reactivity effects . o al limits 50 percent loac rejection (^') o Steam dumps o Rod control 22620:4 Rev 0 1/83
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INSTRUCTOR'S LESSON PLAN LESSON OUTLINE
, NOTES ANC RE.:ERE.NCES o Makeup system o
AI limi.ts o Nuclear power respense
,50 percent lead rejection without auto rod control
( o Steam dumps o Reactivity effects o Nuclear power respense 50 percent load rejection without . steam dumps o Rod contr 1- . t o Reactivity effects a Nuclear power response C.
- Discuss procedures cencerning lead-rejection
)
"~ D.
Discuss Emergency 0;erating Precedure 4 E0P-1. Purpose Symtems Automatic actions Immediate opera:cr actions Follow up' action . E. Discuss the Technical Specificatien 3/:.5 PROCEDURE A. Set up plant in IC Set (later) and conduct a shift turncver i - Shift Initial conditiens: 100 percent power B. Scheduled STPs . NONE C. With the plant at 100 percent power, -
) perform a 10 percent step load rejecticn
-c with and without auto rod control.
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! ) INSTRUCTOR'S LESSON PLAN d LESSON OUTLINE NOTES AND REFERENCES Trend the following parameters -
o T - avg o PZR level ~ o PZR pressure o S/G level (1) ( o S/G pressure (1) o AT (1) Once the plant has stabilized, review the transient with the students using the trend results D. Reinitialize and perform a 10 percent step load rejection without steam dumps. Trend and review transient as per step C E. Reinitiali:e and perform a 50 percent load rejection trend and review the transient
'N_) as per step C F. Reinitiali:e and perform a 50 percent load rejection without red control. Trend and -
review the transient as per step C G. Reinitiait:e and perform a 50 percent load rejection without steam dumps trend and review the transient as per step C H. Reinitialize and explain plant conditions . { and objectives to students System lineups Plant parameters Operational status ( .- Power history i I. Allow students to utilize akeup system to . maintain AI limits . J. During a boration initiate CVC-1 boric f~h acid flow transducer failure (_ / - Discuss method of continued boration of desired quantity 22520:4 Rev 0 1/83
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Page 6 t'Y -\ ,) INSTRUCTOR'S LESSCN PLAN LESSON OUTLINE NOTES AND REFERENCES Evaluate response.using a' copy of Attachment I. K. Reinttialize'at 100' percent. L. Initiate DBA RCS-5, discuss: Indications ( - ECCS response Procedure application Operator actions M. Retnitialize and, if desired, repeat RCS-5 at reduced simulator speed or smaller break N. Reinitialize and initiate RCS-2* leak rate
= 660 gpm and ramp of long enough time to observe indications prior to trip.
Discuss: Indications Procedure amplication Opera.or actions Plant response 0. Reinitiali:e and initiate MSS-3 steam break insice containment, again with a ramp time long enough for evaluation prior to the trip. Discuss: Plant response . ( Indications Procedure application Operator actions P. Reinitialt:e initiate FWM-3 and discuss: Indications . Plant response - Procedure application Operator actions O
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" ~ Page 7 INSTRUCTOR'S LESSCN PLAN LESSON OUTLINE NOTES AND RE.:ERENCSS Q. Reinitiali::e and repeat any of the major
. casualties or minor calfunctions with no operator actions and observe plant response j- V. CRITIQUE 1 Hour
, A. Review overall operations.
B. (.. Rev.iew malfunction response. . t1 i
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SOUTH CAROLINA ELECTRIC & GAS .\
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W;. r PHASE III PROGRAM
- PLANT CASUALTY hRAINING
' Reactor.Startup to Power, Malfunctions C '
Overview
- The proper operation of a nuclear power plant is dependent upon many electrical, electronic, and mechanical support systems. A failure of any particular instrument or device will probably have an effect on sc=e system '
and subsequently af fect plant operation. The consequences of a failure will largely depend upon the type of failure and the system (s) affected. However, the operator will provide a significant contribution'to subsequenc plar.: operation.
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An astute and knowledgeable operator should be capacie of diagnosing the failure and taking appropriate action as specified in c;eration procedures and technical specifications. This unit is designed to give the prospective control room operator experten in dealing with plant malfunctions. These are conditions which ;ose no immediate ha:ard to plant operation or safety. However, without operator action, they could-develop into a serious condition involving possible plant trip.. In addition, during this unit, an'e studen; will receive a star.up examina-tien. This is an examinatica perfor: ed by the program instruct:r arid conducted in accordan:e with the guidelines adopted for the final certifica-( tion startup exam. n) t
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/~T The-stu' cent wil be able to identify system malfuncticns that affect nuclear
. instrumentation and control of reactor operations. The operator will be able to utilize proper system abnormal operating procedures to pla:e the plant in a safe condition. The operator will develop a philosopny of operations which will enable him to combat any unsafe plant condition.
Enabling Objectives Upon completion.of this unit the student shall be able to: '- 1)- identify plant malfunctions through use of ararm and cc.. trol board
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indication.
- 2) recall the proper immediate operator actions for the particular plant i .
problem and refer to the appropriate abnormal operating procedure for
- appropriate subsequent operator actions.
1 ,
- 3) recall any technical specifications limitations associated with the j
~
particular plant failure and apply these limitations to subse:;uent ~ plant operations. . 4)- develop a basic plan outlining an operator philoscphy in dealing with j minor plant problems and systems malfunctions. l 5) perform a safe reactor star:up as evaluated by the programt instructor. ) o . 3 References i
! 1. Virgil C., Summer Training Simulator 507-102, 50P-405, 507-403, E0P-10, i
( 2. STP-102.003,^ ST:-125.002. Technical Specifications
- 3. NIS System diagrams
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. INTRCCUCTICN -
A. UNIT TERMINAL OBJECTIVE: The student will be able to recogni:e, diagnose and respend correc-ly te varicus plant malfunctions. This ability will be ( evaluated by instructor observation and the student's cral response to questions. B. OPERATIONS plan: Conduct a control board misalignment if desired. Perform a Reacter Startup Evaluation of one student. Terminate ' evaluation once 2 percent power has been attained. Conduct normal plant loading e towards 100 percent power. Con:uct the scheduled malfunctions. C. MALFUNCTIONS SCHEDULED: NIS Source range channel failure CRF T reference failure (red - control) CND-2' - Hetwell level transmitter failure CVC Makeup centrol failure in all medes CVC Loss of charging pump TUR EHC first-stage pressure transmitter failure FW>l FW beester pump trip NOTE: In addition to the abcve listed malfunctions, any of the calfunctions . scheduled on previcus simulater sessions may also be used. . STATE THE NEED TO ASK CUESTICNS AS THEY ARISE (V . STATE EASIC pRESENTA7ICN FORMAT ,- 225SD:4 y Rav n 1/o1
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["' INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES PRESENTATION II. REVIEWL(Optional) . A. Review. homework assignment B. , Present overview of C simulator operat' ions c - Reactor startup evaluation Normal plant loading towards 100 t percent Selected malfunctions
- C.
Review SOP-405 Nuclear Instrumentation System malfunction Review Tech-Specs 3/4.3 . D. Review SOP-403, E0P-10 Rod Control System Malfunctions Review Tech Specs 3/4 1.3, 3/4.2 E. Review SOP-102 CVCS Malfunction ' Revtew Tech Specs 3/4.5.2, 3/4.5.3
' I'I I . PROCEDURE A. Initialize at (Later) i Conduct a shift turnover and explain plant conditions and objectives to students j '
( - System lineups Plant parameters Operational status Power hi s*.ory 0 'B. Scheduled STPs' STP-102.003 IR range analog channel ' test
- STP-125.002 diesel generator i operability test-225SD:4 '
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i INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCSS C. Continue plant leading towards 100 percent power, discussing boration/ dilution requirements perform an IR analog channel test STP-1C2.C03 Perform a diesel generator oper. test STP-125.CC2 ( 0. Initiate CVC-3, mckeup control failure discuss: . Effect on plant operation Continue operations with Makeup System in manual, or clear malfunctions to simulate repairs as desired. - E. Once Rod Control is in auto, initiate CRF-8. T reference failure (red control) discuss: Input to rod control Effect on plant operation . Clear malfunction upon request for repair F. Continue plant icacing, initiate CND-2 hotwell ievel transmitter failure, discuss: Manual control of level - makeup and reject Clear malfunction upon request for ( G. repair Continue plant leading, ensure EHC is in first-stage pressure feedback. Initiate TUR-6 EHC first stage pressure transmitter (, failure, discuss: EHC response i.e., cause for possible . load change Clear malfunction upon request for - repair -\ p) 22530:4 Rev 0 1/83
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- H. Continue plant leading, initiate Pn'M-6 F4 .
i booster pump trip, discuss: Effect on plant capability Clear malfunction upon request.for
, repair
( ~I. Initiate CVC-17 loss of charging pump, select operating chargin'g pu=p, discuss: Technical Specifications Effects on PZR level, letdown temperatures, seal flow and VCT level. J. Student conduct shift turnover to ' instructor
- IV. CRITIQUE '
A. Review overall operations conduct. . B. Review malfunction responses i i < 1 i ( l
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' SOUTH CAROLI!!A ELECTRIC & GAS V.
PHASE III PR03 RAM PLA!!T CASUALTY TRAI!It;3 C Reactor Startup to Power, Malfunctions Overvfew . The operation of a nuclear power plant normally involves maintaining stea state conditions. On those occasions when the plant deviates frca normal operation, the operators will have to react to correct the problems and bring the plant back to a stable condition. This unit is designed to teach the operator how to properly react to various malfunctions during varying plant conditions to bring the plant back to a safe and stable condition. ~ Q Als'o during this unit, one student will receive a startup examination
. This
' is an examination performd by the prograa . instructor ar.d corducted w ng fello i the same cuidelines as the final certification startup exam. '-
Terminal Cbjective The student will be able to identify control system failures and r take pro action to return the plant to a safe condition. b+ 1 C967L:4 a... n . --
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Enabline Objectives-
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'Upon completion of this unit, the student shall be able to:
1)- discuss Red Control Abnormal Opera, ting Procedures. ( ' 2) review any technical specifications applicable t'o movable control assemblies.
- 3) perform a safe reactor startup as evaluated by the program instructor.
3 i f -References 1. Rod Control Abnormal Operating Procedures, STP-105.004
- 2. SCE & G Phase III training material 2.
Technical Specification on movable control assemblies. 7 i = F I 4 l l
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Page.1 r/ INSTRUCTOR'S LESSON PLAN V LESSON OUTLINE NOTES AND REFERENCES
. INTRODUCTION .
A. UNIT TERMINAL 03JECTIVE: The student will be able to recognize, dia.gnose and rescond correctly to various plant mal functions. This ability will be . ( , evaluated by instructor observation and the student's oral respo'nse to questions. B. OPERATIONS PLAN: Conduct a control. board misalignment if desired. Perform a reactor startup evaluation of one student. Terminate ' evaluation once 2 percent power has been attained. Conduct plant leading towards . c 100 percent power from a point where the . O(~'s generator is reacy to synchronize to the grid. Conduct the scheduled malfunctions. C. MALFUNCTICNS SCHECULED: NIS Noisy source range channel (on startup) FWM Main feedwater pump speed malfunction CRF Stuck red FWM Tube leak in feedsater heater ' RCS Faulty primary RTD TUR Inadvertan turbine trip NOTE: In addition to the above listed malfunctions, any.of the calfunctions ([ scheduled on previous. simulator sessions may also be used. . STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT 0967L:4 Rev 0 1/83
2:::- F- Page 2 t l' .yi INSTRUCTOR'S LESSCN PLAN i# LESSON OUTLINE NOTES AND REFERENCSS e I. REVIEW (Optional) - A. Review homework B Present an overview of simulator operations
. Reactor startup evaluation
( - Normal plant loading towards 100 percent Selected malfunctions C. Review failure of control bank (s) to move procedure (EOP-10). Re-review Tech Spec 3/4.1.3 ' D. Review Rod Position Indication Malfunction ' Procedure (SCP-403).
,f-J E.
Review Turbine Trip Procedure (50P-214).
\ xil. PROCEDURE A. Initialize at (Later) and perform a shift turnover. Explain plant conditions and objectives to students:
System lineups Plant parameters
, Operational status Power history B. STPs scheduled STP 105.004 RHR pump test C. . Continue plant loading towards 100 percent power, discussing beration/ dilution
,. requirements Perform RHR pump test .
- STP-105.004 D.
Initiate FWM-5, main feedwater pump speed, I discuss: -
'g(2 Effect on plant operation i.e., power capability of emergency feedwater, and one main feed pump 0967L:4.
