ML20202E465
| ML20202E465 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/15/1997 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20202E456 | List: |
| References | |
| ROT-9-200-A, NUDOCS 9712080040 | |
| Download: ML20202E465 (26) | |
Text
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6' ATTACHMENT 1 ROT-9-200 INSTRUCTIONAL OUTLINE
()
C/
EXERCISE NUMBER ROT-9-200 - A REQUALIFICATION CYCLE 97 / 5 Year / Cycle DESCRIPTION:
PRACTICE / REVIEW 0F AP-520. E0P-03 AND E0P-08 i
REFERENCES:
AP-520. AP-770. E0P-02. E0P-03. E0P-08. E0P-13. & E0P-14 1.
BASIS FOR DEVELOPMENT:
A.
This lesson plan provides training on significant changes to E0P-03
" INADEQUATE SUBC00 LING MARGIN" and E0P-08 "LOCA C00LDOWN".
The lesson provides for practice in both procedures. Also included in the lesscn is training on a new procedure that provides guidance for small RCS leaks AP-520, 2.
SCENARIO OVERVIEW:
The crew will perform a structured review of AP-520 and the changes to E0P-03 and E0P-08, conducted in a class room environment by an instructor.
i After the structured review, the crew will exercise AP-520, E0P-03 And E0P-08 on the simulator.
The exercise will be run as a practice demo. The crews will practice or discuss the various steps in AP-520, E0P-03 and E0P-08 based e
(
on equipment availability and plant status, i
A.
With the simulator initialized to 100% power, a 25 gpm RCS leak starts on the discharge of the "A" RCP. Crew will enter AP-520. After the crew transfers RB cooling to SW the leak increases to 250 gpm. Crew should trip the reactor on leak > normal makeup and go to E0P-02.
Crew stays in E0P-02 until they reach step #3.28 and go to E0P-08. Crew will perform E0P-08 up to step 3.21 and one RCP has been shutdown.
The simulator is restored to IC #63. The simulator is at a point where the cooldown was continued until RCS temperature is = 272 *F. and 300 f.
MUP recircs to the RB sump are open. MUP-1C was shutdown to maintain MUT Level. RWP-38 and DCP-1B are still running. The PORV is selected to Low Range.
RCP-1A and RCP-18 are running. The crew has completed up to step #3.39 in E0P-08.
Crew will continue on in E0P-08 and place the "B" Decay Heat train into Decay Heat Removal Mode.
The following E0P-13 Rules and E0P-14 Enclosures are used:
e 2
PPO Post Event Actions, e
4 Letdown Recovery, e
17 Control Complex Emergency Ventilation.
e 15 E0P Temperature Log.
O 2
9712000o40 971203 DR ADOCK 050 32
l ATTACHMENT 1 ROT 9-200 INSTRUCTIONAL OUTLINE O
2.
SCENARIO OVFRVIEW: (cont.)
8.
The simulator is initialized to Mode 3 conditions, with Group 1 safety rods out, ready to commence a plant cooldown per ITS for damaged turbine blading'on EFP 2.
A 200 gpm RCS leak starts from the Pressurizer steam space.
The crew may enter AP-520 and determine the leak is greater than the capacity of normal makeup.
Crew should trip the reactor and perform E0P 02 immediate actions.
When SCM is lost the crew transitions to E0P-03 and perfarm Immediate Action:.. A Loss of Offsite Power occurs when HPI is actuated.
Crew Selectt EFP 1 Trip Defeats oer E0P 14 Enclosure c11.
Crew Starts the "B" tide CC Chiller per E0P-14 Enclosure #18.
Freeze the Simulator at EJP 03 Step # 3.26.
The following E0P 13 Rules and E0P 14 Enclosures are used:
e Rule 1 Loss of SCM.
Rule 2 HPI Control.
Rule 3 EFW Control, o
Rulo 4 PTS.
e Rule 5 EDG Control.
Enc. 2 PPO Post Event Actions.
Enc. 17 Control Complex Emergency Ventilation.
Enc. 11 EDG A Load Management.
Enc. 18 Control Complex Chiller Startup.
