ML12166A086
| ML12166A086 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/14/2012 |
| From: | Division of Reactor Safety II |
| To: | Florida Power & Light Co |
| References | |
| 50-250/11-302, 50-251/11-302 | |
| Download: ML12166A086 (167) | |
Text
ILC-27 NRC Scenario #1 Event Description Facility:
Turkey Point Scenario:
1 Op Test:
2011-302 Examiners:
Candidates:
US ATC BOP Initial Conditions:
Mode 1 75% rower at MDL.
Equipment OOS: Breaker 3AB18 for 3B2 Circ water pump is racked out due to breaker failure. Shift Turnover:
Manager has received notification that conditions for a Grass Influx are favorable and has performed a Grass Influx evaluation.
3-GOP-i 00 Contingency Brief for Loss of a CWP Holding at 75% power.
Online Risk Green with B Train protected on both units.
Event Mat Event Type Event Description I ATC LT-3-460 fails low which isolates letdown. The crew responds using the 1
TFHITV6O ARP and 3-ONOP-49.1 to remove LT-3-460 from service. The SRO will (ITS) SRO address LCO 3.3.1. The crew restores normal letdown and PZR heaters following LT-3-460 failure using 3-ONOP-041.6.
V8CI29ON (C) BOP Circ Water Pump 3B1 Motor Bearing high temperature from increased 2
bearing friction. The crew will lower reactor power to < 60% & secure TVKKB1 (C) SRO SJAE suction before securing the 3B1 CW pump using 3-NOP-OiO.
(N) BOP 3
N/A (R) ATC The crew initiates a boration and reduces Turbine load to 60% using 3-GOP-i 00.
(R) SRO PT-3-445 fails high, the crew responds using the ARP and 3-ONOP-4i.5 TFH1TU45 (I) ATC to attempt to manually close PORV-456. During the instrument failure, 4
PORV-456 develops leakage. The contingent action will be to close the TVHV456 (l,TS) SRO block valve to stop the leakage. The SRO will address LCO 3.4.4 due to excessive leakage on the PORV.
B Condensate Pump Motor Shaft slowly seizes causing a failure of the TVFABP6B (C) BOP pump. The automatic start of the C Condensate Pump is blocked. The 5
BOP can manually start the C Condensate Pump or stop one Main Feed TFF1D6CM (C) SRO Pump to initiate a Runback to equalize Turbine load with available Feedwater flow.
TVHV456 During plant stabilization, Block Valve MOV-3-535 develops leakage with 6
(M) ALL PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions TVHV535 to 3-EOP-E-i. RCPs are tripped with the loss of Subcooling Margin.
TAFK339 AFW flow to the 3C S/G is blocked. Also, B TDAFWP mechanically trips 7
TFFXCGVC (C) BOP and the C TDAFWP Governor Valve Fails closed. During the performance (C) SRO of 3-EOP-E-0, the crew uses A TDAFWP to establish greater than 345 TCF5MTB gpm total to the 3A and 3B S/G.
8 TFQ6A4AF (C) BOP The 3C ECC fails to Auto Start, the BOP manually starts the 3C ECC (C) SRO during Attachment 3 of 3-EOP-E-0.
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor 1
ILC-27 NRC Scenario #1 Event Description SIMULATOR SETUP INSTRUCTIONS 1.
Reset to 10-16 (100% BOL) or other IC with correct setup conditions.
2.
Place Simulator in RUN 3.
Open and Execute ILC27SCN1N.lsn.
4.
Place 3B2 CWP Handswitch to stop.
5.
Trigger lesson step:
SETUP
- 3B2 CIRC WATER PUMP OOS insert TAK4DP RACKOUT delay=0 ramp=0 on=0 off0 6.
Once the pump is stopped and discharge valve is closed, place a clearance tag on 3B2 CWP Handswitch.
7.
Store IC with initial conditions setup if desired.
8.
Trigger lesson step:
SETUP
- 3C ECC FAIL TO AUTO START insert TFQ6A4AF true delay=0 ramp=0 on=0 off=0 9.
Place Simulator in freeze.
- 10. Provide Shift Turnover Checklists
- 11. Perform Simulator Operator Checklist
- 12. When ready to begin, place Simulator in RUN.
2
ILC-27 NRC Scenario #1 Event Description FACILITY OPERATOR INSTRUCTIONS EVENT I LT-3-460 fails low which isolates letdown. The crew responds using the ARP and 3-ONOP-49. 1 to remove LT-3-460 from service. The SRO will address LCO 3.3.1. The crew restores normal letdown and PZR heaters following LT-3-460 failure using 3-ONOP-041.6.
When directed, Trigger EVENT I
- LT-3-460 FAILS LOW.
insert TFH1TV6O TRUE delay=0 ramp=0 on=0 off0 SM
- If directed, respond and acknowledge the failure of LT-3-460.
- If directed, respond and acknowledge the failure of LT-3-460 and to write a PWO for troubleshooting.
EVENT 2 Circ Water Pump 3B1 Motor Bearing high temperature from increased bearing friction. The crew will lower reactor power to <60% & secure SJAE suction before securing the 3B1 OW pump using 3-NOP-Ol 0.
When directed, Trigger EVENT 2
- 381 CW PUMP HIGH TEMP.
insert V8CI29ON TRUE delay=0 ramp=0 on=0 off=0 insert TVKKBI 0.5 delay=0 ramp=4800 on=0 off=0 SM
- If directed, respond and acknowledge the failure of Circ Water Pump 3B1.
- If directed, respond and acknowledge the failure of Circ Water Pump 3B1 and to write a PWO for troubleshooting.
When directed, Trigger EVENT 2
- CLOSE 3-30-003 AND 3-30-005.
insert TAFBOO3 0.0 delay60 ramp=0 on=0 off=0 o
insert TAFBOO5 0.0 delay=120 ramp0 on=0 off=0 When directed, Trigger EVENT 2
- SECURE PRIMING JETS AND VENT WTRBX VACUUM TKS.
insert TAKKV66 0.000000 delay=0 ramp=0 on=0 off=0 insert TAKKV81 0.000000 delay=60 ramp=0 on=0 off=0 insert TAKKV78 1.000000 delay=180 ramp=0 on=0 off=0 insert TAKKV63 1.000000 delay=120 ramp=0 onO off=0 When directed, Trigger EVENT 2
- RACKOUT 3B1 CW PUMP.
insert TAK4CP RACKOUT delay=0 ramp0 on=0 off0 3
ILC-27 NRC Scenario #1 Event Description EVENT 3 The crew initiates a boration and reduces Turbine load to 60% using 3-GOP-i 00.
- If directed, acknowledge power reduction.
- If directed, acknowledge power reduction for the removal of 3Bi CWP.
SYSTEM DISPATCH
- If directed, acknowledge power reduction to 60% for the removal of 3B1 CwP.
ENGINEERING
- If directed, acknowledge power reduction to 60% for the removal of 3B1 CWP.
CHEMISTRY
- If directed, acknowledge power reduction to 60% for the removal of 3B1 CWP and to sample the RCS for the power change.
EVENT 4 PT-3-445 fails high, the crew responds using the ARP and 3-ONOP-41.5 to attempt to manually close PORV-456. During the instrument failure, PORV-456 develops leakage. The contingent action will be to close the block valve to stop the leakage. The SRO will address LCO 3.4.4 due to excessive leakage on the PORV.
When directed, Trigger EVENT 4 - PT-3-445 FAILS HIGH
- PORV 456 DEVELOPING LEAKAGE.
insert TFH1TU45 -i delay=0 ramp=0 on=0 off=0 insert TVHV456 0.1 delay0 ramp=0 on=0 off=0 SM
- If directed, respond and acknowledge the failure of PT-3-445.
- If directed, respond and acknowledge the failure of PT-3-445 and to write a PWO for troubleshooting.
EVENT 5 B Condensate Pump Motor Shaft slowly seizes causing a failure of the pump. The automatic start of the C Condensate Pump is blocked. The BOP can manually start the C Condensate Pump or stop one Main Feed Pump to initiate a Runback to equalize Turbine load with available Feedwater flow.
When directed, Trigger EVENT 5
- LOSS OF 3B CONDENSATE PUMP.
insert TVFABP6B 1.000000 delay=0 ramp=300 on=0 off=0 insert TFF1 D6CM TRUE delay=0 ramp=0 on=0 off=0 insert TFF1 D6CM FALSE cd=imfl p6cs delay=0 ramp=0 on=0 off=0 SM
- If directed, respond and acknowledge the failure of the 3B CONDENSATE PUMP.
- If directed, respond and acknowledge the failure of the 3B CONDENSATE PUMP and to write a PWO for troubleshooting.
4
ILC-27 NRC Scenario #1 Event Description EVENT 6 During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCP5 are tripped with the loss of Subcooling Margin.
When directed, Trigger EVENT 6
- PORV 456 AND BLOCK VALVE 535 LEAKAGE INCREASES insert TVHV456 1.000000 delay=0 ramp=60 on=0 off=0 insert TVHV535 1.000000 delay=0 ramp=60 on=0 off=0 SM
- If directed, respond and acknowledge the failure of Block Valve MOV-3-535 develops leaking with PORV 456 leakage.
- If directed, respond and acknowledge the failure of Block Valve MOV-3-535 developing leakage with PORV 456 leakage and to write a PWO for troubleshooting.