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.,F Page 3 INSTRUCTOR'S LESSON PLAN LESSON OUTLINE . NOTES AND REFERENCES Clear malfunction upon request for repair E. Initiate CRF-7, stuck red, discuss:
, Tech Spec. implications, i.e., shutdown margin determination, continuation of , '( -
operator Clear malfunction up'on attempt to realign the red F. Initiate FWM-9, tube leak in feedwater heater, discuss: Isolation of the heater Effect on plant operation Continue operation with heater
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isolation . s' G. Initiate RCS-9, faulty primary RTD, . discuss: Effect on plan: operation Tripping of bistables H. Initiate TUR-1 inadvertant turbine trip, discuss: Proper plant response, i .e. , P-S Proper operator response with respect to Rx trip
.(.. I. ' Students conduct shift turnover to instructor IV. CRITIQUE A. Review overall operation conduct. :
(. B. Review malfunction responses O . 9 0967L:4 I Rev 0 1/83
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an 50'JTH CAROLINA ELECTRIC & GAS COMPANY k[ PHASE III PRO 3 RAM P! ANT CASUALTY TRAINING Reactor Startup to Power, Malfunctions C-Overview . The Nuclear Steam Supply System for a typical Pressurized Water Rea is designed to operate properly with little or no operator assistance Normal . plant conditions are ma'intained by automatic systems and controls. Unsafe conditions, w" hen detected, cause alarms and other indications to initiate a sequence of events culminated by an operator taking the necessary actions to correct the problem or to safely shutcown the plant. Reliability is g
guaranteed technique. through necessary and proper training in this response orien:ed ~
This unit is designed to train tne prospective plant operator to re'spond properly and in a timely manner to minor plant malfunctions. These malfunc-tions are defined to ce conditions which pose no immediate hazard plant to operation or safety. However, with no cperator action, they could develop into a serious condition involving possible plant trip. During this unit, one student will receive a startup examination O l 1 0966L:4 On., n 1#07
Terminal Objective
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. O The student will be able to identify various system malfunctions and be'able to take the proper actions to' maintain pro,per plant performance at all times.
Enablino Objectives Upon co.mpletion of this unit, the student'shall be able to: ! 1)- discuss the loss of Feedwater System Abnormal Operating Procedure. ( ,'2) analyze plant conditions to identify malfunctions through the use of alarms and control b'oard indications.
- 3) recall related technical specifications. -
- 4) perform a safe reactor startup as evaluated by the program instructor.
4 References
, 1. Abnormal Operating Procedures, STP-133.001, STP-125.002 i 2. System diagrams for Main Feedwater System
)-
- 3. SCE & G Phase III training material i
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A C Page 1 INSTRUCTOR'S LESSCN PLAN LESSON OUTLINE NOTES AND REFERENCES INTRCDUCTION
\ A. UNIT TERMINAL OEJECTIVE:
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: , Perform a Reactor Startup Evaluation of one student. Terminate evaluation once 2 percent power has been attained. ' Conduct normal plant leading towards 100 percent power. Concuct the schtduled
, malfunctions. .
C. MALFUNCTIONS SCHEDULED:
. { ) -
. . NIS-S - Failure of source range high voltage to disconnect-MSS Steam dump control valves fail ' PRS Pressurizer pressure channel failure FWM Trip of main feedwater pump MSS Steam generator relief valve opens + PRS Pressurizer spray valve failure NOTE: Ir. addition to the above listed
- malfunctions, any of the mal' functions scheduled on previous simulator sessions
, may also be used.
STATE THE NEED TO ASK OUESTIONS AS THEY .
-ARIS:
()'- STATE BASIC PRESENTATION FORMAT -
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Page 2 INSTRUCTOR'S LESSON PLAN v' LESSON OUTLINE NOTES AND RE.:ERENCES
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C" ' A. Review homework assignment Present an overview of simulator operations Normal plant loading towards 100 ( - percent Selected malfunctions - B. Review E0P-02 loss of secondary coolant without SI C. Review SOP-210 loss of one feedwater pump D. Review SOP-210 loss of feedwatee system - III. PROCEDURE: A. Initialize at (Later) and perform a shift s turnover. Explain plant conditions and q objectives to students: 4
'v' -
System lineups Plant parameters - Operational status ' Power history B. STPs scheduled STP -133.001 Axial Flux Difference Calculation 4 STP -125.002 Diesel Generator ( C. Operability test Continue plant loading towards 100 percent power, discussing boration/ dilution requirements l ( - Perform a Diesel Generator STP-125.002 Operability test ' O. Initiate MSS-5, steam dump control valve fails, discuss: Indications of problem 0966L:4 Rev 0 1/83
1 Page 3 gf INSTRUCTOR'S LESSON PLAN O' LESSON OUTLINE NOTES AND REFERENCES Effects en plant
- Clear malfunctions upon request for repair-E. Initiate PRS-1,'pressuri:er pressure channel failure, discuss:
( - Failure's effect on pressure control Bistables associated'with failure Clear malfunction upon request for repair F. Continue plant loading, initiate MSS-7 steam generator relief valve opens (100 - percent), discuss: Indications of problem Isolation capabilities '
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'CJ- safety related Clear malfunction some time after repairs are requested G. Perform an Axial Flux Difference STP-123.001 Calculation H. Continue plant loading, initiate PRS-3 pressurizer spray valve failure (with manual control), discuss:
- Indications of problem Isolation (if possible) or reduction of flow if no manual operation Ability to continue operation Clear malfunction upon request for repair .
I. Continue plant loading, at approximately 75 percent, initiate FKM-1 trip of main feedwater pump, discuss: Of : 0966L:4 ' Rev 0 1/83
INSTRUCTOR'S LESSON PLAN page e LESSON OUTLINE
- NOTES AND REFERENCES Effect on operations, i.e., turbine runback, steam dump actuation, control rod response Clear malfunction upon request for r investigation and repair J. Students conduct shift turnover to instructor.
IV. CRITIQUE A. Review overall operation conduct.
- 8. Review malfunction responses v
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0 l 1 I DAY 14 O O
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SOUTH CAROLINA ELECTRIC 1 GAS COMPANY Q,o. PHASE III PROGRAM PLANT CASUALTY TRAINING Load Follow Operation With Malfunctions Overview Power changes because of load follow operations in a PWR causes problems with xenon , oscillations and the effect on maintaining AI within its operating band. Day 14 and 15 are designed to give the student experience of plant operations during load follow operations. During this session the student will decrease load from 100%. While power is being i decreased, xenon is being produced and the operator will have to compensate for the xenon buildup. 'The operator will have to respond to minor plant malfunctions. These malfunctions are defined to be conditions which pose no irmiediate hazzard to the plant operation or safety. However, with no operator action they could develop into serious conditions involving possible plant trip. At the end of this day, a SNAP of the final conditions will .be taken for Day 15. Terminal Objective The student will be able to change power and maintain AI within its limits while maintaining proper plant performance. l m
Enabling Objectives l Demonstrate the , actions to decrease power as xenon builds in. '
' Discuss the applications of Technical Specifications in regards to AI
- - limits.
5 Demonstrate the ability of controlling AI without control rods movement. i l O i j l }{ 1 4 i i i !0 1 1 i
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INSTRUCMP'S LESSON PLAN Page 1 g LESSON OUTLINE t NOTES AND REFERENCES U. I. INTRODUCTION A. UNIT TERMINAL OBJECTIVE: The student will be able to maintain AI within limits during load follow operation with various ' mal functions . B. OPERATIONS PLAN: Conduct load follow operations. On request from dispatcher, ramp generator output from 930 MWe to 450 MWe over a two hour period.
~ Maintain 450 MWe until load increase requested from dispatcher (to be continued during Day 15).
C. MALFUNCTIONS SCHEDULED: ' RCS-ll Accumulator leakage RCS-12 Reactor Vessel Flange Leakage MSS-12 Steam Header Pressure Transmitter O rei>#re FWM-2 Condensate Pump Trip CRF-il Power Cabinet Urgent Failure CVC-16 Charging Flow Control Valve Failure NOTE: In addition to the above listed malfunctions, any of the malfunctions scheduled on previous simulator sessions may also be used. STP Schedule: None. I
I. PROCEDURE
A. Initialize at 100% and perform a shift turnover and explain plant conditions and objectives to students. System Lineups Plant Paramaters
, Operational Status ) -
Power History
INSTRUCTOR'S LESSON PLAN Page 2 n LESSON OUTLINE U NOTES AND REFERENCES
.B. Dispatcher ask for a 450MW decrease in power over a two hour period. Ensure operators are aware of iodine sampling requirements.
C.. As load decreases, initiate FWM2 (condensate pump trip) with reactor power at >95*.. Discuss Operation of Condensate System Discuss Condensate Pump Trips Clear Malfunction on Request D. Initiate RCS-Il (Accumulator Leakge) Discuss: Technical Specifications S0P's Operators Drain to Limit ' Possible Dilution Problem E. Initiate RCS-12 <10 gpm leakage (Reactor Vessel Flange Leakage) U Discuss Technical Specifications. Perform Leak Rate Calculation. F. Initiate CRF-11 (Power Cabinet Urgent Failure) i Discuss ways to control power without rod motion. G. Initiate MSS-12 (Steam Header Pressure Transmitter Failure). Suggest failing low with ramp. Discuss effect on speed control. Operators should take manual control of speed controller. Clear when repaired. H. Initiate CVC-16 (charging flow control valve
. failure).
Operator can take manual control of FCV-122 and maintain PZR level. I. At end of Day write SNAP to be used in Day 15. t .r
l 1 INSTRUCTOR'S LESSON PLAN Page 3
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III'. Critique A. Review overall operations conduct. B.. Review malfunction' responses with students. . l l' l: [. de h O 1
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. SOUTH CAROLINA ELECTRIC & GAS COMPANY ^Q. \_s/. PHASE III PROGRAM PLANT. CASUALTY TRAINING Plant Load. Follow Operations with Malfunctions Overview This is a continuation of-Day 14. During this training session the load follow operations will continue with. the problems of maintaining AI within limits.
1 Because of the time it takes .for xenon to peak after power manipulation this + session consists of 2 days. l Terminal Objective . The student will be able to change power and maintain AI within the limits set l forth' by the operating curves.
- O Enabling Objectives Demonstrate the actions to decrease power as xenon builds in.
i Discuss the applications of Technical Specifications in regards to al limits. Demonstrate the ability of controlling AI without control rods movement. i l 1 I i iO 4
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INSTRUCTOR'S LESSON PLAN Page 1 fs LESSON OUTLINE I NOTES AND REFERENCES l ' I. INTRODUCTION A. UNIT TERMINAL OBJECTIVE The student will be able to maintain AI within limits during load follow operation. B. OPERATIONS PLAN ! Continue with load follow operations from Day
- 14. -Increase generator load from 450 MWe per dispatcher instructions with various malfunctions.
C. MALFUNCTIONS SCHEDULED CRF-2 Auto Rod Speed Failure CCW-8 Seal Water Heat Exchanger Leak FWM-15 FW Control Valve Position Failure
- EPS-6 Diesel Generator Trip PR S-3 Pressurizer Spray Valve Sticks EPS-13 Generator Breaker Fails to Trip
() D. STP SCHEDULED STP-125.002 - Diesel Generator Operability Test II. PROCEDURE A. Initiate in SNAP written at end of Day 14. Review: Plant Conditions Power History Operational Status B. Perform STP-125.'002. During STP initiate + EPS-6 (diesel generator trip). Discuss:
- Technical Specifications Requirement to Verify Other Diesel Operability
- Clear when Repaired b-g
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'('i l NOTES AND REFERENCES
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C. Initiate CCW-8 (seal' water heat exchanger) Discuss the possibility of cromates in the RCS clear when repaired. D. Dispatcher ask for load increase to 930 MWe over two hour perid. E. As load increases, initiate FWM-15 (FW control valve position failure). Suggesc failing valve position "as is" with manual control allowed. F. Initiate CRF-2 (auto rod speed failure) with speed failed to 72 steps per minute. G. Near end of session, initiate EPS-13 (generator breaker fails to trip) and then initiate PRS-3 (pressurizer spray valve failure). Evaluate operator actions with regard to spray valve sticking open and on reactor trip. Olscuss: Immediate actions of E0P-5 Possibility of reducing power to <38% and securing RCP. . III. CRITIQUE A. Review overall operations conduct. B. Review malfunction responses. O
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i SOUTH CAROLINA. ELECTRIC & GAS CCMpANY x PHASE III PP.03 RAM - PLANT CASUALTY TRAINING Power Operations, Malfer.ctions RCP Trip and Recovery, Accident Analysis Part 1 Overview . The American Nuclear Society has divided nuclear plant operations into four conditions. Up to this point in training the prospective operator has mainly ' concentrated on Condition I - Normal Operation and Operational Transients. It is becoming increasingly more important for an operator to experience opera-tion in the other three conditions. These conditions deal with faults of ("'} s increasing severity which have not been emphasi:ed curing the past operator traini,ng courses. Because of the importance placed upon an opera:or's ability to recogni:e and properly respond to fault conditions, this unit will stress the Condition II type faults and the desien analyses behind then. 'The prospective operator will experience Condition II faults of increasing severity, thus enhancing his ability to correctly handle the same category faults during actual operation. TerminalObjective ~ The student will be able to discuss typical Condition II faults including immediate operator actions required and follow the appropriate procedures to i perform subsecuent operator actions maintaining nuclear plant safety at all times.