C.
The simulator is initialized to 100% power. a large Break LOCA occurs on "A" RCP discharge. When the reactor trips a Loss of Offsite Power occurs.
Crew should trip the reactor and perform E0P 02 immediate actions.
Crew transitions to E0P-03 and perform Immediate Actions.
When LPI flows are > 1400 gpm transition to E0P 08 per E0P 03 Step #
3.13.
When at E0P 08 step 3.6 go to step 3.33. When RB Sump is < 20 ft swap to the suctions to RB Sump. At E0P 08 Step # 3.97 crew is informed that SCM does not exist, so that the boron precipitation path is used.
The fcilowing E0P-13 Rules and E0P 14 Enclosures are used:
Rule 1 Loss of SCM.
e Rule 2 HPI Control, e
Rule 5 EDG control, o
Enc. 2 PPO Post Event Actions.
e Enc. 17 Control Complex Emergency Ventilation.
e Enc. 19 ECCS Suction Transfer, e
Enc. 18 Control Complex Chiller Startup.
O 3
ATTACHMENT 1 ROT-9 200 INSTRUCTIONAL OUTLINE i
2.
SCENARIO OVERVIEW: (cont.)
D.
The simulator is initialized to 100% full power, a LOCA on the "B2" HPI line occurs, when the reactor trips a loss of offsite power occurs along t
with a loss of "B" battery preventing the loadir.g of the "B" EDG.
Berm air compressors are lost at the same time as offsite power, r.rew enters E0P 02 for the immediate actions, transition to E0P 03 when SCM is lost and performs immediate actions. Crew transfers 99.1r to MUV-25 & 26.
Crew transfer ES HCC 3AB to the "A" ES 480v Bus and closes MUV-27 per E0P 03 Step # 3.5.
Crew directs bri flow per E0P 03 Step # 3.6.
EFP 2 is cross connected to supply the "A" EFW train and EFP 1 is placed into 4
Pull to Lock per E0P 14 Enclosure #7.
Freeze ihe Simulator at E0P 03 Step # 3.24.
The following E0P-13 Rules and E0P-14 Enclosures are used:
e Rule !
Loss of SCM.
e Rule 2 HPl Control, e
Rule 3 EFW Control.
e Rule 4 P15.
Rule 5 EDG Control.
Enc. 2 PPO Post Event Actions.
e Enc. 17 Control Coinplex Emargency Ventilation.
Enc. 11 EDG A Load Hanagement.
e Enc. 18 Control Complex Chiller Startup.
Instructor Note: tha actions in E0P-02 and E0P-08 are basically the same except that the crew would need to perform Enclosure 7 for EFP-2 Management.
Ci V
4 1
-...m._
j ATTACHMENT 1
]
ROT 9 200 INSTRUCT!0hAL OUTLINE I'
EXERCISE NUMBER ROT 9 200 A
i DESCRIPTION:
Instructor Simulator Trainina E0P Practice i
j 3.
SCENARIO OBJEUTIVES:
t A.
With the simulator initialized to 100% power. respond to a 50 gpm leak 1
from the "A" RCP 01scharge per AP 520.
!f leak size increases to greater than the capactty of normal makeep, the crew should respond by l
tripping the reacter and go to E0P 02.
r B.
With the simulator initialized to an iC that has the RCS at 270 'F.
and 212-# pressure and a leak within the capacity of one makeup pump.
j transfer one train of LPI to OHR mode of operation per E0P 08.
C.
With the simulator initialized to Mode 3 conditions, group 1 control-rods withdrawn and EFP 2 00S respond to a 200 gpm pressurizer steam space leak that causes a loss of adequate SCM per E0P 03 and E0P 08.
10, With the simulator initialized to 100% full power. all other equipment i
operating normally.
Respond to a 25% bre3k of RCP 1A discharge line with a Loss of Offsite Power per E0P 03 and E0P 08.
E.
With the simulator initialized to 100% full power. Respond to a 1200
{
gpm break on the "B2" HP! line with a loss of Offsite Power and a Loss of the "B" Battery per E0P 03 and E0P 08.