When directed, Trigger EVENT 6
- EVENT 6
- ALIGN PAHMS FOR SERVICE.
insert TAC2VO2A 1.000000 delayt0 ramp=0 on=0 off=0 insert TAC2VO2B 1.000000 delay=0 ramp=0 on=0 off=0 insert TAAAV21 1.000000 delayo ramp=0 on=0 off=0 insert TAAAV22 1.000000 delay=0 ramp=0 on=0 off0 insert TACAOO5.000000 delay0 ramp=0 on=0 off=0 EVENT 7 AFW flow to the 3C SIG is blocked. Also, B TDAFWP mechanically trips and the C TDAFWP Governor Valve Fails closed. During the performance of 3-EOP-E-0, the crew uses A TDAFWP to establish greater than 345 gpm total to the 3A and 3B SIG.
Auto Trigger EVENT 7
- AFW MALFUNCTIONS insert TAFK339 0.0 delay=0 ramp=0 on=0 off=0 insert TFFXCGVC true delay=60 ramp=0 on=0 off=0 insert TCF5MTB true delay=60 ramp=0 on0 off=0 EVENT 8 The 3C ECC fails to Auto Start, the BOP manually starts the 3C ECC during Attachment 3 of 3-EOP-E-0.
5
ILC-27 NRC Scenario #1 Event Description SCENARIO QUANTITATIVE ATTRIBUTES Target Quantitative Attributes (Per Scenario; See Section D.5.d)
- 1. Total malfunctions (58) 5 2.
Malfunctions after EDP entry (12) 3
- 3. Abnormal events (24) 4 4.
Major transients (12) 1 5.
EOP5 entered/requiring substantive actions (12) 1 6.
EOP contingencies requiring substantive actions (02) 0 7.
Critical tasks (23) 3 CRITICAL TASKS 1.
Establish minimum AFW flow of 345 gpm prior to transitioning out of 3-EOP-E-O. [EVENT 7]
OR If crew transitions to 3-EOP-FR-H1 to correct loss of AFW, then establish minimum AFW flow of 345 gpm prior to completing Step 2 of 3-EOP-FR-H1.
2.
Trip RCPs due to a loss of subcooling during a SBLOCA prior to completing step I of 3-EOP-E-I.
3.
With RHR Flow less than 1000 gpm, stop the RHR Pumps within 44 minutes of their start signal.
6
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010-302 Scenario No.:
I Event No.: I Page 1
of 5 Event
Description:
LT-3-460 fails low which isolates letdown. The crew responds using the ARP, 3-ONOP-041.6 and 3-ONOP-49. 1 to remove LT-3-460 from service. The SRO will address LCO 3.3.1.
Time Position ApplicanVs Actions or Behavior Direct Facility Operator to trigger lesson step, EVENT I
- LT-3-460 FAILS LOW.
(insert TFH1TV6O TRUE delay=O ramp=O on=O off=O)
Observes failure of LT-3-460.
AIarmsA8I4,A914, &B311 SRO!ATC LI-3-460 fails low Letdown isolates (LCV-3-460 & CV-3-200s all close)
PZR heaters de-energize CAUSES:
1 PZR Level control malfunction A814
- 2. LOCExcessive RCS leakage
- 3. Steam Break
- 4. RCS Refueling operations in mid-loop SROIATC LO-LO LEVEL ALERT ALARM CONFIRMATION 1.
CHECK the following less than or equal to 6% at VPA:
SROIATC Ll-3-459A Ll-3-460 Ll-3-461 OPERATOR ACTIONS 1.
IF either of the following exist:
e Two or more level instruments are less than or equal to 12%
Two or more bistablesare ON SROIATC THEN:
A. TRIP the reactor.
B.
INITIATE a Safety Injection.
C. ENTER 3-EOP-E-0, Reactor Trip Or Safety Injection.
1
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2010-302 Scenario No.:
1 Event No.: I Page 2 of 5 Event
Description:
LT-3-460 fails low which isolates letdown. The crew responds using the ARP, 3-ONOP-041.6 and 3-ONOP-49. 1 to remove LT-3-460 from service. The SRO will address LCO 3.3.1.
Time Position Applicants Actions or Behavior CAUSES:
- 1. 5CR cabinet fan(s) have tripped B3
- 2. SCR cabinet door is open
- 3. Failed air flow switch or door contact switch in SCR cabinet PZR SROIATC HEATER CONTROLLER FAN OFF ALARM CONFIRMATION S ROIATC 1.
CHECK RCS pressure.
OPERATOR ACTIONS 1.
ENSURE PZR Control Group Heaters trip.
2.
CONTROL pressure by manually cycling backup heater group per S ROIATC 3-OP-04 1.2, Pressurizer operation.
3.
DISPATCH operator to check:
Door on SCR cabinet CLOSED e
All SCR cabinet fans oreratinci NOTE If called, the operator reports:
FACILITY OPERATOR
- 1) The SCR cabinet door is CLOSED.
- 2) All SCR cabinet fans are operating.
CAUSES:
- 1. RCSIeakILOcA
- 2. Steam line leak/break
- 3. PZR level control malfunction
- 4. Instrument failure PZR SROIATC LOLEVEL/
HEATER OFFI LTDN SECURED ALARM CONFIRMATION 1.
CHECK LCV-3-460. HIGH PRESSURE L/D ISOL VALVE FROM LOOP B COLD LEG, CLOSED on VPA.
SROIATC 2.
CHECK the following CLOSED on VPA:
a CV-3-200A, 45 GPM L/D ISOLATION VALVE a
CV-3-200B, 60 GPM L/D ISOLATION VALVE a
CV-3-200C, 60 GPM L/D ISOLATION VALVE 3.
CHECK Control and Backup heaters OFF.
2
Ui Cu o
4-4-
_J U)
(I) o U)
Wi c
w o
x w
C,)
Hi O
1-Q o
2 Hiz I
Qw_
2 Cl Li..
Lii jE U
C w
Co U)
(C)
-art (t
()
- E
>0 (f)
.! E C.) cL o
n 1<
(13 (I)Q c1 Q
Cl) w E
0 U
U, 0
4-,0 1...0 4-Cu L..a) 0 V
a)I C) x
-o a)
C0 C-)
ci)>
ci)
-J U)NI 0
Co a
Oc0 ZO 915 0) z 0
- cJjU, Co 04-s C
i5z U)
.=
(3 010 U) 00 U)
.E c U)Ct3 U) 4-U) 0 DCo C) 00 coC!)
0) 1 a).
-c C
o z
t3 4-C:
ci) o _j U)
_c 00 0
EE z
.2 o
4-Q4..
C o
U)
=0) 0 Cl) a-(00 (N
cQ o
ii
((C)
Hc c
Ho cc o
0 Co C%J 0
0-z 09 U)
F-cZ.
cs..
Qc o
UJC)c)
I
>O(O><
I I
°° C
0-C00 E0 0
I C)ØC)
I I
I
><9cJ
I L0U) 0
)ECu
-.J E
I -!J I
0U
,(,)
C
.C0(0Cu q)..
- 0 I
C Cu I
-C a
0
,q I
0(13 U)
I I
I I
0)
><*u:
iI OQ i:ijc 00 01 I
I zi C
I I
I I
- C)$
I
,()
I I
I I
I
.c E
I o3 I
s 18(C I
I
-C 4-,
a U)
-J H-;:
0
().
z (Th r
U)
I PL Co CLj
.-cTh.
-J z
ci) fl-)
&C I
U)
N!
LU C)
IC)
C-)
&DH Co 11)
-I
LU (I)
(-
u...
4-7
.1
<(N U) zc (00,_
Ci)
CjD.c Q_
ii; 0
ci C
4-Co
-C ci) 4-0 0C0 0
Co 4-,C Co0 0
HU II cuo Cc-)
C)
U)
RID C
(U LUci 0
C-)
LU
-J LU>
LU
-J 0:::
UI N
D C,)
Cl)LU.
0-CC LLJO
-J 0)
Wc Cl) E
-J.2 LUPj ZC 4(C I
t 0 4-.
00 U)U) 4-COG)
Cj5
((C)
C)
Ci C)
(,
(,
C)
Cj 0
0 0
0 0
0 0
c1 C
O Ci::
O Cl)
U)
Cl)
U)
U)
U) a)
E 1
S S
J
.)
Li
Li-C Li
.C C
H
4
C V,
,V C
Li.
Li Li
C VC C
3)
C-.
CV J-
-)
z z C
C H
C-.
-.e-.
0 0-.
-t:
.(-.
fl
.r fl I
in i,,
in i
i c1 Q
U)w 0
U C) 0
-I-,0 0
00 0*
a) 0::
x Ca)0 aJO cCC) a)Cl)
U)
C rj
- 5 U)
LI) 4-0
-DCo 3_
00 coO) 0)
Cu
_C 0
ci)
C o
i U)t o _j U)
_C o
EE z
.2 o
0*-i (3
C)
=0)
C-)
U)j Ci) 4-0coO (i
cQ Hc d
CC o
oCu C\\J o
- J z
U)C 1;;
a)
F-CZ Qc o
Wcc C-.
V C
U, z
VN DI)
I)
I) 1)
)1-Cu CU, Ii in dID 0
4 LI) cli)
C-)0 U) a)
C, U)0 0C U) a)0 a)
U) 0,
C 00 ci)
-J U) 0 4-.
U) a)
-e V
CD C)
Cl)
CD VI..V V
DL V
U, C
C)
V VI-.V H
.-Li cZ ZI Qo
>C-i Li C)
C-.
in
>1 c02 o
ci) (0 II (V) a)
4.-
- 0) 0 con cu oa)
U)L.
U) 0 ci)
U) 0 U)
-c ci)
I0 U)C0 0
Cl)
U)0 00 0
V CD I) iC V
CD I-)
C) i-U CD ID V
C0 V
0
-C 0I)
ID 0
- 0 0
in CI, C-.
0
-C C.