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Enabline C'biectives l
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_d. .Upon co=pletion of this unit the student shall be able to: I)- discuss types of faults included in Condition II operation. 2)- identify Condition II faults from Main Control Board (MCE) annunciators and indications. 3)- demonstrate the use of Abnormal and Emergency Procedures in res::ense to Condition II faults. 4)- relate fault conditions to technical spec'ification limits. , References -
- 1. Virgil C. Summer 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
- 6. Abnormal Operating Procecures
- 7. STP 102.002 i
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INSTRUCTOR'S LESSON PLAN Page 1 I LESSON OUTLINE NOTES AND REFERENCES 2-INTRCDUCTION- ' 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: Commence plant unloading from 100 percent - to <50 percent power. Conduct the scheduled malfunctions. C. MALFUNCTIONS SCHEDULED:
- 1. CVC Boric acid flow transducer
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failure
- 2. PCS Steam generator level control failure
- 3. CRF Rods fail to move
- 4. NIS Power range detector failure -
- 5. MSS Steamline bre'ak outside the reactor building 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 O'JESTIONS AS THEY ARISE STATE BASIC PRESENTATICN FORMAT 18800:4 Rev 0 1/83
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[ INSTRUCTOR'S LESSON PLAN h LESSON OUTLINE NCTES AND REFERENCES-" REVIEW ~(Optional) . A. Review homework assignment
-B. Present an overview of simulator operations:
Plant unloading from 100 percent to
<50 percent Selected malfunctions C. Review E0P-10, misalignment of full length -
rods, with respect to a Condition II fault and analysis, i.e., RCCA misalignment. D. Review E0P-10 dropped rod Re-review Tech Specs 3/4.1.3 . E. Review Reactor Coolant Makeup Control System malfunction, with respect tn a I Condition II fault and analysis, i.e., uncontrolled boron dilut' ion. Review Tech Specs 3/4.1.2 F. Re review E0P-2, loss of secondary coolant - G. Review SOP-101, RCP Trip, with respect to a Condition II fault and analysis, i.e., ' partial loss of RCS flow and startup of inactive RCP. III PROCEDURE ( A. Initiali:e at (Later), perform a shift turnover, and explain plant conditions and objectives to students: System lineups Plant parameters . Operational status , Power history B. STPs-scheduled STP 102.002 NIS power range heat v , balance - 18800:.4 Rev 0 1/83 i
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' INSTRUCTOR'S LESSCN PLAN (A -
1 LESSON OUTLINE NOTES AND RE.:ERENCES C. Commence plant unloading towards 50 ' percent. C - Have students perform heat balance before commencing downpower STP. 102.002 D. Initiate CVC-1, boric acid flow transducer-fails high, discuss: Inability to borate, i.e., how ' extensive? Alternate means to borate Clear malfunction when problem is
, located and request for repair is made E. Initiate PCS-3, steam generator level control failure, discuss:
Manual control and load follow problems C Clear malfunctions upon request for repair F. Initiate CRF-1, rods fail to move, (manual control allowed) discuss: ' Means to control T,yg if no manual rod motion Tech Spec requirements Clear malfunction upon request for repair j G. Initiate NIS-7, power range detector failure, discuss: Effect on protection Purpose of various switch
. manipulations taking place at NIS panels -
Required bistable tripping f Clear malfunction upon request for -
- Jp repair IG800;.4 .
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' NOTES AND RE.:ERENCES H. Initiate MSS-12, main steam he~ader steam leak, discuss:
Identification difficulties
, Isolable versus non-isolable Means to minimize energy. release
,- Continue plant shutdown /cooldown to the end of the period!
I. Students conduct a shift turnover to instructor IV CRITIQUE A. Review overall operations conduct. B. Review malfunction responses b . 1 I 1 O .
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SCUTH CAROLINA ELECTRIC & GAS r PHASE III PROGRAM (] PLANT CASUALTY TRAINING Power Operations, Malfunctions Small RCS Leak
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Overview - In the nuclear power industry there have been several utilities that have experienced small amounu of leakage from the Reactor Coolant System (RCS). To prepare the operator to properly identify and isolate such a leak, the ' student will be exposed to several types of RCS leaks and will be required to identify and take proper corrective actions by following the Abnormal Operating Procedures for an RCS leak. Terminal Objective The student will be able to discuss and describe indications of RCS leakage l along with operator actions required to place the plant in a safe.and stable
- condition.
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O - 1 0891L:4 Rev 0 1/83
-Enab'ine Ob.iectives a.
h Upon completion of this unit,.the student shall be able to:
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1)- discuss the Reactor Coolant System Abnormal Oper'ating Procedure for reactor coolant leakage. "
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2)- describe indications of a small RCS leak. A 3)- recall RCS leakage technical specifications limits and their bases. References
- 1. Virgil C. Summer 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 "
- 6. Abnormal Operating Procedures
- 7. STP 114.002 f
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Page I r INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES INTRODUCTION A. UNIT TERMINAL OBJECTIVE: The student will be able to recognize, diagrase and respond correctly to various plant malfunctions. This ability will be
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, evaluated by instructor observation and the student's oral resporise to questions.
B. OPERATIONS PLAN: . Commence plant loading from 20 percent to
,100 percent power. Conduct the scheduled malfunctions.
C. MALFUNCTIONS SCHEDULED: *
- 1. PCS Failure of reactor trip switch
- 2. MSS Steam generator isolation I
valve closes O 3. CvC toss of char 24ne au=,
- 4. RCS RCP Trip
- 5. CRF Dropped full length rod '
- 6. RCS Leak
' 7. PCS Unstable steam generator level .
controller NOTE: In addition to the above listed malfunct' ions, any of the malfunctions ( s'cheduled on previous simulator sessions may also be used. STATE THE NEED TO ASK OUESTIONS AS THEY ARISE - STATE BASIC PRESENTATION FORMAT I I,. REVIEW (Optional)
- 6 A.
B. Review homework assignment. Re-review SOP-403, Dropped Rod (evaluate
- j student response) .
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Page 2 r - INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES
. C. Re-review SOP-102, loss of charging '
(evaluate student response) D. Review E0P-6,. emergency bor'ation Re-review Tech Specs 3/4.5 Stress when emergency boration is required E. Review E0P-12, Reactor Coolant System - i Excessive Coolant Leakage Review Tech Specs 3/4.4.6 III. PROCEDURE A. Initialize at (Later)'and perform a shift turnover and explain plant conditions and - objectives to students: System lineups I -- Plant parameters O - Ogeratiena, stets Power history B. STPs scheduled 1 STP 114.002 Operability Leak Test C. Commence plant loading towards 100 percent. D. Initiate PCS-8, failure of reactor trip ! switch E. Initiate CVC-17, loss of charging pump, i ( 'following a shift to a CCP, discuss: Tech specs associated with ECCS , CCW operating in both trains prior to ! start
- Seal injection Clear malfunction upon request for repair F. Initiate CRF-4,' dropped full length rod, discuss:
Causes and plant limitations-Related tech specs .
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INSTRUCTOR'S LESSON PLAN Page 3
- e n LESSON OUTLINE NOTES AND REFERENCES C-Urgent /nonurgent failures and alarm
( - reset Allow recovery of rod by procedure Ensure malfunction is cleared prior to , attempting rod recovery G. Initiate PCS-4, unstable steam generator level contro11 err' discuss Manual control and load change - relationships Elements of level control Clear malfunction upon request for repair - H. Initiate MSS-6, steam generator isolation valve closes, discuss:
/
Indications-Effect on plant operations at low versus high power levels, i.e., reason for plant trip i If plant trips, backup prior to malfunction and continue plant loading . If plant does not trip, clear malfunction, reopen the MSIV, and
. continue plant loading
( - I. Initiate RCS-3, RCP Trip, discuss: Effect on plant operations at low versus high power levels If plant does not trip, clear malfunction, restart pump, and continue plant loading J. Initialize at (Later) and explain plant conditions l .
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INSTRUCTOR'S LESSON PLAN Page 4
. r-LESSON OUTLINE NOTES AND REFERENCES System lineups -
-~ Plant parameters Operational status Power history K. Have students perform an Operational Leak Test STP 114.002 -
L. Initiate RCS-6, LOCA (small), ramp leak - rate up to allow leak rate' determination and location identification Determine proper procedure,'i.e. within CCP capabilities M. Students conduct shift turnover to - instructor IV. CRITIQUE I A. Review overall operations conduct. O'a aev4 =eir##c <o" resa="ses i I ( !O 0 91L:4 Rev 0 1/83
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T SOUTH CAROLINA ELECTRIC & GAS 'l 1 PHASE III PROGRAM PLANT CASUALTY TRAINING
, Power Operations, Malfunctions Small Steam Generator (S/G) Tube 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 con-tinuation 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 interrelations. A steam I generator (S/G) tube leak is one fault which will be identified by the association of several different indications. Although it may seem unrealistic to discuss a particular fault immediately prior to experiencing it, the discussion and application will complement one another such that the result will be a student familiar with a particular problem and the proper response such that he can properly react to the fault. Terminal Objective ( The' student will be able to discuss indications of steam generator tube leakage along with operator actions required to place the plant in a stable condition. 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. ' ( O .
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Enablin ' Objectives l l 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 operator actions in response to a steam generator tube leak. l 4)- demonstrate an ability to-perform actions as a control room operator
-during a steam generator tube leak.
References
- 1. Virgil C. Summer Training Simulator
- 2. SCE & G Phase II Training Material
- 3. SCE & G Phase III Training Material
- 4. WestinghousePhaseIIITrainihgMaterial -
- 5. Technical Specifications
- 6. Abnormal Operating Procedures Y 7. STP - 204.001 t
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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. -
- 8. OERATIONSplAN:
Commence plant loading towards 20 to 100 percent power. Conduct the scheduled malfunctions. C. MALFUNCTIONS SCHEDULED: *
- 1. TUR First stage pressure transmitter failure
- 2. CVC Boric acid flow transmitter O fatiure 3.' PRS Pressurizer level channel failure .
4. CVC RCP #1 seal leak
- 5. CVC Leak inside containment
- 6. RCS Steam generator tube leak (small)
NOTE: In addition to the above listed malfunctions, any of the malfunctions scheduled on previous simulator sessions may also be ured. STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT II. REVIEW (Optional) A. Review homework assignment 0896L:4 Rev 0 1/83
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> INSTRUCTOR'S LESSON PLAN dr' LESSON OUTLINE NOTES AND REFERENCES Review E0P-03, steam generator tube leak B.
Review tech specs C. Re-review Reactor Coolant. Makeup Control System malfunction (evaluate student response) ( D. Re-review SOP-101, reactor coolant pump - off normal procedure (evaluate student response) . E. Re-review E0P-12, reactor coolant system - excessive coolant leakage (evaluate . student response) III. PROCEDURE A. Initialize at (Later) and perform a shift turnover. Explain plant conditions and f objectives to students: System lineups . Plant parameters Operational status '- Power history B. STPs scheduled STP 204.001 Hot Channel Factor test i 4 C. Commence plant loading towards 100 percent Dl Initiate TUR-12, first stage pressure
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( ' transmitter failure, discuss:
.Ef.fect on all associated systems, i.e'.,
P-13, P-7, C-5, C-7, auto rod control l - Clear malfunction after proper bistables have tripped and , request for repair has been made E. Initiate CVC-1, Boric Acid Flow Transmitter Failure, discuss: Investigation as to cause
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Page 3 p- INSTRUCTOR'S LESSON PLAN - LESSON OUTLINE . NOTES AND REFERENCES' Limitations that this problem imposes clear malfunction upon request for repair F. Initiate PRS-2, pressurizer level channel failure, discuss: i Manual manipulations of pressurizer level in response to load changes bmitations imposed upon operator Allow for a period of manual operation, then clear malfunction upon request for repair G. Initiate CVC-4, RCP #1 seal leak, discuss:
- Use of indications to determine cause Orderly shutdown Upon determination of steps to be followed, terminate malfunction and backup to a point prior to the seal leak. Continue plant loading towards '
100 percent. H. Initiate'CVC-8, leak inside the reactor but1 ding (letdown line), discuss: Source of leak and possible isolation Significance of loss of letdown, i.e., ( - load follow, plant chemistry, etc. Terminate malfunction when proper action has been started. I. Re-initialize at (Later) explain plant con.ditions . System lineups Plant parameters Operational status ( - Power history O . 0896L:4 . Rev 0 1/83
ur Page 4 r INSTRUCTOR'S LESSON PLAN g LESSON OUTLINE NOTES AND REFERENCES J. Have students perform a Hot Channel Factor STP 204.001 Test
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K. Initiate RCS-2 steam generator tube leak, discuss:
- First indications versus determ:ning indications, i.e., radiation alarms in conjunction with flow' changes, and apparent difficulties Leak-rate determination Proper procedure (EOP-12)
Carry out malfunction as long as time allows : . L Students conduct shift turnover to instructor I CRITIQUE (m) A. Review overall operations conduct. B. Review malfunction responses f f p V 0896L:4 , g,y a ifg3 4
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, sis SOUTH CAROLINA ELECTRIC & GAS e .