F.
During the simulator training perform the Control Room actions required by the following E0P 14
Enclosures:
e.
Enc. 11 EDG A Load Management.
o Enc. 17 Control Complex Emergency Ventilation, o
Enc. 18 Control Complex Chiller Startup.
e -
Enc. 19 ECCS Suction Transfer, e
Enc. 20 Hot leg injection Boron Precipitation.
4, PLANT MANIPULATION COVERED:
PM # 7,2 - Leaks In/Out RB 7.3 - Large/Small L. '
including Leakrate 7.4 - Saturated RCS 9
Loss / Degrade Power 10 Loss RC Flow / Nat Circ 25_ - Rx Trip Prepared By:
8((-
b
/
I F
Nucl r Operations Instructor /Date
~
Reviewed By:
Wi
@t 9IfI Nuclear Tr61ninJt Supervisor ' /Date 5
f ATTACHMENT 1 ROT 9-200 INSTRUCTIONAL OLTLINE O
5.
EXERC15E SETUI A. Initialize the simulator to 100% Full Power.
B. Unfreeze th'e simulator and perform the following initial condition modifications: None.
C. Tag out the following equipment: None.
6: PRE SESSION BRIEFING l
A. Assign students to shift positions as appropriate.
B. Have students sign attendance records.
C. Provide t'.udents with shift turnover information in Section 9.
O O
6
ATTACHNENT 1 ROT 9 200 INSTRUCTIONAL OUTLINE O
- 7. EXERCISE OUTLINE A. With the simulator initialized to 100'/. power, a 25 gpm RCS leak starts on the discharge of the "A" RCP.
Crew will enter AP 520. After the crew transfers RB cooling to SW the leak increases to 250 gpm.
Crew should trip the reactor on leak > normal makeup and go to E0P 02.
Crew stays in E0P 02 until they reach step #3.28 and go to E0P 08.
Crew will perform E0P 08 up to step 3.21 and one RCP has been shutdown.
This Scenario includes the following failures / events:
e 50 gpm RCS leak starts on the diccharge of the "A" RCP.
e 250 gpm RCS leak starts on the discharge of the "A" RCP.
- Transfer to Decay Heat Removal.
1)
Load IC for 100% Full Power MOL.
Load IC # 11.
2)
Load and Start Lesson Plan # 14. "** CYCLE 5 **
Load LP # 14 AP-520, E0P-03, & E0P-08 Training" from the "AP-520. E0P-03, &
MISC. directory.
E0P-08 Training".
3)
Give crew the initial Conditions, inform the, 100% FP N0L.
that we will be covering AP-520 and E0P-08.
Give Turnover Sheet.
4)
Insert Scenario "A" Event # 1, "AP-520, 25 gpm Trigger LP Step leak on RCP 1A Discharge".
- 1.
5)
Crew should enter AP 520, " LOSS OF RCS COOLANT AP-520.
OR PRESSURE".
6)
At Step # 3.3, crew will most likely say that Go To AP-520 Step pressure is not lowering and Go To Step # 3.11
- 3.11.
7)
At Step # 3.15, crew will commence a plant Commence Plant shutdown.
Shutdown.
8)
At Step # 3,18, crew should determine that the UE(<50 spa) leak is in the RB.
ALERT (>50 gps) 9)
At Step # 3.20, crew should Go To Step # 3.21.
Go To Step # 3.21.
10)
At step # 3.23, crew should close Letdown Cooler Inlet Valves.
11)
At step # 3.25, crew should isolate the RB Sump.
12)
At step # 3.26, crew should swap RB Cooling to Slow Speed and SW.
7
l ATTACHMENT ROT-9 200 INSTRUCTIONAL OUTLINE O
7.EXERCISEOUTLINE(Cont.)
13)
Insert Scenario "A" Event # 2, "AP 520, 25 gpm Trigger LP Step leak on RCP 1A Discharge".
- 2.
14)
Crew should determine that the size of the leak Trip Reactor, has increased.
They should carry out Step #
Concurrently l
3.13. Trip the Reactor, and Concurrently Perform Perform E0P-02.
E0P-02.