00 V
C)
CD 0
0 C)
C 0
C)
- 1) gE:
Ce 110 1
C)
U, V
CD C
-C V
C) 0 0
U V
CD C)
C)
I;)
C p
C0 C)
Ci 0
C, C)
C)
C)
V i-i-C in E,
(I)
-c (U z
C)
LI)
U)0 (1)
-I-.
Cl)
C, ci)C E
I a) 4-,
ci)
V C)
H V
-S 0
C)
-e p
110 C)
CD Vs CiCD
-CS C,
C) ij CDii 4-il C) if, 0
C CD 1--40 z
.11 0
C?
,,,f C) 5 11 o
V DC
. C.,
-SQ
CD in C,
ci)
,0 a)
U) 0,
C,),
Cu a)I I
a)N I-:5 Co U,
a-U) 0 4
U) ci) rjz0 4-H Cd H
H C
H
-J Cl)
C)
C.)
C)
C.)
C) ci ci C.)
C.)
Ci C) 0 I-I-
I-I-
I-C I
I I
I I
i_.
0
° 0
0 0
0
-2 0
000 00 0
0 U) o c
c o
n o
c 11 U)
U)
U)
U)
Cl)
U)
U)
U)
U)
U)
U)
U) ci) 2 I-
00 cio U)C1)
U) 4-VI C
D U)a)
LI) 4-0 0
0 cC/)
LU U)
U)
F C))
a) rU)0
-c c
c; lJ z
- r U)
SC) a)
UI U)
_C 00 0z Q4
.2 U)
L
=0) a)
a)ct 4-I ci)
QLI 0
o0 C)
Fc (No
?
ga) o
- (Ø o
(N oct U) 0 0
D Z
Qc I
Wc)c) a (a
a a.
ao a
(a 0
a a
a(I 1
a.
(I) 4i a
a Ha.
aH a
cS (a
(.)
a)
(a (a
Ca
)
.0 LJ 0
U
.0 0
a 2
o a)
£ 2 C
a -.0 (a
a)
.0
- 0 L1 HI U) a)
C C.o.c C
a I.,
m o a J
w z OOOH
-Q_
o.
L. 0 C
.0_JO
- 0).C.)
U)
(-I z
C H
C) a:
D0
-C (0
C
-C 4-U)
U)
Cu 4-,
U)
C))
C 0
0 9-U)
-C 4-,
0.
L..
0 C0 C
2 I
U) 4-,
U)
-C)
U)
(U c1 Iz LU>
LU 0
4-Va) ci)00 a.
a.
4-0 4-.
U) a)
.0 (U
4-U):
0 0
Oo..
U)D I
IC, LUI0z a::
LUz x
LU uC aIØ za ZI
<0 I F-ow zz I-I Cu C
a C
4 z
U a
a Ha 0
UaUa Q
Cl)
LU 0
Li U) 0 4-0 I0 4-(U ci)a.0 a)
L.
=
a) a::
ci x
V ci)a.
a.
C0 4-0 0) 4-,
CD a)C0 4-C)C U
I.0
>a)
-C U)c 0
U)C0 U) 4-C a)0 0.0 (aI a
z
..i C
a g
Z C
I an a)
LI)
C Q
Q 0
0 0
0 U)
U)
U)
U)
U)
Cl) 0 0
U) 2 I-
C, LW 0F-C.I 9
U)w 0
U-U) 0 C.)
0 4-U)
G) 0 0
a) x a)0.
0.
o Hci
())
9-0 4zm CG)
U)
(U4-(U3 (N
oi Co o
c-U) z C
0 i-C 9-0 w
cL<
C i_
ci) z 0
CO oc3 C
U)o C/)
0.
(N0 C?
c Cy,o_
-0 COO (N
-I-.
QCU9 0Z (UU)
U) 00) eEC 0_
o Ozi a
0 C)
C a
00 Co U,
ci (N
C)
Co Co EL0 (0
I U) zuJ 0
a-Co G)
U, C)
.ca co-u
-a X
0 (0
(0 S
ci).E--
Z j5 0
a C)
Da-Q ?E -
0
Øci)
(0 I
,Q) 0...
66 EL0 wI0z U)
U.
a o_
ci)
Ui U)
C-,
- i:
z a
C C
U)
S T
cO cu a)
C)
-o C%1 as Fz w>w-a) a)
U)
I-U)
L 0
a)
C S
I 4-o 4-II I-o I-G)
U)
-o w
D o
F z
=
0)
C)
£ U)
C)
U..
4-C.)
a a
-a (U
0)
C U)
C (U
U 0co (0)
(N U)
D
-a (U
U)0 E
ci)
-I-a 0)
C I
(U
- 1 h C.)
a)
U) 0 4-.
ci)
-a U)>
C)
I U) 0)
C 4-,
(U 0
0 0
900 2:
0)
C a)ci oE cL U) a) m 0(0) w D
U)z uJ zw F
C0 (0
a)0 0
C U)a.
E o
D Ii U)
CO.
(1m
ç..)
(0 V
C
Cu m
Ci)
Sz CU) o o;
. z 0)
C I-)
ci)
-D (0
S U)a S
0 cii cci 0)
C cci 0
C-)
0 Sa)
Ecu (0(0 o5ai CO
)-G)
Wi))
0oE 0
W>
Ci)
(00 C
.2 cci)
Cu S-jr.
c%J E
(U U) a)
a)0
-Q0 I0 (U
ci) 0 (I)
C0 0
U)
-aC (U0 0
C0
-a U)00 ci)
E I-CD C)
C)
C)
C)
C)
F-I F-F-
F-o 0
0 0
0 0
i:
U)
U)
U)
Cl)
Cl)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
I Event No.: 2 Page 2 of 3 Circ Water Pump 3B1 Motor Bearing high temperature from increased bearing friction. The crew will lower reactor power to <60% & secure SJAE suction before securing the 3B1 CW pump using 3-OP-OlO.
Time Position Applicants Actions or Behavior EXAMINER NOTE: The SRO determines the need to reduce power to < 60% and secure SJAE (due to CWP 3B2 not available) in order to stop the pump and not loose Main Condenser vacuum.
(Go to Event 3 for details on power reduction.)
2.
IF all Circulating Water Pumps will be shutdown, THEN ENSURE the following are shutdown:
SROIBOP Main Turbine Condensate System SRO!BOP 3.
ENSURE Amertap System is shutdown per 3-NOP-015.01 Amertap Condenser Tube Cleaning Operation.
NOTE DCS/P1612X indicates Main Condenser backpressure. To determine vacuum SROIBOP from backpressure:
Main Condenser Vacuum = 30 in Hg
- DCSIP1612X_A CAUTION When removing a set of waterboxes from service, Main Condenser vacuum should be monitored using the most conservative indication of the following:
SRO!BOP P1-3-1612, CONDENSER VACUUM (VPA)
P1-3-1406, CONDENSER VACUUM (VPA)
DCS/P1612X_A 4.
ENSURE the following are CLOSED:
3-30-003, NORTH CNDSR AIR REMOVAL LINE TO SJAE SROIBOP SQL 3-30-005, SOUTH CNDSR AIR REMOVAL LINE TO SJAE ISOL 5.
IF removing a set of waterboxes from service and condenser air inleakage is SROIBOP greater than 10 SCFM, THEN PLACE the SJAE hogger in service per 3-NOP-
073.01, Steam Jet Air Ejector Operation, prior to removing waterboxes from service.
7
-H 3
CD Cl)
Cl)
Cl)
Cl)
Ci)
Ci) o o
u 0
0 0
0 0
0 0
w w
a; a;
a; a;
0 0
0 0
0 0
D u
-o 0
co m
zm z0
-Im z-1 1
CD Ui 01OL
,i° rcD m.
0-C, ZCD 0
m mz
-1
-I is.
01 1
I Cl)
W 11W m
°O) E CD D)
- 0-o
Co CoC) 0
.CD CoO 8.
C)
Cn -
CD CD 0
Cj)
- =
%) 0.
CDD - -I -s
>0 CDCD Co i-i-C) z.
DCoCD OCD CD C)
C)
_5
_5
- i 0
Cl) r
Co >. C)
CD C) r o >CD 3
-I.-
Co Cfl CD 0
CDCD (DO CD
(C 00
-o 0-(:3 CD CD CD
-U C
a (00 CD CD CD 0
00
- 5 C
CD (n
0 C
C-)
Co
- 3 Co C-)
0 Ci) 0
-3 13J CD Co 0
-o Co C-)
CD CO Co
- 30.
-ox
-m CD CD Oa
-U In.
C CD
- 5 CD 5)
CD
-o C
S-o 0
000
- 5-CD
- 3 0a-Co0
- 5-1)
CD CD 0
(0 0
CD Cl) z p
M0-C)
C)
CD D
Co
-Sazp m
CD r4-zp M
-U Co CD CD C) 0-h C) rnz C,)
C,)
03 03 M
- 5(DO o
o C)
C)
C C
(DO I
I 0(0 z
z r G)
C)
- 5:3
- o
-o
-ij 50 C
C CD0 U
t3
,jCD C
3D-
_o ci 00 aD)
(DC 0<
-t3
<-1 Ur
>rnz
-0o2. L)
CD g
5) 01 D2.
a_a 3 CD(D 0-(0
,,0 3
. g -a a_ 0 =
o0 (is CD CD Z
00 -a
-Im CD (0
D 00 0
CI) 0 CD S. 2.
- , a CD C,
Z5 H
0 t3 CD CO
=
-S 3_C) 0--
- C)
C CD 0)0 CD Co
-S Qo (1) CD c CD D_
(-3
>0 m!
(oCo C)-,
CD
-h
- 3-30 0
CDh_.
0:3 CD-3 CD CD
-÷ 0)
CD:3
--0 C
3CD o
C)
-S CD CD 0.
x CD
- 0 CD0.