O ea^sejr11jaoon's PLANT CASUALTY' TRAINING (
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' Power Operations,-Malfunctions Loss of Site Power and Recovery, Establish Natural Circulation Overview -
The casualty training prese ned in weeks one, two, an'd three has concentrated on minor malfunctions for which the ope'rator could usually take corrective action and continue plant operation. Although it is unlikely for a major
- accident to occur in a nuclear plant, the possibility does exist. Therefore, operators have to be knowledgeable of accident conditions, responses and f procedures in order to place the plant in as safe'and stable a condition as p
O possible without causing further damage or public hazard. A loss of site power requires the control room operator to verify 5 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 site 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.
I Successful completion of this unit will be based,on satisfactory evaluation by
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j the program instructor based on observation and the student's oral responses 1 to questions. 1 - i 0897L:4 Rev 0 1/83 I
Enablino Objectives l Upon completion of'this unit the student will be 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)
A 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. References I 1. Virgil C. Summer Training Simulator ECP-4, 50P-306, STP 102.003 0 2. 3. ses & c 88 se 11 Tr.4 4 e " ter4 1 SCE & G Phase III Training Material
- 4. Westinghouse Phase III Training Material '
- 5. Technical Specifications l~
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e INSTRUCTOR'S LESSON PLAN Page 1 LESSON OUTLINE NOTES AND REFERENCES INTRODUCTION A. UNIT TERMINAL OBJECTIVE: The student will be able to describe the symptoms and automatic actions during a loss of site power. The, student will also be able to perform and justify the immediate action required of a control room operator for a loss of site power and other plant malfunctions.' Successful completion of this unit will be based on satisfactory evaluation by the program instructor based on observation ind the student's oral responses to questions. B. OPERATIONS PLAN: I Initiate at 100 percent power equilibrium n U conditions and complete a shif t turnover. Initiate minor malfunctions as scheduled. Have the load dispatcher inform the ' control 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.
C. MALFUNCTIONS SCHEDULED:
- 1. NIS-3 Power range channel failure RN-21 HP feed heater bypass valve 2.
- 3. CRF-9 DRPI loss of voltage
- 4. SN-3 Emergency feedwater pump trip i
1
'5. PRS-4 PZR PORV failure
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- 6. RN-4 Feed flow transmitter failure i
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\- LESSON OUTLINE NOTES AND REFERENCES 1
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, 7. EPS-1 station blackout
- NOTE: In. addition to the above listed malfunctions, any of the l
, malfunctions scheduled on previous sessions may also be used.
STATE THE NEED TO ASK OVESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT - II. REVIEW (Optional) A. Review thermodynamics homework - B. Present a basic cverview of simulator operations. Power operation at 100 percent with O . mi#or m ir##ctio#s e#d stetioa blackout. C. Discuss emergency procedures for station ' blackout (EOP-4) Ask the students to list the symptoms, automatic actions, and immediate operator actions. Discuss the subsequent oparator ( ' actions to place the plant in a more s-table condition. D. Discuss the mechanism, indications, and plant conditions related to natural circulation flow. ' This review should include a discussion of plant design to promote f. natural circulation flow along with the various parameters which should be observed:
- o Pzi pressure
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.. = =7 INSTRUCTOR'S LESSON PLAN Page 3 r'
h LESSON OUTLINE - NOTES AND REFERENCES o Pzr level - o Wide range temperature recorders o In-core thermocouples o S/G pressure o S/G level Review the following technical E. specifications S/G safety valves emphasizing necessary actions if one or more valves are inoperable. . Re' view specification 3.0.4 Emergency Feedwater System Condensate storage tank F. Discuss the following emergency and system
# procedure Diesel Generator Procedures 50P 306 III. PROCEDURE A. Set up the plant in (LATER) and conduct a i shift turnover emphasizing the current conditions - steady stata 100 percent power;.no testing in progress.
Power history Systems status ( - Tests / evolutions in progress Equipment inoperability B. STPs scheduled STP 102.003 I.R. Analog Channel
. Operability Test j .
C. Initiate a power range channel failure (NIS-3), such that the channel fails to a minimum output. f Have the students explain how the channel signal is utilized in Rod , l . Control, SGWI.C and Rx Protection. l 0897L:4 Rev 0 1/83.
l :::= f INSTRUCTOR'S LESSON PLAN age 4 rs i) LESSON OUTLINE NOTES AND REFERENCES Review tech specs limitations for PR . channel failures Discuss differences in indication
, ,between a channel failure and a detector failure.
Trip the associated bistables and initiate epairs. D. Intiate a HP feed heater bypass valve - failure (FWM-21), due to a failed control switch. (bypass fails open) Review the Feedwater Heater System Discuss any reduced plant efficiency - and indications on the MCB. Review the concept of Rx Turbine power f mismatch. O e. Cieer the sP seeter me, function w8ee requested to reposition the valve locally. F. Initiate a RPI loss of voltage (CRF-9), ' due to failed power supply to Group B. Review RPI system to include non-urgent failure alarm, Data B failure, and General Warning lights. Discuss RPI system accuracy after a ( ' failure Review tech specs limitations ~ for continued operation When (If) requested to switch power supplies, clear the malfunction. O Otherwise continue plant operations with the failure as allowed by tech specs. 0897L:4 , Rev 0 1/83
2::= (- INSTRUCTOR'S LESSON PLAN Page 5 LESSON OUTLINE NOTES AND REFERENCES G. Initiate a PORV failure (PRS-4), such that the selected valve fails open~ without interlock to 100 percent position. Students should isolate the faulty valve; if not the plant will trip and SI will occur. Operator action will depend on - immediate actions Discuss tech specs limitations on ' continued operations. H. Continue plant operations at 100 percent power. - I. Initiate a feed flow transmitter failure (FWM-4). Fail the transmitter used for I SGWLC to a high flow value'. O - oper> #rs sh #1e t 'e =>"">> c #:r i of S/G 1evel or switch to an alternate feed channel. If not, a low-low S/G i level should result. Review the inputs to and operation of SGWLC. Review any tech specs limitations Trip the selected bistables and
- continue plant operations
! J. Initiate a emerg. feed pump trip (FWM-3) malfunction due to less of elect. power. K. Have students perform an I.R. range l channel test STP STP-102.003 , L. Initiate a Station Blackout (EPS-1), due . to inclement weather. l - When the loss of site power occurs, a l [ generator trip - turbine trip - Rx ! L) trip results. 0897L:4 Rev 0 1/83'
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Page 6 r INSTRUCTOR'S LESSON PLAN () LESSON OUTLINE NOTES AND REFERENCES Discuss blackout recovery ' actions Review vital loads which should start on a blackout. M. When (If) emerg. feed pump failure.is , noticed and local help is requested, clear ( . the malfunction to simulate reclosing the pump breaker locally. Review Emerg. Feed System drawing . N. Continue subscquent recovery actions from the blackout as time permits. Discuss and calculate a shutdown margin. * - Review tech specs for electrical power system.
/ Note to Instructors: The simulator O sess4en >8eeie de cone #ctee 4th as nv questions as possible being asked of the operators regarding plant systems, i procedures, tech specs, etc. The sessions should be representative of the final audit operational exam.
O. Students conduct shift turnover to
. instructor
( CRITIQUE A. Review overall operations conduct'. B. Review malfunction responses { 1 0897L:4 Rev 0 1/83
Review Questions f-2 ' 1. What automatic actions occur upon a loss of site power (blackout)? 4
- 2. List the immediate operator actions required for a loss of site power (blackout).
- 3. Describe the plant conditions that enhance natural circulati.on.
- 4. Describe indications of natural circulation being established.
- 5. What 1s the design bases for the capacity of the condensate storage tank?
J
- 6. Describe a method of cooldown if the Emergency Feedwater System was not available. .
- 7. Describe the operability requirements for the S/G safety valves in various modes.
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- 8. What signals will automatically start the emergency feedwater pumps?
9. Why does feedwater isolation occur on P-4 and low T,yg signals? l l l l f lO 7 0897L:4 Rev 0 1/83
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SOUTH CAROLINA ELECTRIC & GAS o-h PHASE III PROGRAM PLANT CASUALTY TRAINING Power Operations, Malfunctions Pressurizer Steam Space Leak, Accident Analysis Review Part 2 Overview - Since the occurrence of the Three Mile Island Incident, a significant amount of attention has been focused on pressurizer (PZR) steam space leaks. The control board indications of a steam space leak differ from those of a water piping leak and therefore warrant special consideration and training. This unit concentrates on the unique indications of this type of accident and allows the student to evaluate and respond to it. In addition, other Condition III type faults and their analyses will be discussed.
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Terminal Objective The student will be able to describe the symptoms and automatic actions during a pressurizer steam space leak. The student will be able to perform and
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justify the immediate operator actions required of a control room operator for l ( a small Reactor Coolant System (RCS) leak and other plant malfunctions. Successful completion of this unit will be b'ased on a satisfactory evaluation by the program instructor based'on observation and the student's oral responses to questions.
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Enabline Objectives . e 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 sniall loss of coolant accident. 3)- describe what is meant by Condition III faults. 4)- list the types of faults considered to be Condition III faults.
- 5) perform the subsequent operator actions while using the applicable procedure (s) for small loss of coolant accident.
References
- 1. Virgil C. Summer Training Simulator EOP-1, E0P-2, E0P-5, E0P-12, SOP-404, 50P-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 O
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W r O ( ' INSTRUCTOR'S GUIDE \ t f O i
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* :::::7 Page 1 l r INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES ~ '
INTRODUCTION A. UNIT TERMINAL 0BJECTIVE: The student will be able to describe the symptoms and automatic actions during a , pressurizer steam leak. The student will - also be able to perform and justify the immediate operator actions required of a - control room operator for a small RCS leak and other plant malfunctions. Successful completion of this unit will be based on satisfactory evaluation by the program instructor based on observation and the student'.s oral responses to questions. B. OPERATIONS PLAN: Initiate minor malfunctions as scheduled. O - Eventuai,x e pient ene Rx shutea n wiii be required due to a Pzr steam space leak. Continue with plant cooldown as time ' permits. C. MALFUNCTiONSSCHEDULED: , 1. CRF-7 Stuck rod
- 2. NIS-S Source range high voltage failure
( 3. 4. NIS-7 PRS-1 Power range detector failure Pzr pressure channel failure
- 5. MSS-5 Steam dump control failure
- 6. FWM-1 Main feedwater pump trip i 7. . MSS-7 S/G relief failure t 8. RCS-6 RCS leak NOTE: In addition to the above listed malfunctions, any of the malfunctions -
l_ scheduled on previous sessions may be used. J STATE THE NEED TO ASK OVESTIONS AS THEY ARISE c
. STATE BASIC PRESENTATION FORMAT 0900L:4 . Rev 0 1/83
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LESSON OUTLINE NOTES AND REFERENCES
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4 ( REVIEW (Optional) A. Review thermodynamics homework B. Present a basic overview ( - simulator operations. Power operations at 100 percent with minor malfunctions and a small RCS leak. C. Discuss emergency procedures for immediate action and diagnostics (EOP-1) and loss of primary reactor coolant (EOP-12) - Ask the students to list the symptoms, automatic actions, and immediate
/ operator actions for each emergency.