15)
Crew should perform Immediate Actions of E0P-02 and look for symptoms.
16)
At step # 3.8 crew should Minimize Letdown, Open MUV 24, Open MUV-73, Start MVP-lC and Open Additional HPI Valves.
17)
Crew should return Prersurizer Heater to Automatic when level is restored.
18)
At step # 3.23, crew should Restore Letdown per Recovery of E0P 14 Enclosure # 4.
NOTE: may not do this due Letdown E0P-14 to RCS leak rate.
Enc. # 4.
19)
At step # 3.29, crew should Go To E0P 08.
So To E0P-08.
20)
At step # 3.2, crew should Concurrently Perform Trigger LP Step E0P 14 Enclosure # 2.
- 7.
21)
At step # 3.12, crew should Isolate Waste Gas Header.
22)
At step # 3.15, crew should Initiate EFW.
23)
At step # 3.16, crew should Cencurrently Perform EFP-2 Management E0P-14 Enclosure 7, and start warmup of Aux E0P-14 Enc # 7.
Steam Line to EFP-2, 24)
At step # 3.17, crew should Establish Cooldown.
Establish Cooldown.
25)
At-step # 3.19, crew should Concurrently Perfsrm E0P Temperature E0P-14 Enclosure # 15.
Log E0P-14 Enc. #
15, 26)
At step # 3.22, crew should stop 1 RCP.
Shutdown One RCP.
O 8
m
ATTACHMENT 1 ROT-9-200 INSTRUCTIONAL OUTLINE O
- 7. EXERCISE OUTLINE (Cont.)
27)
At step # 3.25, crew should start RCS Start RCS Depressurization.
Depressurization.
28)
At step # 3.26, crew should go to Mode 3 Condensate Lineup.
29)
At step # 3.27, crew should Shutdown MFW.
Shutdown MFW.
Load GRA SEPT 22. Freeze and Re-Initialize the simulator to IC # 63.
Inform the crew that we have completed E0P-08 Step # 3.39.
All Steps between 3.27 and 3.39 have been completed, CDV-103 is Open, Adequate SDM Exists, CFV 5 &
6 have been Closed, P0RV is Selected to Low Range, and Only RCP-1A and 18 are Running. MUP-1C shutdown due to MUT level.
30)
Load IC # 63.
Load IC f 63.
31)
At step # 3.40, crew should Go To Step # 3.74.
Gio To Step # 3.74.
32)
At step # 3.78, crew should align air to "B" DC Trigger LP Step Valves.
- 13.
33)
At step # 3.84, crew should Shutdown Remaining RCPs.
34)
At step # 3.85, crew should Stop EFW and Close EFW and Close TBVs.
1.
35)
At step # 3.88, Freeze the Simulator.
Freeze the simulator.
9
ATTACHMENT 1 R0T-9 200 INSTRUCT 10NAL 00TlINE 7.EXERCISEOUTLINE(Cont.)
{
B. The simulator is initialized to Mode 3 conditions, with Group 1 safety rods out, ready to commence 4 plant cooldown per ITS for damaged turbine blading on EFP-2. 'A 200 gpm RCS leak starts from the Pressurizer steam space.
The crew may enter AP 520 and determine the leak is greater than the capacity of normal makeup.
Crew should trip the reactor and perform E0P 02 immediate actions. When SCM is lost the crew transitions to E0P-03 and perform Immediate Actions. A Loss of Offsite Power occurs when HPI is actuated. Crew Selects EFP 1 Trip Defeats per E0P-14 Enclosure #11. Crew Starts the "B" side CC Chiller per E0P-14 Enclosure #18.
Freeze the Simulator at E0P 03 Step # 3.26.
This $cenario Includes the following failures / events:
e 200 gpm RCS leak from pressurizer steam space.
- Loss of EFP-2 Solution Set.
- EDG "A" Load Management / Defeat of EFP-1 Trip.
1)
Load IC for Mode 3 with Group 1 Control Rods Load IC # 45. Red Withdrawn.