0 CD
-5 Co 0
-5 CD 0
Co
-n0
-5 3
m Cl)6 0
W
)
1 m
(n
oZ 3 CD g5Cn
-4 5.
0 C o 0
m CD 3U CD 4-:5m o
M:53 Mm cm 9.
(D:5 (D(D
- 3(D O-,
(D CD 0)3 0)
>c.
C 00 CD 3
0 (D
C, 00 aa
- 3:5 C
0 a-CD 5) 5C 5
(0
>2 CD CDX
- i CD CD 03 CD 2
D CD a
a
<2.
CD 0:5 CD x
2CD CD
- 2 CD Cz.
O
£?-
3_
O CD 0
Cl) 33 a
0_a_
a_9.
CD CD
- 5:5 CD 5
0:5
0 DD-OCD
- 3 a-C_
CO a)
H 2
3o I
a a
m 0
0 Z
3
da
&0 cy)
LC) t3)
.4-o D
0 U)
Q 0)
(0 (3
0 (30 U)
C?)
E w
0
.4-,
C
.2
.4-,
(3 o
o z
-a o
c U)
(3 U)
C a)
C.)
t Cl)
U)
I0 (Na 1;;
0 U)
HC Ow p = a a
I tZ I
I g))
0 I
H I
Eq)
)
I 8c I
I I
I o E I
o I
IL) 1W I5 I
12 a)ca) a)
I I
I I
- U!
I c*o o
I.J !I I-..
I I
U)
(3 ci)
-c C.)
U)
U)
E
-I-,
C0
-a
-o (3
-o
- 0 Cu C.)
40 cucu
-I-,0 0);
Ecu I.
ci)
U)
C) 00) a2 C
-2 C
C) 0 C.)a) cr W
Cu;;
C,4 I0 UJ a
F ci)- U_
LL cI) a)
cci ci)
4-(J C
I a.)
QLJJ F-9 L
UJ Q
>11 o
CO 1.1.1 CciLIJ a)
V
a) ci)
C cci 0
U-)
CD a.
CT 0 Cu cci
_C C)
C.)20)
..a c
-a.)a)Ci) tZ)1) t cci a)a a)
_C a
0.
Ccii 130 z
2
-a.)
0 d
$)
I-i o
I) ci)
F
<C,)
a)
Cl) a)
C) 4; 0
0 2
Z UJ Q
0 0
4o
.9 ITi
C)
C.)
a U
C)
<(I) a)
0 ci) 0 CI)
çl (I)
Ii-.
C) zwD_
a)
Cz dri d
I 0
C)
C.)
0I) a)
0 c;l 1?
Cl)
LU EI0 U
(I)
C0 C.)
0 Cu I...a)00
-Ua)
U)
LD x
C C
0 ci 0:::
-o Cu0
-J,
U)
Cu LL C0 00 Cd) 0)
U)D ci)
U)C00 U)
U) 0 U)0)
(30 4-,x ci)C ci U) 0)
U)C0 C.)
(3 U)0)
(30
.4-,
0 t7 0
Uaa 00 (a.)
U)
U)
U) 0 Cu
-C U)
CD 4--0 U)C0 0
4:
U)
C Cu Ci 00 4:
0)
C a)
D a)
C C0a) a)0
- E0DC, z
Euj ox
-a:a
a)
C)L)
LJ_
CiCI)
CC)
C).)
IL C*.Zi 0) 2 IL Li.)
j t.).
Z Lcci.23 i
I F-F l2 cz UI LU F
1
øC.)0 0
L
-JOc 0
(9
-2 0Ch.)D
)
Fi?
Cl)
CI)
OOo c
c a...
ci 0)
U)
E I
C)
Co 0
0 Lii LU 0
Cl)
Cl)
Q U)
Cl)
U)
Cl)
Cl)
U)
C) 0 U)
0 W
0 0
0 Iii 03 0
Q
- 3
-I C,
C_)
C)
-I CD CD CD0.
C, CD0 H
C1a.
CD 0
U)p.
-nz rn flQ 0 Or!T1 O
0Q Cfl..
(j.
0.
p iii 9
-n
rTl CD o
1 rn ij
r C) 01 4
Z
-1 CD CD) 0 ti DC CD CD o
CD oti 0
DC DC 0
CD
-o ID 0
DC rC:Ci I
Cf.
U U
I OC)
U I
U I
I I
CC I
0CC.
I ZI CD I
1 m
I I
E I
Iii I
U B
U i:(CC I
I I
U I
rn.
I 00 r
I
>-o C)
U)
-CD U)
C, 0
- 3 U) 0
-C CD
- 3-U) 0
-C C,,
LCD 0
p.
UI DC DC 0
CD C.C CO 0.
2.
Cl Cl CD 0
C o
DC Cl 0
LIC CD C
00 CD
=
CD CD DC Cl 0
-D CD U) 4-z 0
N)0 0)
C, CD
- 3 U)
-C 0z p
m CD
- 3 z
-a U)
(0 CD N) 0
-4, C,
m CD
- 3 EJ CD U)
C,
-C 0
0
- 3 H
- 3-CD C,
-C CD
- 3 U) 1CD CD (I)
U)a 0
-C U) i-CD 0
- 3 0 0
C, CD C
-C0
- 3 CD 0
U)a 0
0 0)0 0
- 5 COc)
G)0-a
-0p i[jH r4 g
fl!I C)-CJ CD DC cI I
C-,
C-40 C
Cl CD
-g g
CD 0
C DC.
2.
çl h° CD CD CD CCC DCSC
Cç ZCD CD DC CD
CD..
DCCD(T
.-.. 012.
I_D%
Cfll i?.*-..-
2 op.:
c3
.D_0 HC,
CD ro
.D CD 0.
x CD
.0 C
-C CD0.
0 CD
-C U) 4-,-
0 C.,
4-,-
0 U) 1 0
m U)6 C)
DC.
0 Cl CD CD (ICti CDII 03(0 D.(/)
1-O -o 2.2.
>11 jO 0
CD W
JCD
>0 0
H H c
_<D CD CD DCC)
Cl O
CD (CD Co 2.> >
DC 0>>2.
o C
DC.
ON 0.
tiCD p.
CD Co 2.
0 Co DC 0
- 3-C 0
03 0
DC S0 CD C
CD Cl Inz CD0 0
(0 CD
-D U)
z U
ii Zr C-ii
()
C C
0 0
9 7z oi z
LLJ 0-(--
>.99 C.
ip lJ,I Li
DC0:
CJ
- )*
C o
a.Q D
EP a)l1)ZCi 6C=
C Li
-0
,(:(
LU o
Zr
C C)
E a.
zF U
C
.0 51)
E C
0)
Li)
C))
o C.
C,)
° liz
.9 13 dl C
C-0-
-CU
>o1
.0o I,)
c*;1 9
U)w E
0 U
0 0
1-0 0
4-Cu 1
ci0.0 L.
=
x
=
0.
0.
00 0
(9 C)
LU 4-
.9 o
U)
- 3 C) 0 a) 0 C)
(C) a)
0 0..
-Ca)0 U)
(Y)
£3 S...
z
4-U) c o
U)>
-D w
0 c
.2 a)
L.
o o
z
-Q o
a)
U) a)
U)
U)
- S C)
+/-
(1) 9 C)
C.J0 C
o o
(:z!
z U
U)
Q_
Ow In di In 4)
Zr 0.
U U
0)N di CO4) 4)N UI 4)C Lii co
.9 C
I if).9 0 CC,)
0
,v ii,
.9 15.9 0.
D 0(55 --
(F-)
)3 9
.9 Ui I.-.
CC)
C C)
.0I di CO4)
-J 0
C)a
-J 4)
C
.0 I
di>
0)
I I
O I B
H I
o IZ I
0 B
C,)
-Li I
Li-I I,)
V I
-C I
15 I
J I
- ° 0
I cI L_i I0
>a)
-c U)
S...0 U)
C0,0 U) C a)0 00 Ci.
(Li (1)
C C,
CD 0
4-0 OS 4-0 o
C)
OS
o i)
.2 U)
LL C.
2 C
C, c,
U0
fl(.5 o
.,V
-J C
C) ai c
(j s2Ln 0
.9
.2
,_C Q
ID Iw
-a
,CQ iH° IDc1
- J Q)
-F--
0<
a
.2:3
,u
.21 C. 0<
(J)a QU) 0 O
U) 6 C
CO if:
CI) 0 CI)
C,)> 0 DO pa, 13 -
00 LLE (55D
(,flli a,,))
03)
CI)
Q_ a) 0.9 0 )
a) 4-0
.0 U)
-c 4-)
U)0 0,
0)
U)
E I-C)
C) 0..
()
C.)
I F-0 F-I g
2 0
0 0
U)0 Q
U)
U)
Cl)
U)
Cl) 2 0-o H
CD Cl)
Cl)
Cl)
Cl)
-o (1)
- o o
0 w
0 0
0 0
-D 0
-1 D
C)
-o C) m C
3 CD
-z 0
-I.
CD CD Cl) 0 3
0 3
z0
-I 3
CD 3
CD CD
-h 0
0 CD (ft C-I.
CD.
(j F) 0 CD 0
0
- 3-0.
2 0
CD 0
ü.
CD CD C
0.
0 0.
CI)
CD o
CI) 3
- 3 0
0) 0 0
iii rn CD.)
-C)
(DID cc)
I6) 0-fl J)-1D m-cj H
9
- 0 3, <
CI) o
1D CI 0
- 3 0
(I) 03-I.)
Ci) 00 0
(Dr
CD 3-(C, 0
T (iI0
-n 3-CD
-ci cim cv rn-u 0.