Discuss the subsequent operator (V3 . actions to place the plant in a more stable condition. D. Discuss Condition III - Infrequent Faults Review each Condition III fault emphasizing any applicable emergency or off-normal operator actions: o Minor steam system piping failure ( (EOP-2) o Complete loss of forced reactor coolant flow (EOP-4)' l o Rod cluster control assembly misalignment (50P-403) . 1 o Improper fuel loading and operation o Small break loss of coolant accidents (E0P-12). [ o Radioactive gas waste system leak U o Radioactive release due to liquid - tank failure 0900L:4 , Rev 0 1/83
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r INSTRUCTOR'S LESSON PLAN Page 3 LESSON OUTLINE NOTES AND REFERENCES
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o Spent fuel cask drop accidents E. For each event in item D above,' discuss any applicable tech specs sections: Movable Control Assemblies Group Height Design Features Section 5.3 Reactor Core Reactor Coolant System Leakage Section Refueling Operations Section Crane Travel-Spent Fuel Storage Pit Building. F. Review'the aspects of a Pressurizer steam space le'ak to include the following: Indications to the Operators
System Design
o Isolable PORVs I o RTDs for safety valve /PORV leakage O o ^coustic ieex mo.nitor Ability to maintain plant pressure and .- continue plant operations ' Effects on level indication of a level stand' pipe / condensing pot leak. Overall review of leak rate determina-tion and subsequent plant shutdown if tech specs limits are exceeded. i ( PROCEDURES A. Set up the plant in (Later) and conduct a j shift turnover emphasizing the current conditions - steady state 100 percent power; no testing in progress. Pcwer history ' Systems status i Tests / evolutions in progress I - Equipment inoperability ( . B. STPs scheduled STP-108.001 Quadrant Power Tilt Ratio 1 - 0900L:4 Re'v 0 1/83
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_ LESSON OUTLINE NOTES AND REFERENCES C. Initiate a stuck red malfunction due t . ( D. mechanical failure (CRF-7) in a shutdown bank. Initiate a source range high voltage failure (NIS-8). Select the source range channel chosen for the audio count' rate circuit. Failure of HV power supply. . NOTE: In the event of a reactor trip, - the stuck rod should initiate an immediate boration action from the operators if noticed and the source ' range failure will result in a loss of power indications once the source
.- ( range instruments reenergize (~ 15 i
minutes after the trip). E. Initiate a power range detector failure (NIS-7) such that the lower detector fails i to a high value. Student should take manual rod control to terminate rod insertion. Review Inst. Failure Response Manual Review Rod Control System inputs Perform followup actions of AOP-15 NIS Malfunction Review methods of monitoring power in the affected quadrant of the core. Trip the associated bi' stables and , i initiate repairs Discuss power range detector current compartor circuit Quadrant Power Tilt, f - F. Initiate a pressurizer pressure channel l' failure (PRS-1) such that the controlling
- l pressure channel fails high. .
(.0900L:4 Rev 0 1/83
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g INSTRUCTOR'S LESSON PLAN Page 5 LESSON OUTLINE NOTES AND REFERENCES NOTE: A pressure channel low failure vill result in a OTAT Rx Trip. If students trip bistables for this failure an inadvertent OTAT Rx Trip will result.
- Students should respond to take manual control of Pzr sprays and heaters to, stop the pressure decrease or select -
an alternate controlling channel. Discuss Pzr pressure control system /PORV interlocks Review Inst. Failure Response Manual 1 . for failed channel. Review tech specs limitations for pressure channel failures. NOTE: Operators cannot meet tech specs limitations for minimum operable channels unless in Surveillance Testing. Therefore plant shutdown is i required; if bistables are tripped with I hour, a plant trip will result. If a trip occurs, follow Rx Trip procedure and discuss stuck rod and NIS failure. Then reset to 100
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( G. percent power. Commence plant shutdown in accordance with normal procedures.
. H. Repair the NIS lower detector; complete
- functional testing, then stop the power ,
decrease. - Reset bistables for power range Trip selected bistables for failed 7 pressure transmitter. O- - Continue plant operations - increase power towardl100 percent slowly. 0900L:4 . Rev 0 1/83 I
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LESSON OUTLINE NOTES AND REFERENCES e Have student perform a Quadrant Power Tilt
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I. STP-108.001 Ratio J. Initiate a steam dump control failure (MSS-5) such that the cooldown valves (Group 1) ramp open. Failure is due to a failure of I/P converter for selected group of valves. Increased steam demand should cause . power increase Students should terminate system operation by taking manual control or turning the system off. - Discuss limitations on Rx power output, S/G swell, Pzr response to Con ue perations with the system off. Discuss effect on load rejection - capabilities with the steam dump system inoperable. K. Initiate a feedwater pwnp trip (FWM-1) due to a failure in the pump trip circuit. Stud'ents should perform immediate and subsequent actions of 50P-210 (loss of main feedwater) The Rx may trip from S/G low low level. If so, follow E0P-5; discuss stuck rod and SR failures. Reset at . , 1
.. previous power level and continue '
power increase. If no trip occurs, ensure operators return Steam Dump System to normal i O - after the transient, discuss Steam - Dump System operation.
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/ INSTRUCTOR'S LESSON PLAN Page 7 LESSON OUTLINE NOTES AND REFERENCES Investigate MFP trip; restart the pump and start restoring power to 100
( - percent. Review AI and RIL relative to Rod Control response to insert control (~ L. rods. Initiate a S/G relief valve failure with'out manual control. (MSS-7) Students should have the valve isolated locally Discuss tech specs limitations for relief valves and/or S/G safety valves. - M. Initiate a RCS leak (RCS-6). The leak size is variable. Recommend a value I < 40 gpm to start. Students should respond to decreased pressure and level and reactor building rad monitors Observe proper actions for E0P-12 loss of reactor coolant without S.I. Start additional charging pumps Monitor for leak location; calculate leak rate Review tech specs limitations N. Commence plant shutdown in accordance with normal procedures. l As shutdown continues, slowly increase the size of the leak to > 200 gpm. , Discuss methods of determining leak size and location.
- 0. Students should trip the Rx and proceed f
according to E0P-1 (Safety Injection Actuation). 1
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...s .( ) LESSON OUTLINE NOTES AND REFERENCES
'. P. Proceed with E0P-1 to stabiliz~e plant conditions as time allows. Q. If no previous Rx trip, discuss stuck rod and Source Range failures. Note to Instructors: The. simulator ( session should be conducted with as many questions as possible being asked of the operators regarding plant systems, procedures, tech specs, e.tc. The sessions should be representative of the final audit operational dxam. R. Students conduct shift turnover to instructor IV. CRITIQUE I A. Review overall operations conduct. , O 8. Rev4ew meifenction resacases ! / O . l 1 j 0900L:4 Rev 0 1/83 1
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i SOUTH CAROLINA ELECTRIC & GAS
,r y . 'U PSASE III PROGRAM MAJOR PLANT CASUALTY TRAINING-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 cons,idered 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 p IV accident which the plant is designe'd to protect. The plant's protection d 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 procedtres. This unit is designed to review the accidents in the Condition IV category and allow students to experience selected faults as control room operators. . Terminal Objective 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
- centrol 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 n student's oral response to questions.
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. Enabling Objectives r~
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Upon completion of this unit,'the student shall be able to: 1)- describe what is meant by Condition IV events.
.2)- list fault's included in the Condition IV category.
3)- describe indications of a feedline break inside' the reactor building.
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4)- discuss assumptions used in the feedwater break analysis. 5)- describe operator actions for a loss of secondary coolant. 6)- describe plant response to a steam line rupture. 7)- describe the major indication differences between steam and feed breaks inside the reactor building.
- 8) perform the subsequent operator actions while using the applicable procedures for a loss of secondary coolant.
References
- 1. Virgil C. Sur.mer Training Simulator
- 2. 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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INSTRUCTOR'S GUIDE . O 1 r (% { l l . L O 0901L:4 1
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r INSTRUCTOR'S LESSON PLAN
d LESSON OUTLINs NOTES ANO REFERENCES I. INTRODUCTION A. UNIT TERMINAL OBJECTIVE:
The student wil)1be'abla to describe the symptor:.s and automatic actions during a loss of. secondary coolant (inside the reactor building). The student will be C able to perform and justify the immediate operator actions required of a control room operator for a loss of secondary s coolant accident and other plant malfunc- - tions. Successful completion of this unit will be based on a satisfactory evaluadon by the program Inst'ructor based on obser-vation and the student's cral response to questions. U B. OPERATIO"5 P'Ld:
~ Initiate at 50 ' ercentp power during xenon transient anc 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 y emergency plans with students for each t ' , N_ major accident. l C. MALFUNCTICHS SCHECULED:
- 1. CRF-10 DRPI cpen or shorted coil '
f 2. PRS-6 Fat,1ure of PZR backup heaters -
- i 3. CVC-2 VCT divert valve control failure t
4 MSS-3 Steam treak inside contain.ent l
- 5. FaM-4 Feed.Jater flow transmitter failure -' -
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INSTRUCTOR'S LESSON FLAN Page 2 l u
<s' t LESSON OUTLINE - NOTES AND REFERENCES \,}
- 6. CRF-8 T ref failure
- 7. RCS-8 RTO failure (TH ~C0"t" I)
C 8. FWM-8 Feedline break inside containment
- 9. FWM-3 Emergency feed 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
'I. REVIEW (Optional)
() A. Review thermodynamics homework. B. Present a basic cverview of simulator operations. Increasing load from 50 percent curing a xenon transient with minor malfunctions and Loss of Secondary Coolant Accidents. C. Discuss Condition IV events Review each Condition IV fault s emphasizing any applicable emergency l for off-normal operator actions: o Major steam system piping 'ailure (EOP-2) ,
, o Feedwater system pipe break (EOP-2)
! o RCP shaft seizure (50P-101) i I 1 n 0901L:4
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- pj. , INSTRUCTOR'S LESSON PLAN - ~\" / . .
LESSON OUTLfNE , NOTES AND REFERENCES a, o' RCP shaft ~ break (S0P-101) 1
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, s o ~ Rod ejeption accidents '
o Steam' Generator Tube Failure (EOP-3) , s o 'Large Break Loss of, Coolant' l' ) ,
- Accident (E09-1) s
.o ' Refueling Emergency'(EOP-7)
Emphasizeihbabilitytodiagnose plant conditions /indicahons'and '
~ identify the various faults)
D. For each event in item 4 above, jiscuss 3, , any applicable Tech Specs sect'icns: -This review;-should enccmpass the. Tech Specs i secticns.for Rx-Protection Systems and ESF I y Instfumeqtation3/4.3.1and3/4.3.2c
. E. Review overall indications and plant response to the following:
Steam Break Inside the reactor building Feed Break-Inside the reactor building F. Review (E0?-1) for Accident Diagnostics and immediate. operator actions. G. Discuss Loss-of Secondary Coolant ' Procedure (EOP-2) . Ask the students to list the immediate
'( operator actions' for this emergency s.
precedure. l !i . Review steamline and feedline isolation
,, signals and.their bases. Review Tech -
t l specs 3/4.7.1. i . , Steamline Isolations I I o High 2 Containment Pressure o Lew steamline pressure l
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(") - LESSON OUTLINE NOTES AND REFERENCES o High Steam Pressure Rate - Decreasing Feedline Isolation 0 S/G High Level Override P-14 Feedwater Isolation o Rx Trip with Low T,yg signal o P-14 II
I. PROCEDURE
A. Set up plant in (Later) (50 percent power during xenon transient). B. Conduct a shift turnover emphasi:ing the current conditions 150 percent power during a xenon transient; no testing in progress. Power History System Status (} - Test / Evolutions in Progress Equipment Inoperability NOTE: The instructor may initiate with equipment inoperable as long rs applicable surveillance requirements are being met for continued plant operations. C. Initiate plant loading towara 100 percent power D. Initiate a URPI open or sorted coil l (CRF-10) in Data A. Discuss ORPI system alar: ' I o Nonurgent failure ss - o General warning Discuss system accuracy with failure Review Technical Specifications limitations for continued cperatiens O t; Section 3/4.1.3 090ll:4
a 22::7 Page 5 pm. INSTRUCTOR'S LESSON PLAN _
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LESSON OUTLINE NOTES AND REFERENCES Clear malfunction ~5 minutes after request for repair. { ' E. Initiate a failure of Pzr backup heaters
~(PRS-6).
Discuss Pzr pressure control system
. response.
Operators should 'take proper action to stabilize plant pressure Initiate repairs and continue operations F. Initiate a failure of VCT divert valve . such that valve fails to HUT. Students should take manual control of VCT divert valve. q k/ Alternative acticns are to isolate normal charging and letdown, reouce charging flow to minimum and establish excess letdown. Discuss CVCS flowpaths/ flow ~ balance / excess letdown system Discuss the ability'to dilute / borate in this condition G. Continue plant loading; initiate a
, steamline break inside the reactor
( 6 ( building (MSS-3) Recommend 6 x 10 lb/Hr over a 30 minute ramp. Observe operator actions; diagnos-ics Wnen students are in subsequent
- s actions of ECP-2 freeze the.conditicns and critique the evolution.
H. Reinitiali:e at 50 percent power or a backup SNAP >50 percent pcwer if desired O V to maintain previous plant conditions. 0901L:4
. 22::7 Page 6 INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES t;0TE:
Remove the steamline break if inserted with-time delay. C- I. Continue plant loading; initiate a feedwater flow transmitter failure (R.M-4) such that a feed valve fails closed in f- automatic. (Manual control is available). t . N - Prcper operator response should restore S/G 1evel in manual control. If 5/G level trip occurs, follow E0P-5 then reset in Backup and repeat the failure. Discuss indications of failure o Loop ai decrease o Steam flow increase due to increased steam pressure. (O
,,2 o T,yg increase - control rod insertion.
Review S/G swell and shrink. J. Continue plant operations in manual S/G control; initiate a failure low (CRF-5). Operators should respond to control rod insertion and switch to manual rod control Continue operations in manual rod k, Control K. Continue plant loading; initiate a RTD failure such that loop 3 T RTO fails H
, low (RCS-8).