Tag A5V-5 ASV-204, MSV-55, &
MSV-56.
2)
Load and Start lesson Plan # 14, "** CYCLE 5 **
Load LP # 14 AP 520. E0P 03, & E0P-08 Training" from the "AP-520. E0P-03, &
MISC. directory.
E0P-08 Training" 3)
Give crew the Initial Conditions, inform the, Mode 3, that we will be covering E0P 03 and E0P-08.
Group 1 CR 9 100%,
Ready to C/D.for ITS on EFP-2 due to Damaged Turbine Blades.
4)
Insert Scenario "B", Event #1, "EOP-2 to E0P-3 Trigger LP Step #3 to E0P 8, 200 gpm Steam Space Leak".
5)
Crew should enter E0P-2, " Vital System Status Intermediate Range Verification", and perform the Immediate will be off scale Actions.
Iow.
6)
Upon completion of E0P-02 Immediate Actions the Enter E0P-03, crew should look for symptoms. SCM will go below the required value.
The crew should enter E0P-03.
O 10
~
ATTACHMENT 1 ROT-9-200 INSTRUCTIONAL OUTLINE b
- 7. EXERCISE OUTLINE (Cont.)
7)
At step # 2.1, crew should make sure that the 2 minute Time RCPs are tripped.
Perform Rule #1.
Critical Step.
Perform Rule # 1.
8)
At step # 3.2, crew should Concurrently Perform PP0 Post Event E0P 14 Enclosure # 2.
Actions E0P-14 Enc. 2. LP step #7 9)
At step # 3.7, crew should Close MVV-18.
20 minute Time Critical Step.
10)
At step # 3.8, crew should select ISCM setpoint.
20 minute Time Critical Step.
11)
At step # 3.11, crew should Concurrently Perform control Complex E0P-14 Enclosure # 17.
Emergency Ventilation E0P-14 Enc. # 17.
30 minute Time Critical Step.
12)
At step # 3.15, crew should Perform E0P-14 EDG A Load O'
Enclosure # 11.
iianagement E0P-14 Enc. # 11.
13)
At step # 3.16, crew should Concurrently Perform Control Complex E0P-14 Enclosure # 18.
Chiller Startup E0P-14 Enc. # 18.
14)
At step # 3.17, crew should Isolate Potential Leak Paths.
15)
At step # 3.25, crew should Go To E0P 02 Go To E0P-02.
16)
Freeze the Simulator.
Freeze the Simulator.
O 11
ATTACHMENT 1 ROT-9-200 INSTRUCTIONAL OUTLINE 10 7.EXERCISEOUTLINE(Cont.)
C. The simulator is initialized to 100% power, a Large Break LOCA occurs on l
"A" RCP discharge. When the reactor trips a Loss of Offsite Power occurs.
l Crew should trip the reactor and perform E0P 02 immediate actions. Crew transitions to E0P 03 and perform Immediate Actions. When LPI flows are >
1400 gpm transition to E0P-08 per E0P-03 Step # 3.13. When at E0P 08 step 3.6 go to step 3.88.
When RB Sump is < 20 ft. swap to the suctions to RB Sump.
l This scenario Includes the following failures / events:
large Break LOCA on discharge of the "A" RCP.
ECCS Suction Swar, to the Reactor Build Sump.
e 1)
Load IC for 100% Full Power HOL.
Load IC # 11 2)
Load and Start leston Plan # 14. "** CYCLE 5 **
Load LP # 14 AP-520. E0P 03, & E0P-08 Training" from the "AP-520. E0P-03, &
HISC. directory.
E0P-08 Training" 3)
Give crew the Initial Conditions, inform the, 100% FP N0L.
I that we will be covering E0P 03 and E0P 08.
Give Turnover Sheet.
i 4)
Insert Scenario "C", Event #1, "EOP E0P-8, Trigger LP Step #4 LBLOCA, LOOP, DHV-12 Fails, Baron Precipitation".
f.)
Crew should enter E0P-2, " Vital System Status Verification" and perfonn immediate Actions.
6)
Upon completion of E0P-02 Immediate Actions the Enter E0P-03.
crew should look for symptoms.