>c 9-CD H
C
- 3 CI)
CD CI) o cr 0
CD 3
1)
H C
C:30.9 CD C)
- 3-CD CD
- 30
(-3 CD (ft Cx 0)
-4.
CD03 (ft 0
(0
- 3 CD0.
-I 0
C
- 3
-o-o C)0
- 3
-I-(ft 0
0
- 3 (ft 0
oJ CD
- 3-0.9 0
--C I1 II CD
- 3:3-I I
d E
C)
CD 0.
CD r,j I
- 3 CD CD I I1 CD
CD I
I SI I
0CD m
I (I) 9-CD o
0 00 01 D3 0
CD 0
3 3
0
-9H CD (ft z
p F)0 CI)
C)
CD
- 30
--C 0z p
m
.9 CD:3
-Izp
()
-U 0
(0 CD 0
-h (3
(3
>0 CD0D CC z
CD 0
CD CD 0
C ID0.
-n 0
3)0 I 1
ix 9:
> 3 3 mCD-<
9:6 Zr I
3m m
.9 CD
- 3
-4.
CD (30
-D 0
- 3 H
Z3 CD 0
- 3 0
-4.
CD (I) 0 0
0
-C0 0:3 0 a
C0 CD
-4.
C
--C0
- 3 CD 0a)a 0
0)0 C
Cl)
(a (i.)
G)0
-p 0
cD F)
IC-)
3-CCJ 330.
I mz 6
2 I 0 0.
0
- 3_
3-c 0 2.
--U)
Zr C CI)
CD CD C
C!
055 9
(CI I
- 0 CD C
CD
.D
- 1 CD 0
-o CD-0 I-I 0
C, 0
(ft 1
0 m
Cl)
I C) 3-rn 0
I-(CC 0
o CD CD i
CDCD 5,
0 5,
-r 3
C.)
G)
(0 Q.0 CD H
3-ID Z
09 C))a CD 0
CD CD CD C.)
C.)
-1 C)
CD CD C.)
CD C
0 0
3 3
9-9:
U)
)J 0
H 9
ci) 9 g
0 iv Z
-CC 0.
3-u 3-CD 0
3 CD
CD I!
I fl 13 C.)
rI
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 3 Page 5 of 5 Event
Description:
The crew initiates a boration to reduce turbine load to 60% using 3-GOP-i 00 Time Position Applicants Actions or Behavior 1 5 Ensure Station Service Loads Supplied From The Startup Transformer Using ATTACHMENT 2 BOP 1 6 Ensure Auxiliary Steam Supplied From Another Unit Usirg ATTACHMENT I EXAMINER NOTE: When power has been sufficiently reduced and the 381 CW pump has been shutdown, proceed to EVENT 4 (page 1).
FOLDOUT PAGE 1.
3-EOP-E-O Transition Criteria IE any of the following limits are reached, THEN trip the Reactor and Turbine go to 3-EOP-E-O, REACTOR TRIP OR SAFETY INJECTION:
a.
RCS Tavg
- GREATER THAN 578 °F b.
RCS Tavg
- GREATER THAN Tref by 6 F c.
Rod Insertion Limits are exceeded as indicated by:
Rod Position Bank D Insertion Limit Recorder (VPA)
Stepcounters on console Plant Curve Book Section 7, Figure 3 2.
Notify Chemistry Department WHEN reactor power has changed by greater than or equal to 15 percent, THEN notify the Chemistry Department that RCS sampling is required according to Tech Spec Table 4.4-4.
3.
Restore Blender to AUTO WHEN boration is complete, THEN restore the Blender to AUTO as follows:
a.
Place the Reactor Makeup Selector Switch to AUTO.
b.
Set FC-3-1 13A, Boric Acid Flow Controller pot setting as desired.
c.
Place the RCS Makeup Control Switch to START.
13
Cl, 00 E;;-I C,
C,,
00; I
C)
Cl, 0;
I C-)
H B
CD C) 00;
-I C)
(I) 0 Cl,
- i0;
-I C)
Cl),0 I
C)
CD 0x
-a 0
U) 0
- 3 0
0 CD U) z 0
M0 0
0 0
0 U)
B CD (1)00D U)
CD U)
C, 0
0 C)
C, C)
- 3-
- 3
- 3.
- 3 CD CD U)
C)6z0 0
0C
-I-
-o U)
CD CD U)
C, K
0
- 3 C)
Cl)
CD CD
- 3 CD
-I U)
CD CD 00 U)
CD CI)
U) r CD 0
CD 00 C,,
CD CD Co U)
D C
- 3 C,
U)
K 0
Co CD (5,
CD B
- 0 K-Co K
0 C,
0 Co CD U) 0 C-)
C)
(Ti9)
OI3
(,)
v):
- 3*
.-N C)CD
- 3--
-b
- 3-,
r-0,
.L!
t
- 3 0,
CD g,,
c
-.4c 0
C
-o
-D C,
U)
I-U)
C, K
0
- 5 C) 0 CD
- 3-U) 0
-S
-S CD C,
K-U)
-S CD U)00
- 5 U)
CD C
U)
CD K-
- 3-CD
-a U)
- 30 CiA) 0z0 5,
cr (i
D
CD C)
G.)t o
CD o -cs -
0 CD b E
CD f (DO C)
CD.-.
C)
CDV)
CD b
CD C,
CD
- 3 C-)
(I)
-ø
-S CD C)
U)C 0.
CD C,
U)
Co
- 3(p Cl)
C, CD
- 5 U)
-S 0zp
-A I
I I
U C,
0 C)
CD (0
0 C,
U)
CD 0
C?)
(5 (A)
(5, K
0 U)0 U)
CD CD U)
U)
(0 D
Th 00 00
£1>
<0 CD C) 00 0.
0-CD 0
0 0.
0 CO
- 3-0
- 3-0 C)
CD0 C
0 1
0 1
I I
I 0
I I
0<0 I
D2.
0 Z r0
>0
!11 (DCc HO T1 -
CD rn rn I 0
Q_f o
C,.)
0 C_h CD Cl)
-Iix
<G) a-i a-(Ti o
C)1 0)
U)
U) m Q
CDCD U)B CD -o CD -D K-CD H
U)
O3-B o
CD C,
OCQ 13 QCDoH CU)
CD D
CD j CD 0 -h D
a Co
?;* <-
-. :5-
< 0 (i-i.
C, 9:3-CD o r-i U)
()
CD CD C,
CD CD
- oD0CD,
- C,
. U)
U)
< t3
-zg B o CD U)
K-U) 5 o
CD t3 C
KSCD CDaa U) <U)
CD CD CDCD CI)ØQ 0-(5, 0
0
-a
-S CD U)
U)C
-S N
CD
-Sr 3
- 3-
-U C,)
C,)C
-a C-)4 (5
0) 5.
CT Co K-U)
CT CD 0
- 3-0z
-aN 0
U)
C,,C C,0
- 3 C,
- 5-U):3
- 5 CD
-a C?)
C-fl 0
CD CD CD CD0
- 5-CD:5-CD
.Dt CD 0
CD 0
-I C,
0 0)
-a0
-o C)
(A)
(-I 0) 0
-a CD
- 5
- 5-
- 50 0)a C
0)
- 5-CD
- 3-
-o ci)
U)C 1
CD C,0 0
K 0
- 5 m
CD z
p
-a U)
CD CD 0
-h 0) 1 0-rn Cl)6
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 4 Page 2 of 6 Event
Description:
PT-3-445 fails high, the crew responds using the ARP and 3-ONOP-41.5 to attempt to manually close PORV-456. During the instrument failure PORV-456 develops leakage.
The contingent action is to close the block valve to stop the leakage. The SRO will address LCD 3.4.4 due to excessive leakage on the PORV.
FOLDOUT FOR PROCEDURE 3-ONOP-041.5 1.
FAILED INSTRUMENT ISOLATION a.
any Pressurizer Press,jre control Instrument Loop fails, TI-lEN place applicable control switches to a position that isolates the failed Enstrument.
2, PZR pressure cannot be maintained greater than 2COQ psig, perform the following:
a.
Ccntrnue efforts to restore PZR pressure and b.
Trip the reactor and turbine and cm to 3-EOP-E-O, REACTOR TRIP OR SAFETY INJECTION.
3 PORV ISOLATIONfLEAKING PORV IDENTiFiCATiON a.
IF any PORVi5 OPEN OR Leaking pressure is less than 2235 psig, THEN CLOSE the aplicabIe PORU andfor Elcck valve.
b.
The following are indications of leakage from a PZR POR/ and should be used to identify and isolate a leaking PORV:
I)
PZR relief tine temperature, 71-3463, iNCREASING.
2)
PZR relief tank level Ll-3-470, NCREASING.
3)
PZR relief tank temperature, TI-371, INCREASING.
4)
PZR relief tank pressure, P1-3-472, iNCREASING.
CREW 5)
PZR PORV/SAFETY ACOUSTIC MONITOR, LEDs LIT.
4.
OPENILEAKING PZR SAFETY VALVE IDENTIFICATION a.
The following are indications that a PZR safety is open or leaking:
1)
PZR Safety line temperature, Tl-3-465, INCREASING or at saturation temperature associated with the PZR relief tank pressure per Mtachment2.
2)
PZR Safety line temperature, Tl-3-467, INCREAS1NG or at saturation teinperatuTe associated with the PZR retef tank pressure per Attachment 2.
3)
PZR Safety line temperature, Tl-3-469. INCREASING or at saturation temperature associated with the PZR relief tank pressure per Attachntent2, 4)
PZR relief tank level, Ll-3-470, INCREASING.
5)
PZR relief tank temperature, TI-3-471, INCREASING.
6)
PZR relief tank pressure, P1-3472, INCREASING.
7)
PZR PORV/Safety Acoustic Monitor, LEDs LIT.