Discuss indications of failure (T,yg, aT analysis) Discuss affects on Rod Control, P:r Level Control, RIL circuitry (aT)
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LESSON OUTLINE NOTES AND REFERENCES
-. Review Tech Specs operability requirements 2{
Trip selected bistables and initiate repairs L. Initiate an Emergency Feed Pump Failure (FWM-3) due to a feed breaker failure. (Motor Pump Fail.ure) This failure should be noticed during subsequent SI and corrective action taken to cross-connect the. motor driven ' pump headers or attempt to , start the pump locally. M. Continue plant loading; initiate a feedline break inside the reactor cuilding (FWM-3); break is dcunstrean of check eO valve inside the reacter building. Leak a rate of 6 x 10* lb/hr ar.d a ramp'of 20 minutes are recc : ended. ~ Observe operator actions; diagnostics When students are ir. subsequent actions of E0P-2, ciscuss overall operations Review Emergency Feed Pump operability
,- requirements (Tech Specs)
\ s. N. Continue subsequent ac: fens as time permits.
O. Students conduct shift turncver t
. instructor. -
Note to Instruct:rs: The si.ulator session shoulc be c rcuctec with as cany ' questions as possible baing asked of the o:erators regarding .plir.: systems,
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) INSTRUCTOR'S LESSON PLAN Page 8
-O " ores a~o asseasuces -
procedures, Tech S::ecs, etc. The sessions ( should be representative of the final audit operational' exam. IV. CRITIQUE . A. Review overall operations conduct. B. Review malfunctions responses. 1 lO i f 4 i . a Q 0901L:4
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- SOUTH CAROLINA ELECTRIC & GAS '
O (,,)- PHASE III PROGRAM MAJOR PLANT CASUALTY TRAINING Loss of Secondary Coolant Outside the Reactor Building Overview ~ Day 21 discussed, in detail, a loss of secondary coolant inside the reactor building. To fully develop this analysis the same basic accident occurring at
-different locations outside the reactor building must also be discussed. .
Several control room indications and operator actions will differ depending on the break location. This unit is designed to enhance-the prospective operator's ability to identify, locate, and respond to a loss of secondary coolant. Terminal Objective ' Upon completion of this unit, the student will be able to describe the symptoms and autcmatic action during a secondary steam break. 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 and other plan't 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.
O 0898L:4 ' Rev 0 1/83
-Enablino Objectives
, {,e) s Upon completion of this unit the student will be able to: 1)- describe indications for feedwater breaks in the following locations: immediately downstream of flok. transmitter immediately upstream of flow transmitter common feedwater header discharge of feedwater pump-2)- describe indication of a steam line break outside the reactor building. 3)- list the immediate actions required of the control room operators for
.* loss of secondary coolant accident. -
4)- diagnose feedwater and steamline break accidents as a control room operater. >
- 5) perform the required immediate and subsequent actions as a control room operator for a loss of secondary coolant. ,
References O 1. Virgil C. , Summer Training Simulator E0P-1, E0P-2, SOP-211
- 2. SCE & G Phase II Training Material
- 3. SCE & G Phase III Training Material ;
- 4. Westinghouse Phase III Training Material
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- 5. Technical Specifications 4
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l I I I INSTRUCTOR'S GUIDE 1 O . 'l l
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l INSTRUCTOR'S LESSON PLAN Page 1 P V LESSON OUTLINE NOTES AND REFERENCES I. INTRODUCTION - A. UNIT TERMINAL OBJECTIVE: The student will be able to describe the symptoms and automatic actions during a secondary system break. 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 and other plant malfunc-tions. Successful completion of this unit will be based on a satisfactory evaluation . by the program instructor based on obser-vation and the student's oral responses to questions. B. OpCRATIONS PLAN:
- Initiate at 15 percent load and complete a shift turnover. Initiate minor malfunc-
- tions as scheduled. Have the operators '
continue plant loading toward 100 percent. Major accidents will include a steam break and feed break outside containment. If additional time remains, other steam / feed r break drills can be initiated at the ** - discretien of the instructor. Discuss emergency plans for each major accident. C. MALFUNCTIONS SCHEDULED:
- 1. EPS-6 Diesel generator failure J. EPS-5 Loss of ESF bus .
- 3. FWM-9 H.P. feedwater heater tube leak
- 4. CRF-7 Stuck rod
- 5. NIS-4 IR gamma compensation -
- 6. FWM-4 Feed flow transmitter failure
/ ]) 7. PCS-3 S/G level control failure
- 8. PCS-6 Inadvertent phase A isolation
- 9. CCW-4 Loss of CCW to letdown H/X
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. .- 1 2:::- 1 INSTRUCTOR'S LESSON PLAN Page 2 .:m.
(,) - LESSON OUTLINE NOTES AND REFERENCES
- 10. CND-1 Loss of condenser ~ vacuum
- 11. CVC-8 Letdown line leak inside the reactor building, 12., MSS-4 Steam break outside the reactor building NOTE: In addition to the above listed malfunctions, any of the malfunction scheduled on previous simulator .
, sessions may also be used. STATE THE NEE 0 TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT . II. REVIEW (Optional) A. Review Day 22 thermacynamics homework B. Present a basic overview of Day 22 simulator operations. Increasing load from 15. percent with minor malfunctions and loss of secondary coolant accidents. C. Review Feedwater System Ccmponents Flow path 5/G level control Feed pump speed control 1 o Bases for programmed AP 1 Operation of system System procedures D. Discuss feed line break accidents at various locations:
- Have the students list the appropriate I indications to determine the following
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break locations. - o Between feed flow transmitter and
. . feed isolation valve 0898L:4 Rev 0 1/83
- = I INSTRUCTOR'S LESSON PLAN Page 3
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LESSON OUTLINE NOTES AND REFERENCES o Between-feed rag. valve and flow - transmitter o In the common feedwater line before branching to feed reg. valves o Between feed pump discharge and - feed discharge check valve. o In H.P. feedwater heaters E. Review Emergency Feedwater System Components Flow paths (Have a student draw the . system) Flow control - normal system lineup SCP-211 Sources of water System response to a feed line break F. Discuss indications for steamline breaks
, outside the reactor building. '
Compare or contrast these indications with those for a feedline break . outside the reactor building. G. Review the emergency procedure for a Loss of Secondary Coolant (EOP-2), and Accident Diagnostics (EOP-1). III. PROCEDURE A. Set up the plant in (Later) 15 percent load during a normal startup and conduct a ' shi.ft turnover emphasizing the current 1 conditions - 15 percent load during a normal plant startup, no testing in progress. - g - Power history Systems status Tests / evolutions in progress Equipment inoperability 0898L:4
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n:= INSTRUCTOR'S LESSON PLAN Page 4
.;-q -() LESSON OUTLINE NOTES AND REFERENCES NOTE: The instructor may initiate with equipment inoperable as long as applicable surveillance requirements.are being met-for continued plant operations. -
B. STPs scheduled STP 202.001 Target Axial Flux Difference Measureme~nt C. Continue plant loading toward 100 percent . power in accordance with normal procedures. D. Initiate a diesel generator failure (EPS-6) on DG A due to mechanical failure. . E. Initiate a ESF bus trip (EPS-5) on bus 10A due to a failure in the supply breakers mechanical latching mechanism. Discuss OG failure; students should
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attempt to restore power to the bus. Upon request, clear the OG malfunction to allow the bus to be restored to - power. Discuss reports; tech specs require-ments for loss of power supply to ESF Bus; OG failure. Clear ESF bus supply failure and restore affected equipment to normal status. F. Continue plant loading toward 100 percent; ! initiate an H.P. feedwater heater tube leas (FWM-9). . Select the maximum break size with minimum ramp time. Observe proper immediate actions / - diagnostics
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Start to restore plant conditions
- 0898L:4 Rev 0 1/83
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(> LESSON OUTLINE - ' NOTES AND REFERENCES
-G. Reinitialize at 50 percent load (Later) and continue plant loading toward 100 percent.
H. Have students perform a Target Axia1 Flux STP 202.001 Difference Measurement I. Initiate a stuck rod malfunction (CRF-7) due to mechanical failure. J. Initiate an intermediate range gamma compensation failure (NIS-4 on IR N35 with a + 10 -10 am s value. i These failures will be noticed only . during any subsequent plant trip. IR under compensation will result in a failure of the SR to reenergize. Operators should imm.ediately borate for the stuck red if the Rx trips. K. Continue plant loading; initiate a feedwater flow transmitter failure (FWM-4). Select the flow transmitter being used for SGWLC to fail low with minimum ramp time. Review SGWLC system operation. Operators should take manual control to stabilize conditions and select an alternate channel for control. Initiate repairs to the failed channel. L. Initiate a S/G level control failure (PCS-3) such that level input to the control system fails "as is". Affected S/G level will change during load change until an alternate level - Q channel is selected. ' Discuss level input to SGWLC system. Trip selected bistables; initiate 0898L:4 Rev 0 1/83
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- l INSTRUCTOR'S LESSON PLAN Page 6
-: s V LESSON OUTLINE NOTES AND REFERENCES M. Continue plant loading; initiste an inadvertent containment Phase A isolation signal in one train during.periedic SI sys, tem testing (PCS-6).
Once the operators have identified the problem, clear the malfunction and re' store systems to n'armal lineup: CVCS, blowdown, reactor building ventilation. Review containment Phase A signal generation and* systems affected.
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Review tech specs limitations. N. Initiate a simultan'eaus loss of CCW to Letdown HTX (CCW-4) and loss of condenser vacuum (CND-1). Loss of CCW failure should be in automatic control only. 4 Loss of condenser vacuum should be caused by a slow leak on the steam seal unicading valve. Recommend a 10 percent failure on the unloading valve. Operators should take manual control of CCW to the letdown HTX to restore temperatures to normal. Discuss effect of increased flow of CCW to the letdown H/X to other system components. Upon request or announcement for Local Action for loss of condenser vacuum, clear the malfunction. Allow vacuum to stabilize; discuss - (} vacuum pump and gland seal steam system operation. - 0898L:4 , Rev 0 1/83
- 4 INSTRUCTOR'S LESSON PLAN Page 7 LESSCN OUTLINE NOTES AND REFERENCES Discuss other possible causes for low vacuum; e.g. low C.W flow, high C.W.
temp, leaks on valves (vacuum breaker). O. Continue to increase load; initiata a small CVCS letdown leak inside the reactor
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building CVC-8. Recommend a small leak in . order to evaluate leak rate and diagnosis. ' Students may not identify the leak location, but should commence an orderly plant shutdown. Review tech specs leadage requirements and definitions. P. Commence shutdown; initiate a steamline break outside the reactor building; recommend a 30 minute ramp to 2 x
; (} 10 6
lbm/hr. 3 Observe diagnosis, manual SI if applicable. ' Once the plant is stabilized; main i steam lines are isolated and subsequent actions are being performed; affected S/G is boiled dry: o Discuss differences between feed break and steam break o Discuss core protection provided by ECCS. o Review the emergency procedures a...' the students overall performance. Q. Students conduct shift turnover to i instructor. - lO + l l OS98L:4 l Rev 0 1/8.3
2::= i INSTRUCTOR'S LESSON PLAN Page S LESSON OUTLINE NOTES AND REFERENCES Note to Instruc*. ors: The simulator session
- should be conduc ted with as many questions as possible being asked of the operators regard-ing pla,nt systems, procedures, tech specs,
, etc. The sessions should be representative of the final audit operational exam. IV. CRITIQUE A. Review overall operations conduct. .
- 8. Review malfunction responses
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[G . SOUTH CAROLINE ELECTRIC & GAS . (n) PHASE III. PROGRAM MAJOR PLANT CASUALTY TRAINING
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Loss of Coolant Accident - Inadequate Core Cooling i r Overview The next 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'R,eactor Coolant System (RCS) leaks have , been previously observed, the required actions for . 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 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 plant 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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1 0893L:4
,v Enablfr i Objectives
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Us_1 Upon completion of this unit, the student will be able to: l 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 Simulater E0P-1, SGP-115 N-- 2. SCE & G Phase II Training Material
- 3. SCE & G Phase III Training Material j 4. Westinghouse Phase III Training Material
! 5. Technical Specifications t E ( 2 0893L:4
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O . i i l l INSTRUCTOR'S GUIDE i a 4 O 4 i i l l t I j Q 08931.:4
22337 INSTRUCTOR'S LESSON PLAN Page 1 p)
'v LESSON OUTLINE NOTES AND REFERENCES -
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 satisfactory evaluation by the program instructor based on observation and the student's oral response to
- questions.
B. OPERATIONS PLAN: v Initiate at 100 percent power and complete a shift turnover. Initiate minor malfunctions 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. NIS-4 Int. Range Gamma Compensation
- 2. NIS-3 Power Range Channel Failure
/ 3. CND-2 Hotwell Level Transmitter Failure 4 RCS-5 Large LOCA (CEA)
- 5. FWM-3 Em. Feed Pump Trip
- 6. RCS-5 Large LOCA (03A)
- 7. RHR-1 RHR Pump Trip '
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,q , LESSON OUTLINE NOTES AND REFERENCES v
NOTE: In addition to the above listed malfunctions, any of the
~C malfunctions st .eduled on previous simulator sessions may also be used.