The crew should enter E0P-03.
7)
At step # 2.1, crew should make sure that the 2 minute Time RCPs are tripped and perform rule #1.
Critical Step.
Perform Rule # 1, 8)
At step # 3.2, crew should Concurrently Perform PP0 Post Event E0P-14 Enclosure # 2.
Actions E0P-14 Enc. 2.
Trigger LP Step
- 7.
O V
12
. -. - - - _. -. ~
ATTACHMENT 1 ROT-9 200 INSTRUCTIONAL OUTLINE O
7.EXERCISEOUTLINE(Cont.)
9)
At step # 3.7, crew snould Close MUV 18.
20 minute Time Critical Step.
1
\\
10)
At step # 3.8, crew should select ISCM setpoint.
20 minute Time Critical-Step.
11)
At step # 3.10, crew must consider RB Pressur-when calculating SCM.
l 12)
At step # 3.11, crew should Concurrently Perform Control Complex E0P-14 Enclosure # 17.
Emergency Ventilation E0P-14 Enc. # 17.
30 minute Time Critical Step.
12)
At step # 3.13, crew should Go To Step E0f ;3 Go To E0P-08.
13)
At step # 3.6, crew should Go To Step # 3.90.
Go To Step # 3.89.
Whenever BW5T Level < 20 feet, transfer ECCS Suction to the RB Sump per E0P-14 Enclosure # 19.
14)
At step # 3.91, crew should Close CFV-5 & 6.
15)
At step # 3.92, crew should Concurrently Perform Control Complex E0P-14 Enclosure # 18.
Chiller Startup E0P-14 Enc. # 18.
16)
At step # 3.93, when ECCS Suetions are on the RB Sump, crew should Control LPI at 2000 gom.
17)
At step # 3.96, crew should Notify PPO to Tread RB Hydro 9en RB Hydrogen / Concurrently Perform E0P-14 Management E0P-14 Enclosure # 21.
Enc. # 21.
16)
Freeze the Simulator.
Freeze the Simulator.
O.
V 13
j ATTACHMENT 1 ROT-g-200 INSTRUCTIONAL OUTLINE i O
- 7. EXERCI5E DUTLINE (Cont.)
- 0. The simulatur is initialized to 100% full power. a LOCA on the "B2" HPI line occurs, when the reactor trips a loss of offsite power occurs along with a loss' of "B" battery preventing the loading of the "B" EDG.
Berm air
~
compressors are lost at the same time as offsite
)ower.
_',tw enters E0P 02 for the immediate actions, transition-to E0P_03 w1en SCM is lost and:
performs immediate actions. Crew transfers power to MUV-25 & 26. Crew transfer ES MCC 3AB to the "A" ES 480v Bus and closes MUV-27 per E0P 03 Step # 3.5.
Crew directs HPI flow per E0P 03 Stap # 3.6.
EFP-2 is cross connected to supply the "A" EFW train and EFP-1 is placed into Pull to Lock per E0P-14 Enclosure #7.
Freeze the Simulator at E0P 03 Step # 3.24.
This scenario Includes the following failures / events:
e Small Break LOCA on "B2" HPI line.
e loss-of "B" Battery / LOBB Solution Set.
e Transfer of ES MCC 3AB power.
e loss of Berm Air Compressors.
o EFP 2 Crosstie to "A" EFW Train.
1)
Load IC for 100% Full Power MOL.
Load 10 # 11 2)
Load and Start lesson Plan # 14 "** CYCLE 5 **
Load LP_# 14 AP 520, E0P-03, & E0P-08 Training" from the "AP-520. E0P-03, &
\\
MISC. directory and trigger setup step.
E0P-08 Training" 3)
Give crew the Initial Conditions, inform the, 100% FP N0L.
that we will be covering E0P-03 and E0P-08.
Give Turnover Sheet.
'4)
Insert Scenario "D", Event #1, "SBLOCA, LOOP,
-Trigger LP Step #5 and Loss of "B" Battery".
5)
Crew should enter E0P 2, " Vital System Status Verification" and perform Immediate Actions.