5.
SPURIOUS ACTUATiON OF r.V3..311 AUXILIARY SPRAY VALVE due to itre in Containment or 35 4KV Switchgear Room a.
IF pressurtrer pressure is decreasing and Auxiltaty Spray Valve, Ci-3-31 1 is suspect, THEN reduce charging to one charging punt p on slow speed close charging to RCS Control Valve HCV-3-12 1.
15
cHm 4
CD(DCD 3D 1
-D CD CD CD.CD D°CI)
Z 0(O3 p
0 CDQ)-
0 (jC 0r C)
CD W()
)
0 D)CDJ 01 m
a)c1 0
0 0
01 C)
))
6)0 (DQ H
H.
F Z
EJ CDcnO Z3 CD
003(0 0
0 CD--
D CD))
!CD ij
-u 0) mCD 3
CDC5 (1)
0 O
-4 CDO*D CD CC) z D.CD P
00 rnZ D
0.
-o
<a)(Qq C) rn 0
<D CD
° 0(0 0
0 C,
CD 0
CD 33 CD
((>0 Cfl a) 4m CI1Q.
CD>
-TI r-2,(*
8 o-o 0
C)
-CD CD (ft oi
,-,. 3 ci D
0)
(I)
CD 0
b (1)
)
C))
DC Z
Cr CD P
o C
5
- u
-a C) a)
>m fl1 CD
CD
-a 0.
CD H
fl CD
- u
>2,
CD
(/)D)
CD
-ou
.0 00) 0 (0
zCD0
-h CD (3) 1 0
U 0
3 9
I.)
m C,)6 D
3
Øm 0
-D 0-(Dcp i
ø3 CD CD cnCD--D CD H
0 C1)
Z x
o CD
-o (3O jj Oco o-K
=..
- 3<-,
I 0-(Q C)
J
(.)
CCD71 0
o 0 CD j.
(-)
i,-1 CD,-,-
01
>< 0 L)
0 CD CD
,-(D ZL CD a.
0z (DD-Do 0.
0 OcT CD-
-I.
m CDCD0
a z
-0:3 c) 0
(
.g 1J
cDti>
CD0tj J
D)<
0 CD (D
010 H
0 D0
-h CDCD<z a
-n 0
_j 3
m
=
01 CI)6 H
3 CD Cl)
Cl)
Cl)
Cl)
Cl)
Cl)
-u a0 0
0 0
0 0
2-0 I
I I
I I
C)
C)
C)
C)
C)
C) vm CDX
.0 I
I 0
3CD 0
C, 3z rç q.
CD DC C1)
--o CD
-N C) 00 00 (1) 0
-I.
CY H
fD
- 0
- )
CD9
=
0
.2-z m
CD 0
0 D;Q 0
(DCY o
0) 0)
0 V
C)
D C,
C)
CD 0
z 3,
Cl)
C) 01 CD CD (1)0
(,)
o mci>
01 0
u Z
0)
CD 0
S 0
cm 0
o 0<
CD CDJj E.
-u CD 0
C) 0)
0 I
7c-I 0-mIo Co I
-a CD
, I (TI
oi-ij
a) 0<
ONIX r-(T)
CD
Q*
3 3
1 Zj 0H 0<
0) 3 0
IZN 0.
D ca 3:
CD O
V 6
CD DC V
CD CD 3
=
2.
0) oJ DC)CD(n 63
<3
.CDCD 9
CD
<c CDO 0
zC) 0)
cC) oc-J
° C)
CD CD CD Z
J 0
0)
V O bri 0.
D
CO 1<
?-
1 r>
L CD CD II:i C,)
CD I
0)
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
I Event No.: 4 Page 5 of 6 Event
Description:
PT-3-445 fails high, the crew responds using the ARP and 3-ONOP-41.5 to attempt to manually close PORV-456. During the instrument failure, PORV-456 develops leakage. The contingent action is to close the block valve to stop the leakage. The SRO will address LCO 3.4.4 due to excessive leakage on the PORV.
Time Position Applicants Actions or Behavior 3
Check PZR Spray Valves Closed IF PZR pressure less than normal. THEN perform the following:
PZR pressure normal or trending to normal a.
Verify PZR Spray valves closed.
Place PZR Spray Loop C, PCV-3-455A in MANUAL and CLOSE.
Place PZR Spray Loop B.
PC\\/-T455B in MANIJAL and SROIATC CLOSE.
Verify Aux Spray Valve CV-3-3 I CLOSED.
b.
IF PZR pressure can be maintained greater then 2000 psig, THEN perform the following:
1)
Trip the reactor and turbine and go to E-0. REACTOR TRIP OR SAFETY INJECTION.
2)
Trip the RCP in the affected Ioop 4
Check RZR Safety Valves Closed a.
PZR PORViSatety acoustic monitor LEDs
- NOT LIT h.
PZR safety line temperatures at or near normal SROIATC a p safety line temperature, Tl-3-465 a
PZ safety line temperature, Tl-3-467 a
safety line temperature, Tl-369 5
Check PZR Pressure Stable Or Increasing Perform the following:
SROIATC Continue efforts to restore PZR pressure control.
Determines Pressurizer pressure can be maintained greater than 2000 SROIATC psig.
Recognizes requirement for LCO 3.2.5 Action b entry.
SRO 18
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 4 Page 6 of 6 Event
Description:
PT-3-445 fails high, the crew responds using the ARP and 3-ONOP-41.5 to attempt to manually close PORV-456. During the instrument failure, PORV-456 develops leakage. The contingent action is to close the block valve to stop the leakage. The SRO will address LCO 3.4.4 due to excessive leakage on the PORV.
Time Position Applicants Actions or Behavior SRO Recognizes requirement for LCO 3.2.5 entry.
3.2.5 The following DNB-related parameters shall be maintained within the following limits:
a.
581.2F b.
Pressurizer Pressure 2200 psig*, and SRO c.
Reactor Coolant System Flow 264.000 gpm APPLICABILITY:
MODE 1.
ACTION:
With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less then 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SRO Recognizes requirement for LCO 3.4.4 Action a entry.
3.4.4 oth cower-operated relief valves (POR/s) and their associated block valves snail be OPEA5LE, APPLICABiLITY:
MODES 1,2, and 3.
ACTION:
SRO a.
With one or both PORVa inoperable because of excessive leakage, within 1 hoar either restore the PORVIs) to OPE.9ABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherNise he in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in OT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
EXAMINER NOTE: When Pressurizer pressure is stabilized, proceed to Event 5.
19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
I Event No.:
5 Page 1 of 1
Event
Description:
B Condensate Pump Motor Shaft slowly seizes causing a failure of the pump. The automatic start of the C Condensate Pump is blocked. The BOP can manually start the C Condensate Pump or stop one Main Feed Pump to initiate a Runback to equalize Turbine load with available Feedwater flow.
Time Position Applicants Actions or Behavior Direct Facility Operator to trigger lesson step, EVENT 5
- LOSS OF 3B CONDENSATE PUMP. (insert TVFABP6B 1.000000 delay=0 ramp=300 on=0 off=0, insert TFF1 D6CM TRUE delay=0 ramp0 on=0 off=0, and insert TFF1 D6CM FALSE cdimf1 p6cs delay=0 ramp=0 on=0 off=0)
Observes the following:
RCS pressure decreasing.
SROIATC e
PZR pressure control channel PT-3-445 pegged high PORV PCV-3-456 open with no actual high pressure condition Pressurizer High Pressure PC 456A bistable light ON.
SROIATC Observes annunciator: D 9/1 and D 9/2 SRO Directs response using the ARP and/or 3-ONOP-089.
CAUSES:
- 1. Motor malfunction D9 2.
High system flow 3
Low bus voltage COND PUMP SRO/BOP AJBIC MOTOR OVERLOAD ALARM CONFIRMATION SROIBOP 1.
CHECK Condensate pump(s) ammeters)
OPERATOR ACTIONS 1.
MONITOR SGFP suction pressure.
2.
IF necessary to maintain adequate suction pressure, THEN START 3rd condensate pump.
SROIBOP S.
CHECK associated feed train components for proper operation.
4.
REQUEST Operator check condensate pump recirculation valves closed and amps locally.
5.
IF cause of motor overload can NOT be corrected, THEN MAKE preparations to stop affected pump(s) using 3-OP-073, Condensate System.
Starts additional Condensate Pump.
SROIBOP Stops 38 Condensate Pump with high current if not tripped.
20
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.:
5 Page 1
of 2 Event
Description:
B Condensate Pump Motor Shaft slowly seizes causing a failure of the pump. The automatic start of the C Condensate Pump is blocked. The BOP can manually start the C Condensate Pump or stop one Main Feed Pump to initiate a Runback to equalize Turbine load with available Feedwater flow.
Time Position Applicants Actions or Behavior CAUSES:
i Motormalfunction 18
- 2. Low bus voltage COND PUMP SROIBOP NB/C MOTOR OVRLD TRIP ALARM CONFIRMATION SROIBOP 1.
CI-IECK condensate pump indicattons on console.
OPERATOR ACTIONS 1.
ENSURE the following automatic actions have occurred:
Automatic start of idle condensate pump if applicable Possible trip of SGFP SROIBOP 2.
MONITOR SGFP suction pressure.
3.
REQUEST Operator check condensate pump breaker(s) 3AA21, 3AB21, or 3AC12 for any targets.
4.
REQUEST Operator check condensate pump(s) locally for any abnormal indications.
EXAMINER NOTE: When secondary system parameters stabilize, proceed to Event 6.
If another Condensate Pump is started late after a Main Feed Water Pump trips, then continue below with initial steps of 3-ONOP-089, Turbine Runback.
SRO Directs response using 3-ONOP-089.