( STATE THE NEED TO ASK OUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT 4 II. REVIEW (Octional) A. Review . Thermodynamics Homework B. Present a basic overview of - simulator operations. Operations at 100 percent power with () minor plant malfunctions Large LOCA event carried out through recirculation moce (1.5 - 2 hours). As time permits, additional operations with malfunctions. C. Review ECCS Have the students draw the systems on the board for use in further discussion and critique the drawing. s - Review the following: o System flow paths for:
+ Injection mode f + Cold Leg recirculation mode .
's. + Hot leg recirculation mode o Flow rates at varying system pressures {
b) x_s. 0893L:4
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/m. LESSON OUTLINE C NOTES AND REFERENCES -
o Technical Specifications and Bases ( Section 3/4.5
+ Accumulators
+ ECCS Subsystems T,yg >177'C
+ ECCS Subsystems T,yg < 177'C
+ Boron Injection System C + RWST
- 0. Review Safety Injection Actuation (EOP-1)
Review Immediate Actions of E0P-1 . Outline on the board a general sequence of events involved,in , subsequent operator actions: o Precautions and Notes o Verify sump level indication o Regulate Emerg. Feed Flow i L o Isolate PORV's o Terminate SI (Precautions) .
+ RCS Pressure > 2000 psig
+ Pzr level > 50 percent of span
+ RCS subcooling > 50'F
+ Sufficient water level in at least one S/G.
o If SI terminated, plant recovery 1 follows with orderly plant cooldowr o For legitimate SI, proceed to cold leg recirculation
+ Notes, Precautions
( + Automatic Shiftover to cent. ' 4
' recirculation su p
+ Realignment of ECCS suction flow paths to RHR 0893L:4
22337 , I INSTRUCTOR'S LESSON PLAN Page 4
;q . LESSON OUTLINE NOTES AND REFERENCES U
o Initiation of reactor building spray recirculation o At 5 24 Hours, switchover to hot leg recirculation mode. NOTE: The instructor should review these procedures in detail using the C system drawing and asking questions about various steps in the procedure: e.g. Why shift to hot leg recirculation mode? E. Review RHR Loss of Flow Off-Normal Procedure 50P-115. F. Review Loss of Emergency Feedwater Off-Normal Procedure. G. Discuss the G-module review I O_z
$ self-evaluation. Handout copies for students to fill out and return to the instructor.
III. PRCCEDURE A. Set up the plant in (LATER) (100 percent power, Equilibrium Xenon). B. Conduct a shift turnover emphasizing the current conditions - 100 percent load, N- equilibrium Xenon, Power Range functional
; testing in progress by Instrument Maintenance personnel.
t
- Turbine Driven Emerg. Feed Pump 0.0.5 cue
'- to oil leaks.
' Power History Systems Status Tests / Evolutions in Progress Equipment Inaperability l
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~ , LESSON OUILINE ~ NOTES AND REFERENCES -
' L) ~ NOTE: The instructor may initiate with ( equipment inoperable as long as applicable surveillance
~
requirements are being met for continued plant operations. , C. Initiate an Int. Range gamma compensation C problem on channel N36 (NIS-4). Recommend ove compensation with a ' value of (-10 8amps) Students should observe the problem and check Tech Specs. Continued operation allowed; initiate repairs D. When repairs are requested, clear the malfunction and then t.ndereempensate the same channel with a +10 -10 am s value - for subsequent plant trip. E. hitiate a Power Range channel failure (NIS-3), such that channel N44 fails to 200 percent value due to a summing amp output failure. Observe student's response Discuss Instrument Failure Reference Manual (IFRM)
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Review Rod Control System inputs Trip selected bistables and consult Tech Specs for operational limitations 7 Review overpower rod >stop ckt.
- Discuss methods of monitoring quadrant power. s F. Continue c'pehations at 100 percent. power.
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1 INSTRUCTOR'S LESSON PLAN Page 6 ()
<s LESSON OUTLINE ' NOTES AND REFERENCES -
.G. Initiate a Hotwell Level' Transmitter Failure (CND-2), such that the level transmitter fails to O percent.
Upon manual action to control hotwell level, clear the malfunction. ( - Discuss the design and operation of the Hotwell Level Control System Discuss adverse effects of high or low hotwell level. H. Initiate a trip of emergency feed pump ( FWM-3 ) . I. Initiate a large LOCA (DSA) in Loop 1 (RCS-5). This evolution should take 1.5 - 2 hours. When requested to restore Emerg. O Feedwater, clear FWM-3. Carry out the immediate and subsequent - actions to the point of waiting for shiftover to het leg recirculation. Simulate time lapse of 24 hours and shift to hot leg recirculation mode. Discues procedures, notes, and precautions as you handle this ' accident. Discuss loss of all emergency feedwater system and alternate methods of feeding S/G's or previding cooling
/
s for the RCS. ' Use system drawings /CRT's for emphasis during system realignment.
*- Discuss undercompensated IR when SR i
-s fails to reset, !
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, ]lhi INSTRUCTOR'S LESSON PLAN Page 7 f~ LESSON OUTLINE NOTES AND REFERENCES i
.J. Reinitialize at 100 percent power; stabilize plant conditions instructor can backup.
K. Initiate a RHR Pump Trip (or fail to start) (RHR-1). L. Initiate a large LOCA (RCS-5). Operator should carry out immediate actions including ensuring Rx Trip. Discuss loss of RHR train affect on ECCS functional capabilities. Review ECCS criteria from 10CFR50. o peak clad temp. 2200'F o Max H2 generati n < 1 percent o Max clad oxidation < 17 percent o Coolable core geometry o Long term cooling M. Students conduct thift turnover to t instructor. Note to Instructors: The simulator session should be conducted with as many questions as possible being asked of the operators regarding plant systans, procedures, Tech Specs, etc. The sessions should be representative of the final audit operational exam. IV CRITICUE i A. Review overall operations conduct. ' 8 .~ Review malfunction responses with Attachemnt-I. O , 0393L:4
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SOUTH CAROLINA ELECTRIC & GAS
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(u e) PHASE III PROGRAM MAJOR PLANT CASUALTY TRAINING Steam Generator Tube Rupture , Overview During normal operations, several nuclear plants have experienced varying degrees of steam generator (S/G) tube failure up to an actual rupture. A tube rupture alone represents a serious problem, however the consequences of that rupture depend significantly upon actions performed by the operators. Because ' of the frequency of occurrence and importance of the operator actions, it becomes imperative for operators to, receive training in both discussion and implementation of tube rupture procedures and actions. This unit is designed () to provide the prospective operator with a thorough discussion of the procedures supplemented by operations during a steam generator tube rupture. Terminal Objectise - The student will be able to identify a steam generator tube rupture and describe the symptoms and automatic actions of this event. The student will f also be able to perform and justify the immediate operator actions required of
\ a control room operator for a S/G Tube Rupture 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. s-(s,* 1 0599L:4~
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o Enablino Objectives Upon completion of this unit, the student will be able to: 1)- list indications of a steam generator tube rupture. 2)- describe how an operator can identify and verify the affected S/G. 3)- describe operator actions required for a tube rupture.
- 4) explain the bases for each of the required operator actions.
5)- demonstrate an ability to perform the requirec immeciate actions as control room cperator during S/G tube rupture. ( 6) perform the subsequent operator actions while using the applicable procedures for a steam generator tube rupture. References
- 1. Virg'il C. Summer Training Simulator EGP-1, EOP-3
- 2. SCE & G Phase II Training Material
- 3. SCE & G Phase III Training Material
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,s , 4. Westinghouse Phase III Training Material
\ J' 5. Technical Specifications s 2 0899L:4
l l C L i I INSTRUCTOR'S GUIDE O i l s s Q OS99L:4 l
22227 Page 1 INSTRUCTOR'S LESSON PLAN
. LESSON OUTLINE N3TES AND REFERENCE.S I. INTRODUCTION A .. UNIT TERMINAL OBJECTIVE:
The student will be able to describe the symptoms and automatic actions during a S/G Tube Rupture. The student will also be able to perform and justify the ( immediate operator actions required of a control room operator for a S/G Tube Rupture and other plant malfunctions. Successful completion of this unit will be based on a satisfactory evaluation by the program instructor based nn observation
- and the student's oral response to questions.
B. OPERATIONS PLAN: /~') s Initiate at 50 percent power and complete a shift turnover. Initiate minor malfunctions as scheculed. The objective of this unit is to gain familiarity in handling S/G Tube Rupture events. The session will provid the opportunity to utilize emergency and subsequent actions for a S/G Tube Ruoture event. Discuss emergency plans for each major accident. C. MALFUNCTIONS SCHEDULED:
- 1. MSS-8 Stuck steam dump valve
- 2. CND-4 Circulation Water Pump trip j' _ 3. CVC-2 VCT Divert Valve control failure 0899L:4 Rev 0
- 7 Page 2 INSTRUCTOR'S LESSON PLAN A LESSON OUTLINE NOTES AND REFERENCES U
- 4. RCS-2: S/G Tube Rupture
- 5. PCS-5 Inadvertent SI actuation
- 6. FWM-1 Main Feed Pump Trip
- 7. CVC-4 RCP Number 1 Seal Failure
- 8. MSS-7 S/G Relief Valve Failure
- 9. RCS-2 S/G 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 OVESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT . - 4 Ov . REVIEW (Optionai) A. Review Thermodynamics Hemework B. Present a basic overview of simulator operations. Power cperations at 50 percent power . with minor malfunctions and S/G Tube Rupture. S/G Tube Ler.k and Diagnosis Plant Shutdown C. Discuss a S/G Tube Rupture Accident Possible causes o S/G Chemistry Control o Continuous Blowdown
-( o Condensate Demineralizers (Copper in seconcary systems) o Tube Denting, etc, Q
0899L:4 Rev 0
223S7 Page 3 INSTRUCTOR'S LESSON PLAN 7 LESSON OUTLINE NOTES AND REFERENCE.S -
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Plant response o LOCA o- Rx Trip and SI o Required operator actions to isolate the affected S/G o Minimizing a.irborne releases Condenser Off gas system
-( o Analysis o Tech Specs Bases for S/G Activity Sec. 3/4.7.1 o Tech Specs on S/G's and Bases Sec.
3/4.4.5 . o S/G Pressure / Temperature Limitations Sec. 3/4.7.2 Emergency Procedure (EOP-1) o Diagnostics (EOP-1) {'~ ) - RCS Leak from S/G Tube o E0P-03 D. Discuss the Inadvertent SI Abnormal Procedure III. PROCiDURE A. Set up the plant in (Later) (50 percent power, Equilibrium Xenon)
- 8. Conduct a shift turnover emphasizing the
[ current conditions - steady state N-equilibrium Xenon for 50 percent power, no testing in progress. Power History ( - Systems Status Tests / Evolutions in Progress Equipment Ineperability (if desired by instructor) O 0899L:4 Rev 0
22.'17 Page 4 INSTRUCTOR'S LESSON PLAN 7~ LESSON OUTLINE NOTES AND REFERENCES 'd NOTE: The instructor may initiate with equipment inoperable as long as applicable surveillance requirements are being met for continued plant operations. C. Commence load increase toward 100 percent; initiate a stuck steam dump valve (MSS-8) due to mechanical failure. Isolate valve (LOA) upon request. Discuss steam dump systems operation and indications. D. Continue load increase; initiate a Circulation Water Pump trip (CND-4) once . plant load is above 80 percent. Associated condenser shell pressure will increase. Discuss circ. water system requirements [) - Discuss staam cump valve failure when noticed. Initiate repairs on CW Pump breaker. E. Initiate a failure of VCT Divert valve ~ with full flow to RHUT (CVC-2) due to a failed I/P converter. Review VCT Level control system Review Scron Recycle System-capacity of RHUT Observe operator's awareness of excessive auto makeup system operation Initiate repairs; clear malfunction or i take manual control of system. F. Clear the Circ. Water Pump malfunction; continue load increase.
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22337 Page S INSTRUCTOR'S LESSON PLAN
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. LESSON OUTLINE NOTES AND REFERENCES G .- Initiate a S/G Tube Rupture (RCS-2);
recommend max leak rate with minimum ramp f time. g Observe proper operations in accordance with'EOP-1. Continue the transient until RCS f T,yg is below S07'C and RCS pressure.is below the S/G safety valve setpoints. Free:e and discuss the overall event. H. 'Reinitiali:e at 100 percent power with all malfunctions cleared. Conduct a shift - turnover of plant conditions. I. Initiate an inadvertent SI actuation (PCS-5), due to an accidental short
.{']) circuit in Train S.