6)
Upon completion of E0P 02 Immediate Actions the Enter E0P-03.
crew should look for symptoms.
The crew shculd enter E0P-03.
7)
At step # 2.1, ciaw should make sure that the 2 afw te T(se Tu s are tripped and perform rule #1.
Critical Step.
Perform Rule # 1.
O 14
.. i'
l..
ATTACHMENT 1 l
ROT-9-200 INSTRUCTIONAL OUTLINE l
- 7. EXERCISE OUTLINE (Cont.)
]
l 8)
At step # 3.2, crew should Concurrently Perform PPO Post Event E0P-14 Enclosure # 2.
Actions E0P-14 Enc. 2.
l Trigger LP Step
- 7.
9)
At step # 3.3, crew should swap power supply for 10 minute Time MUV-25 & 26.
Critical-Step.
l Crew will not be able to complete step # 3.4 due to Loss of "B" ES power.
10)
At step # 3.5, crew should swap power supply ES MCC 3AB.
11)
At step # 3.6, crew should identify the leaking 20 minute Time HPI Line and Isolate it.
Critical Step.
12)
At step # 3.7, crew should Close MUV-18, 20 minute Time Critical Step.
13)
At step # 3.8, crew should select ISCM setpoint.
20 minute Time Critical Step.
14)
At ste # 3.9, crew should swap power to the "B" Trigger LP Step side ES Status Lights,
- 10.
15)
At step # 3.11, crew should Concurrently Perform Control Complex E0P 14 Enclosure # 17.
Emergency Ventilation E0P-14 Enc. # 17.
30 minute Time Critical Step.
Whenever BWST Level < 20 feet, trantfor ECCS Suction to the R8 Sump per E0P-14 Enclosure # 19.
16)
At step # 3.15, crew should Concurrently Perform EDG A Load E0P-14 Enclosure # 11.
Management E0P-14 Enc. # 11.
17)
At step # 3.16, crew should Concurrently Perform Control Complex E0P-14 Enclosure # 18.
Chiller Startup E0P-14 Enc. # 18.
18)
At step # 3.23, Freeze the Simulator.
Freeze the Simulator.
15
ATTACHMENT 1 ROT-9-200 INSTRUCTIONAL OUTLINE O
- 8. POST EXERCISE REVIEW 1
A. Review of Session
- 1) Review t'he sequence of events and facilitate a critique of the training session.
B. Documentation
- 1. Document Plant Manipulations (PM's) performed during this session on (Facsimile of Form 203.7), Simulator Control Manipulation Record.
Each PM performed should be listed by PM number and name (SEE TDP-203, Appendix B for Plant Manipulation listing). Include a brief description of the scenario used during the session in the " Scenario Description" section of Attachment 2.
- 2. Review the class attendance record for completeness.
- 3. Route Attachment 2, Plant Manipulation Record, and the Class Attendance Record to Training Specialist for processing.
O oV i
16
- 9. SHIFT TURN 0VER for SCENARIO "A" L
A. The following are the initial plant conditions:
- 1) Time in core life - 300 EFPD
- 2) Rx power arid power history - 100% for last 30 days.
- 3) Boron concentration - 1096 PPMB.
- 4) Xenon Equilibrium.
- 5) RCS Activity - See status board.
j B. Tech. Spec. action requirement (s) in effect: None.
C. Clearances in effect: None.
D. Significant problems / abnormalities: None.
E. Evolutions / maintenance for the on-coming shift: None.
F. Units 1 and 2 status: On line.
G.' Units 4 and 5 status: On line.
H. SS00 - Instruct the R0s to walk down the main control board and provide you with the following data:
O
- 1. RCS Average Temperature 4.
Make up Tank Level
- 2. RCS Pressure 5.
Turbine load
- 3. Pressurizer Level 6.
Turbine Reference
- 1. Required Emergency Plan Implementation Full implementation, including all required notifications.
Initial / upgrade Classifications Internal Notifications.
- None,
- XXX]
J. The STA should start this exercise B the Control Room.
K. The CNO should start this exercise H the Control Room.
L. The SS00 should start this exercise B the Control Room.
O 17
(.