4.0 IMMEDIATE OPERATOR ACTIONS CREW 4.1 Verify the automatic actions listed in Section 3.0 are finictioning to stabilize and maintain plant conditions, or assume manual control.
3.0 AUTOMATIC ACTIONS 3.1 Main Turbine Control Valves and the Reheat Intercept Valves modulate closed upon receipt of a rsmback signal from the Generator Governor/Speed Changer.
3.2 Steam Dump Valves ann and open to relieve excess steam to the condenser due to the load rejection anrl subsequent Tavg.Tref mismatch.
3.3 Automatic Rod hssertion Coistrol adjusts core reactivity to issatch. Tavg with Tref.
C RE\\N 3.4 Main Feedwater Control Valves opeis or close in progranuned response to steamflowfeedflow mismatch and level input signals, to maintain steam generator levels at proeram.
3.5 Pressurizer Level Controller and Pressurizer Pressure Controller vary clsarging punsps speed and Heater/Spray actuation to maintain the programmed level and pressure, as reqssired for the changing values of Tavg.
3.6 Turbine runhack upon a SGFP breaker trip with first stage pressure greater than 45 perceist load.
Botls a governor and a load limit runback occssr smtil first stage pressure is at 15 percent load.
21
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.:
5 Page 2 of 2 Event
Description:
B Condensate Pump Motor Shaft slowly seizes causing a failure of the pump. The automatic start of the C Condensate Pump is blocked. The BOP can manually start the C Condensate Pump or stop one Main Feed Pump to initiate a Runback to equalize Turbine load with available Feedwater flow.
Time Position Applicants Actions or Behavior SUBSEOFENT OPERATOR ACTIONS 5.1 Determine the cause of the runback initiation AND refer to the appropriate ONOP for specific recovery instructions.
5.2 Verify the following conditions:
CREVV 5.2.1 Steam generator levels and pressures stabilized.
5.2.2 Steam dumps closed.
5.2.3 Tavg matches Iref.
5.2.4 Pressurizer levels and pressures stabilized.
EXAMINER NOTE: When secondary system parameters stabilize, proceed to Event 6.
22
CD D
CD C,
0 Ci)
CD C)
C,,
(I)
CD CD3 Cl)C p
J U
-I CD3.
-o CD QCD CD Oo CD 0) 0)
V U
CD tV C2.
CD (0
3 QCD CD 0
G) 3<
-c) 0
.)
In V
I (D
CD 0.
0
0 (I)
CD 0
m V
CD
2 0
CD p
p_
iZ I0CD CDIOCD CDI_
CD 0
CD CD 2
(DCD
°-H 0
CD0.CD IXE Im -
1 Ea -I CDImCD CD Izth 00_
CD Jm VCDCD CD CDCD CD Qg 3*<
I CD
<CD<
CDQ-CD3L CDO CDm(D 3<
Lfl 0
000.
CD CD.
0 CD z
u ou 0
CD 0
r1(D 0
C 0
mCD 0
g z
g-CD z(
g nIl 0
0 c
0 3
CD
=
I o
cj Q
V m
In
(_)
I 00 0
g 2
H CD UN m
CD 0
CD z CD CD
>ZQ 11WnI HCo Cn0 Z
0
-P Q>r 1
n 71 CDO 0CD (flQC) 5 flhi m0
-11 (CDCD z[n C
0.0 m
i--*
mlo x__
>0 0 rn m
Z0 CD cn 00 0
(0 q
CD o Cn) -.
o r C
°>rl CD 1)),p
.=
ii o
Zt t30(D ii
-I -
O) a om omo o Ci).-,.
0 C/)(C/CD
<Cl)
Cii 00 m
0<
0l 1o cD70 0<
0 1101 0
Oi 0
liz 0
0)
(1)
- 1.
H<<
I>
c5m CDm 0
-D t
3 3D CD o, CD 0
CD 3 N) -0 c
CD.
5_
Cn)0 (i)CD N) 0 0 (0, -
CD 3 0)
C C)
D--_
0) 0 CD
(-CDCD CD 4-0 CD CD C
CDn0 P
mc) 0-ti<
m CD C
m-CD Z
-0 0
)
0)
-a (flCD C)
(0 0_
CD CA) 0 mC 0
UCD
-ti:S CD Cl, Cl)
(I) 70 70 70 C) 0 0
0 70 Cl)
CO m
0 0
00 0
0 C_)
N)
(n)
-H 3
CD
-a 0
CD 0D 0
C, CD CD C,
4-0 CD 0-,
03 CD
- 3-C)
C 0-,
a CD CD 0
- 3 CD CD C
CD
- 5 (0
m0
-p r71 0
CD CD
- 3 (0
C) Cl) CD O-C) 0 a
C) 3 C)
- 3C C) V CD Cn CD CD C-)
0
-I V
U)
CD
-o0
- 3 1
U)
CD CD C-)
CD 9-I I
I I
I I
I I
I I
iir IV Ill I
S-I I
CO I-I I
I 0
Cb I
nil I
I I
I 0
I I
10 l
I Cl)l I
VI I
I I
I I
I I
I I
I I
I
- o CD 70 CD CD 0
CD
-I CD 4-I.
0
-I C,
0 CD
-n 0
3 m
Cl)6
Appendix D Required Operator Actions Form ES-D-2 a.
Perform the following:
1)
Attempt to emergency start any Unit 3 available diesel generator.
2)
IF neither 3A nor 384 KV bus is energized, :w.g!a go to 3-EOP-ECA-O.O, LOSS ALL AC POWER, Step 1.
b.
Attempt to emergency start the de-energized Unit 3 bus diesel generator.
c.
Perform the following:
1)
IF lockout of 3D 4 KV bus NOT present, THEN perform the following:
a)
Verify 3C COW pump BREAKER OPEN.
b)
Verify 3C lOW pump
BREAKER OPEN c)
Operate bus supply breakers to restore power.
Op-Test No.: 201 1-302 Scenario No.:
1 Event No.: 6 Page 2 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Applicants Actions or Behavior Time j Position Applicants Actions or Behavior 3
Verify Power To Emergency 4KV Buses a.
Check the 3A and 38 4 KV buses MAINTAIN AT LEAST ONE ENERGIZED b.
Check the 3A and 38 4 KV buses MAINTAIN BOTH ENERGIZED c.
Maintain the 3D 4 KV bus energized ALIGNED TO AN ENERGIZED 4 Ky BUS SROIBOP 24
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-302 Scenario No.:
1 Event No.: 6 Page 3 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 4
Check If SI Is Actuated Perfom the following:
SI Annunctators
- ANY ON a.
Check if SI is requirec:
OR Low pressuriser pressure 1730 psig Safeguards equipment AUTO STARTED Hiçh containment pressure 4 psig OR High steam line differential pressure 100 psid a
SRO!ATC Hich steam flow with low SIG pressure - 614 psig OR low Thvg (543 F) ti. j SI is required. THEN manually actuate SI and containment isolation phase A AND go to Step 5.
- c. SI isrequired, perform the fohowng:
1)
Monitor Critical Safety Functions using 3-EOP-F-0, CRITICAL SAFETh FUNCTION STATUS TREES.
2)
Go to 3-EOP-ES-0.1 REACTOR TRIP RESPONSE, Step 1.
CREW L
FQLDOUTPage shall be rnonito:d forthe rernathderof this procedure. -
CREW Monitors 3-EOP-E-0 Foldout page (see next page) 5 Continue With Attachment 3 To Complete SROIBOP The Prompt Action Verifications While Performing This Procedure Examiner Note: 3-EOP-E-O, Attachment 3 commences at Page 12 of 23.
Examiner Note: The SRO and ATC will complete the remaining steps in 3-EOP-E-O, while the BOP performs 3-EOP-E-O Prompt Action Verifications using Attachment 3.
25
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 4 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior FOLDOUT FOR PROCEDURE E-0 1.
ADVERSE CONTAIN MENT CONDITIONS IF either of the conditions listed below occur, THEN use adverse containment setpoints:
Containment atmosphere temperature 180° F OR Containment radiation levels 1.3x10 RJhr WHEN containment parameters drop below the above values, THEN normal setpoints can again be used IF the TSC determines that containment integrated dose rate has not exceeded 106 Rads.
2.
RCP TRIP CRITERIA a.
IF both conditions listed below occur, THEN trip all RCPs:
- 1) High-head SI pumps
- AT LEAST ONE RUNNING AND SI FLOWPATH VERIFIED.
- 2) RCS subcooling
- LESS THAN 25°F[65°F]
b.
IF phase B actuated, THEN trip all RCPs.
3.
FAULTED S/G ISOLATION CRITERIA IF any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized, THEN the following may be performed:
a.
Maintain total feedwater flow greater than 345 gpm until narrow range level in at least one SIG is greater than 6%[32%].
b.
Isolate AFW flow to faulted SIG(s).
c.
Stabilize RCS hot leg temperature using steam dumps when faulted S/G has blown down to less than 10% wide range.
4.
RUPTURED SIG ISOLATION CRITERIA IF any S!G level increases in an uncontrolled manner OR any SIG has abnormal radiation, AND narrow range level in affected S!G(s) is greater than 6%[32%], THEN feed flow may be stopped to affected SIG(s).
5.
AFW SYSTEM OPERATION CRITERIA a.
E two AFW pumps are operating on a single train, THEN one of the pumps shall be shut down within one hour of the initial start signal b.
two AFW trains are operating and one of the AFW pumps has been operating at low flow of 60 gpm or less for one hour, THEN that AFW pump shall be shut down 6.
CST MAKEUP WATER CRITERIA IF CST level decreases to less than 10%,
THEN add makeup to CST using 3-NOP-018.01, CONDENSATE STORAGE TANK (CST).