Operators should respond to Rx. trip Discuss indication that an operator can utili:e to determine an inadvertent SI from a legitimate plant transient, o P:t Pressure o Reactor Building Parameters o S/G Parameters [s - Reset SI signal and stop affected equipment Discuss E0P-1 recovery from spurious Si J. Reinitiali:e at 100 percent power; ('~ initiate a MFP trip (FWM-1) due to a failure in the pump' trip circuit. Once plant conditions are stabilized, discuss what things can cause a MFP Qu. trip. 0899L:4 Rev 0
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22307 Page 6 INSTRUCTOR'S LESSON PLAN LESSON OUTLINE ( ) NOTES AND REFERENCES Discuss administrative recuirements for reports, etc. K. Repair the MFP (clear malfunction), and continue operation. L. Continue plant operation; initiate a RCP No. I seal failure (CVC-4). Recommend the ( max value. Isolate affected No. I seal Commence plant shutdown Discuss RCP seal construction and coeration, evaluation of seal performance. M. Initiate a S/G Tube Leak on A S/G (RCS-2). Shortly after the leak is noticed, initiate a failure of the S/G (3
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Relief valve on A S/G (MSS-7). Recommend a small leak rate (< 100 gpm to allow unit sh'utdown). Discuss release of activity througi, failed relief valve Follow E0P-03 as time permits. Discuss Radiological Problems and Actions N. Continue plant shutdown following E0?-03 as time allows. O. Students conduct shift turnover to instructor i N0:e to Instructors: The simulator session ' ( should be concucted with as many questions as possible being asked of the operators I regarding plant systems, procedures, Tech OS99L:4 Rev 0 t
~22333 e
INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES Specs', etc. The sessions should be representative of the final audit cperational exam. IV. CRITIQUE A. Review overall operations conduct B. Review malfunction responses-1 O i
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Review Ouestions J 1. What actions could be taken for a stuck open S/G relief valve, during a S/G tube break? Safety valve?
- 2. What advantage / disadvantage could be gained by stopping the Reactor Coolant Pump (RCP) in the loop with a S/G tube ructure?
- 3. Describe how the S/G is isolated following a tube break.
C 4 What is the basis for the rapid 50'F cooldown of Reactor Coolant System (RCS)?
- 5. Describe what actions the operator will perform to implement the Station Emergency Plan.
- 6. What limits are imposed on secondary system activity? Explain the bases for these limits. .
LJ 7. What is the maximum allowed S/G tube leakage permitted by Technical Specification?
- 8. What radiation monitors are used to detect S/G tube leakage?
- 9. Do any of the radiation monitors in question no. 8 above have autcmatic functions? Describe these functions.
- 10. What actions are necessary in order to sample S/G's following a S/G tube rupture assuming all radiation monitors function properly?
Explain. (
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SCUTH CAROLIf1A ELECTRIC & GAS
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LPHASE III PRC3 RAM - MAJOR PLN1T CASUALTY TRAlt It:G c Integrated Power Operations' , Overview During the South Carolina Electric & Gas Training Program for Phase III the student has been subjected to approximately 100 plant malfunctions and a wide assortment of discussion topics. At this point in the plant cperator's training, the operator should feel relatively competent and knowledgeat:le regarding plant routine operations and casualties. From this point on, specific scheduled malfunctions will not be discussed prior to the simulator operations period. This unit includes time for a review of any topic deemed necessary by the program instructor. Simulator operations with malfunctions selected by the program instructor will be administered based upon individual / class needs. Terminal Objective The student will be able to maintain nuclear plant safety during normal and
- casualty plant operation while fulfilling the duties and responsibilities of a control room operator. Satisfactory completion of this unit will be deter-mined by the instructor based on observation and the student's oral response to questions.
O 1 0894L:4 v- w - - - -,m- ,- * , p. .rs
Enabline Cbjectives 1-)\ - Upon completion of this unit, the student shall'be able to: ^
- 1) perform functions.as a control room operator during Nuclear Steam Supply System (NSSS) and secondary plant faults.
2)-' describe how any NSSS fault affects plant safety.
.3)- describe how any secondary plant fault affects plant safety.
4)- recall technical specifications related to NSSS and sec0ndary plant faults. 5)- recall operator actions for a plant fire. 6)- recall operator actions for control roem inaccessibility. Re fe~rence s
- 1. Virgil C. Summer Training Simulator *
- 2. .SCE & G Phase II Training Material
, 3. SCE & G. Phase III Training Material 4 Westinchause Phase III Training Material
) 5. Technical Specifications 4
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l l 1 1 1 INSTRllCTOR'S GUIDE O C ( l O 0394L:4
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g LESSCN OUTLINE NOTES AND F;EFERENCES t_ < > I. INTRODUCTION A. UNIT TERMINAL OBJECTIVE: The student will be able to maintain nuclear plant safety during normal and casualty plant operation while fulfilling the duties and responsibilities of a control room operator. Satisfactory completion of this
'{
unit will be determined by the instructor based on observation and the student's oral response to questions. B. OPERATICNS plan: Initialire at power and conduct a shift turnover - follow the schedulea malfunction scenarios. Conduct this session in the same canner as a final operational audit exam 7-ss with as many questions as possible to all k-~# the operators. Review Radiolooial Emergency Resconse and Imolementation Plans as acclicable. C. MALFUNCTIONS SCHECULED: NOTE: These scenarios can be run in any order. Additional malfunctions can be addad or conditions modified at the instructor's di cretion.
- 1. RCS-2 & CND S/G Tube Rupture with
[' Loss of Vacuum
- 2. CRF T Failure Lcw ref TUR Stator Water Ccoling Trouble f CVC Loss of Normal Letdown "
TUR-1 & ?CS In cvertent Turbine Trip with Failure of Manual Rx Trip Switch n L) 0894L:4 1
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Page 2 INSTRUCTOR'S LESSON PLAN LESSON OUTLINE _(-)
.em NOTES AND REFERENCES
- 3. RMS-2 & CCW Failed Rad Monitor in
.CCW with Letdown Hx Leak
[" TUR Turbine Vibration MSS Stuck Open Steam Cump Valve 4 RCS RCS Leak (Small LOCA) RMS Area Monitor Failure (Item No. 10) ( RMS-2 Process Radiation Monitor Failure (Item No. 13) STATE NEED TO ASK CUESTIONS AS THEY ARISE STATE BASIC PRESENTATION FORMAT II. REVIEW (Optional) A. Review Cay 25 Thermodynamics Homework f-' B. Present a basic overview of Day 25 simulator b> s operations C Medule self evaluation sheets Power Cperations with selected malfunctions and transients C. Discuss the E ergency Procedures for Control Room Inaccessibility and Fire
- Ask the students to list the immediate actions for control room inaccessibility
- Review the organization and procedure for
(' the Fire Emergency Procedure o Organization and Responsibilities o How to Report a Fire o Actions tn be Taken During a Fire -
.o Fire in a Radiatien Area b.~g 0894L:4
menw m Page 3 INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES 13 u D. Discuss the Fire Suppression Tech. Specs. Section 3/4.7.9 Fire Suppression Water System
-{ -
Spray and/or Sprinkler Systems
- Low Pressure CO Systems 2
High Pressure CO Systems 2 Halon Systems {-
-- Fire Hose Stations
- Penetration Fire Barriers II
I. PROCEDURE
Note to Instructors: The following combinations of events are intended to provide multiple failures for operator diagnosis and response. These events were intended to be performed at power (50 percent - 100 percent) with power being changed. System parameters U being outside their normal band may complicate the diagnostic process and therefore power changes are desirable. Otherwise initial conditions and sequence of events are at the discretion of the instructor. A. Set up the plant at power (Later) is recommended for peak Xenon burnout at 50 percent power.
/ B. Conduct a shif t turnover emphasizing the
( current conditions and the following: Power History Systems Status Tests / Evolutions in Progress ' Equipment In0perability
- Recommend that various equipment is made inoperable as appropriate.
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22237 Page 4 INSTRUCTOR'S LESSON PLAN LESSON OUTLINE NOTES AND REFERENCES 7-)3 C. Scenario #1 - S/G Tube Rupture with Loss of Vacuum At power (25-100 percent), initiate a S/G Tube Rupture in B S/G (RCS-2) of 3500 gpm with minimum rarnp time. Simultaneously initiate a loss of condenser vacuum (CND-1.) Observe operator response o E0P-0 immediate actions and diagnostics o Stop RCP's below 1500 psig if necessary; natural circulation o Proceed to E0P-1 Procedure o Stabilize RCS conditions o Attempt to determine faulty S/G f s o Step emergency feed ficw to faulty S/G o Stop RCP in affected loop o Cooldown using three atmospheric relief valves o Reset SI - step selected pumps o Restore pressurizer level l o When T,yg reaches 507'F reduce plant pressure o Reset Phase A Isolation o Equalize Primary and Secondary pressures Stop the evolution and conduct a short critique ~
- 0. Rotate cperaters; reinitialize at pcwer (Recommend (Later) 25 percent ocwer);
conduct a shift turnover. (3 G) 0894L:4
- 22337 Page 5 INSTRUCTOR'S LESSON PLAN n~ LESSCN OUTLINE NOTES AND REFERENCES
() . E. Scenario #2 - Minor malfunctions with Turbine Trip, Failure of Rx Trip Switch and l Loss of Condenser Vacuum { - Increase plant load toward 100 percent Initiate a T ref Failure (CRF-8) to 500'F o Operators should take manual rod. (~ control o Discuss followup course of action Initiate a Stator Water Cooling Trouble (TUR-7) event such that the temperature control valve fails to a full divert . position, o Observe Generator Panel Trouble-alarm on CEP o Stator water return anc supply bm temperature on CSP increase o Review System - when asked to take local action, clear the calfunction Initiate CVC-7, Loss of Normal Letdown o Observe operators reaction to loss of letdown flow o Valve failure is due to loss of' air (broken air line) { o Initiate repairs;' reduce charging; establish excess letdown o After some operating period, clear the calfunction to simulate repair completion. ' Initiate an Inadvertent Turoine Trip (TUR-1) after failing the Rx Trip Switch (PCS-8) 0894L:4
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, LESSON OUTLINE NOTES AND REFERENCES 1
L) . o Initiate a loss of condenser vacuum (CND-1) { o Operators should attempt to trip the Rx by any method
+ If they deenergf:e Rod Drive MG sets, rods will drop
-{ + If not, T avg I"C#'"8' "ill shutdown the Rx to low power and r operators should borate to complete the shutdown o Loss of vacuum will result in a loss of secondary heat sink to condenser o -Observe operation to atmospheric
-reliefs / safeties When plant conditions are stabilized, g stop the evolution and conduct short U critique F. Rotate operators; reinitiali:e ac 25 percent load (Later); conduct a shif t turnover.
G. Scenario #3 - Small RCS Leak, Rad Monitor Failures, Turbine Vibration (Trip) with stuck open steam dump valve. Increase plant load toward 100 percent Initiate Rad Monitor Failure in CCW (RMS-2) RCS activity will not cause any rad monitor alarms upon system leakage Initiate a Letdown Hx Leak (CCW-1) of 100 percent o Rad Monitor System monitoring the '
-s-letdown line will see the reduced activity and cause a rad conitor l
failed low alarm O l i OS94L:4 l 1
ma Page 7 lNSTRUCTOR'S LESSON PLAN m . LESSON CUTLINE 1 NOTES AND REFERENCES - %_ f. , o Camp Cooling Surge Tank level will I increase ! ; Initiate a Turbine Vibration problem l l (TUR-2) such that #2 bearing exceeds 12 mils in <5 minutes. Initiate a stuck open steam dump {- cooldown valve (MSS-8) to the 100 percent position. o When the turbine trip occurs, excessive cooldown should result, causing pressurizer pressure and level to decrease. . o Operators may respond to failure as , a LOCA rather than a cooldown - steam break type accident o Cbserve diagnosis and operator u response o If operator response is improper, ' stop the drill and critique tne plant conditions o If operators ' find the stuck valve and request isolation locally, terminate the drill, discuss plant conditions and critique the operators performance. H. Rotate operators; reinitialize at power (recommend 100 percent power, Later); cenduct a shift turnover. I. Scenario n5 - Small LCCA with Failed Rad - Monitor Systea L 0894L:4
22337 t' Page 8 INSTRUCTOR'S LESSON PLAN ' NOTES AND REFERENCES -
-r" LESSON OUTLINE r Initiate a Small LOCA (RCS-6) with Area Monitor Failure (RMS-3) Item No.10 and " Process Monitor Failure (RMS-2) Item No.
1 13 o Recommend a gradually increasing leak rate frem 10 gpm and a short ramp time to minimize duration ( o No rad monitor indication inside the reactor building; so could be a steam / feed leak except '
)
o T,yg remains essentially constant o Observe operater actions to diagnose , conditions as time permits . o Terminate drill before end of shift and critique
\q .J' J. Students concuct shift turno.ver to instructor i:ota to Instructors: The simulator session should be conducted with as many questions as possible being asked of the operators regarding plant systems, procedures, Tech Specs, etc. The sessions should be representative of the final audit operational exam.
IV. CRITIQUE A. Review overall operations conduct. B. Review malfunction responses ( C i O vs 0894L:4}}