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- 9. SHIFT TURNOVER for SCENARIO "B" A. The following are the initial plant conditions:
- 1) Time in core life - 300 EFPD i
- 2) Rx power arid power history - 0% for 1 Hour.
l 3 Boron concentration - 1096 PPMB.
4 Xenon --Increasing.
5 RCS Activity - See status board.
B. Tech. Spec. action requirement (s) in effect: ITS ??? for EFP 2 00S.
C. Clearances in effect: EFP-2 (ASV-5, ASV 204, MSV 55 & MSV 56).
D. Significant problems / abnormalities: During the normal SP, EFP-2 turbine self destructed. No one injured.
The plant is preparing to start a cooldown to go to Mode 5.
E. Evolutions / maintenance for the on coming shift: Commence cooldown to Mode 5.
F. Units 1 and 2 status: On !ine.
}
G. Units 4 and 5 status: On line.
H. SS00 - Instruct the R0s to walk down the main control board and provide you O
with the following data:
- 1. RCS Average Temperature 4.
Make-up Tank Level
- 2. RCS Pressure 5.
Turbine Load
- 3. Pressurizer level 6.
Turbine Reference I Required Emergency Plan Implementation
- Full Implementation, including all reqaired notifications.
Initial / upgrade Classifications Internal Notifications.
J,XXX) None.
J. The STA should start this exercise B the Control Room.
K. The CN0 should start this exercise B the Control Room.
L. The SSOD should start this exercise M the Control Room.
O 18
- 9. SHIFT TURNOVER for SCENARIO 'C' A. The following are the initial plant conditions:
1 Time in core life - 300 EFPD 2 Rx power arid power history 100% for last 30 days.
3 Boron concentration - 1096 PPMB.
4 Xenon - Equilibrium.
5 RCS Activity - See status board.
B. Tech. Spec. action requirement (s) in effect: None.
C. Clearances in effect: None.
D. Significant problems / abnormalities: None.
E. Evolutions / maintenance for the on coming shift: None.
F. Units 1 and 2 status: On line.
G. Units 4 and 5 status: On line.
H. S500 Instruct the R0s to walk down the main control board and provide you with the following data:
(\\ -
- 1. RCS Average Temperature 4.
Make up Tank Level
- 2. RCS Pressure 5.
Turbine Load
- 3. Pressurizer Level 6.
Turbine Reference I. Required Emergency Plan implementation Full Implementation, including all required notifications.
- Initial / upgrade Classifications Internal Notifications.
- XXX
None.
J. The STA should start this exercise B the Control Room.
K. The CNO should start this exercise B the Control Room.
L. The SS00 should start this exercise H the Control Room.
. ('~~h x) 19
4 o
- 9. SHIFT TURN 0VER for SCENARIO "D" A. The following. - the initial plant conditions:
1 Time in core life - 300 EFPD 2 Rx power and power history 100% for last 30 days.
3 Boron concentration - 1096 PPMB.
4 Xenon --Equilibrium.
5 RCS Activity - See status board.
B. Tech. Spec. action requirement (s) in effect: None.
C. Clearances in effect: None.
D. Significant problems / abnormalities: None.
4 E. Evolutions / maintenance for the on-coming shift: None.
F. Units 1 and 2 status: On line.
G. Units 4 and 5 status: On line.
H. 5500 - Instruct the R0s to walk down the main control board and provide you with the following data:
O
- 1. RCS Average Temperature 4.
Make up Tank Level
- 2. RCS Pressure 5.
Turbine Load
- 3. Pressurizer Level 6.
Turbine Reference
- 1. Required Emergency Plan Implementation
[ Full Implementation, including all required notifications.
Initial / upgrade Classifications Internal Notifications.
- XXX
None.
J. The STA should start this exercise B the Control Room.
K. The CN0 should start this exercise H the Control Room.
L. The SS00 should start this exercise B the Control Room.
O 20
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 i
DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 ATTACIIMENT E AI-402C, AP and EOP Verificati<.i and Validation Plan 1
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