7.
RHR SYSTEM OPERATION CRITERIA IF RHR flow is less than 1000 gpm, THEN the RHR pumps shall be shut down within 44 minutes of the initial start signal.
26
U)
U) iz U;
D L1J G
cx:
N-I-
U).
Q2U)
U)
U
_U)t)
D C)
U cx:
U) U) ci)
U)U)
LIJD DcCf)
(N (N
e Co w
E 0
U 0C0 C.)
L.0 a)0.0
- 0 a) x V
C a)0.
a.
U)
U o
>o I UI
U)
E
- _U Q0 U)
U)U)(
o°- >00
-s -o- <
(U--.
E H<E 0
I I
(I)
.iw-J I
0 E
b CD CUQ) 0.
0 9
Ia) 0.
4-00 NQ)
U)
U)U)
.r.0 LI U) 4 CuD_
o coW (Y) a)
130 0)
U)
Q)U)
O LO C)
C)
U) 0 ic z
- E U)
.J U)i W
>0 OW o
OCOU) z 0
-00)
U)
.°o c
U) 0 U) i D
- CI)
- 0) 0 0 U)
U)
I -
U)
?
F.2 Cç o
CN Z
U)LOU) 4-.
U)
LJQ I
&o WQU)
U 0
U)
U)
U>
11) 0 (U>
U)>
C U)
(U w
U0 ft:c1 C
<0 0_j
>-0 ULU
<0
>w 0
4-I-0 L..a.
C.)0
-J CD C,)
CU CIz V
C 00 0
9-00 9-CU 0
0-a)G) 4-0) 4-
-I a)
I-0 U)
-c U)
CD I-0 U) 0 0
U)
.4-,
U)0 00 C0
-I-,
U)00 a)
E I-N cJ C.)
C)
I I
f0 0
O U)
CO
u.FL rj Li)
I 0 u UHJ
- -U,ç U)
. LU LU u
Lii 4-
,C!)H LLS 0z U) U)
IL F i a
- 0. iij fl oUJz0
çQZ 00 U) c o Lii LU c) 1r U) U)
C0 ZI 3
C (3
0 ot cc1 01 0
C
>,(l
- 3o5 si)o (1(00.
(1 4
0 C
o?
d C0 00_
i 2
o
LL.
C0 IL LU Li.
H 4
04 LIj 00.0c 0
- o co e
Co Ui EI0 U
(UC0 4-C.)
0 4-(U I-00.0 ci)ci x
V C00.
0.
U)
-CD 0)!
g LJ C3Q 0
U)UJ (0
o a)
_50 0) a)
a)Cl) a CO
(.0 c (Y) a)
I
4-o 0
c z
a)
.jj a) w
>o ow
-2.
c OCø)a) z o
- -00)
.z a)
-o-C ci)
U)° 0
_)
I.
1 D,
- 0) 0 0 (N
.a)U)
U)
C?
i0 WD-w I-0
>a) ci) 0 U)C0 0
U) 4-,C a)0 0
ci 4-,0 CU (U
4-0 4.-E.
C)
CI) a)L..
4- 0 (U
--U-(9<
mu)
CCI)
(93 COQ a) 0 4-4..
Oa)
Li 00 U) 4 a)
-C LL if) 0 U,
U) 111 cii 00 4-0 C)
C C0 4-(U C
4-0 4-0 0.
E0.
C)
If)
C, 4-0 0
U E
E E
-t (U
.0 CU 4-I U)0 C
a).t 4-LL
<LL.
I-a a
2c 0
0ci 0
0(I)
-C)
-C Oc.
II jC) 4-co
(\\1 0
c_)
0 C
I-.
I I
02 0
0 0
U)0 D_
Cl)
Cl)
Cl) a)
E I
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-302 Scenario No.:
1 Event No.: 6 Page 7 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position
[
Applicants Actions or Behavior 9
Check RCP Seal Coolthg Check all RCP thermal barrier alarms
a j COW to an RCP thermal carrier is lost OFF A 111. RCP ThERMAL BARR U
Trip the affected RCP(st.
COOLING WATER HI FLOW 2)
Go to Step 8c.
A 112, RCP ThERMAL BARR COOLING WATER HI TEMP A 113. RCP THERMAL SARR COOLING WATER LO FLOW Go to Step 10 c.
Check all RCP seal return temperatures c.
Go to Ste 1Q are less than 235 F d
lerify SI RESET th ResetSL IF offsite power is NOT available. THEN check diesel capacity adequate to run one charging purnp adequate diesel SROIATc capacity 5 NOTavailable, THEN shed nonessential cads.
Refer to ATTACHMENT 2 for component KW load rating L
Start one charging pump at imnimun, f
Go to Step 10.
speed for seal injectton g
Adjust Charging Flow To Regen Heat Exchanger HCV-3-121, to maintain proper seal injection Sow 29
H B
CD Cl) 0 Cl)
O 0
0 0
0 5
I I
H C)
C.)
C)
Q CD0 C)
CD U) 0 0
11 t3
-o C)
U)
- 5 Ci)
C) 0
- 5 Cl) 0
-I w
CD
- 3-U) 0
-I p
ml) nG 0>
Z
-o
- cpc,
(
C 0
0_
- ij
-o J) fli
-N cc
-o I
0.
U) 0 t)
(P C!)
c,,
In 0
p C)<
0
)
I a
)
0
0 I
U) 0.
2 mI (P
0 m_
m IU g g-r U)O yc9.<,< oc
<Om H79C
ç-
i
.0E3 O
O
>0 I:i.?
- 0]
o C?
z° i01 o,C.
In
<D0.
0 (P.
0 H
CD Ci) z p
I)0
-A
-A (A)0 t\\)
0)
C-)
CD
- 5 U) 0zp m
CD:5 z
3)
-u U)
(0 CD 03 0
-h N)
(A)
CD 0<
CD 0i CD
- U) 0
. 0 D
CDP ci)
CD 5 0 0 (0 0 -
C-)
CD Cl)
Cl)
(0 Q (l)N cQ. o (0?
5(0 i0 mo 0-1J<
U)
Io CD
- 5
- 5 (31 5 Q (j)CD
OCD CA) 0 05-U)
CD
-u Cl) 0 (P
>U) z QIfl
-s 9
flrn IH ci
-Il J
(Orn2
-l L
-II 2o 0
cc C
__(PC)_
-.,..(P
...,o
(
Dci
0
ç:
o--
- hjc, 2.
-iE
=0 CP C
- r 0
x ir A2 r,
g-Lc, g
C)
- 0. 0 (P
(P 0 x 0.
(p
- 0
- 0 CD 0.
- t CD
.0
-I CD0.
0 CD 0
C.)
P.
0 (ft 1
0 3
m
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 9 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior I I Check PRZ PORVs, Spray Valves And Excess Letdown Isolated (continued) d.
Excess letdown isolation values
d.
Manually close valve(s).
CLOSED SROIATC CV-3-387, Excess Letdown Isolation Valve From Cold Leg To Excess Letdown Heat Exchanger HCV-3-i 37, Excess Letdown Flow Controller 1 2 Check If RCPs Should Be Stopped a.
CheckRCPs-ANYRUNNING a
GotoStep 13.
b.
Check RCS subcooling LESS THAN b.
Go to Step 13.
25F165F)
SROIATC c.
High-Head SI Pump AT LEAST ONE c.
Go to Step 13.
RUNNING AND FLOWPATH VERIFIED d.
Stop all RCP5 Stops RCPs if subcooling is less than 25°F (65°F) with HHSI flowpath SROIATC verified with HHSI pumps running.
REWCRlTlCAL,TASK1 Trip RCPs due to a loss of subcooling during a SBLOCA prior to completing step I of 3-EOP-E-1.
31
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 10 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 1 3 Check If S/Ge Are Faulted a
Check pressures in all SOs
a.
Go to Step i&
ANY SO PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR ANY SO COMPLETELY SROIATC DEPRESSURIZED b.
Perform the following:
I Monitor Critical Safety Functions using 3-EOP.F-a. CRITICAL SAFETY FUNCTION STATUS TREES 2)
Go zo 3-EQP-E-2, FAULTED STEAM GENERATOR ISOLATiON. Step 1 1 4 Check If SIG Tubes Are Ruptured a.
Check levels in all S/Ga and secondary a.
Go to Step 15.
radiation levels:
ANY SO LEVEL INCREASING IN AN UNCONTROLLED MANNER OR Condenser air ejector radiation, R-15
HIGHER THAN NORMAL OR SG blowdown radiation, R-19 HIGHER THAN NORMAL SROIATC DCS SO or secondary radiation readings HIGHER THAN NORMAL OR Local steamline radiation HIGHER THAN NORMAL b.
Perfom the following:
1)
Monitor Critical Safety Functions using 3-EQ P-F-C, CRiTICAL SAFETY FUNCTION STATUS TREES 2)
Go to 3-EOP-E3, STEAM GENERATOR TUBE RUPTURE, Step I 32
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 11 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 1 5 Check If RCS Is Intact Perfom the following:
Containment radiation
- NORMAL 1
Monitor Critical Safety Functions using 3-EOP-F-O, CRITICAL SAFETY Containment pressure
- NORMAL FUNCTION STATUS TREES Q
Containment sump level
- NORMAL 2
Go t 3-EOP-E-1 LOSS OF REACTOR I
OR SECONDARY COOLANT, Step 1 LI-3-63084 LI-3-63086 CREW Diagnoses the Small Break LOCA.
SRO Transitions to 3-EOP-E-1.
BOP Continues performance of 3-EOP-E-0 Attachment 3 Prompt Action Verification.
Examiner Note: 3-EOP-E-1 details start on EVENT 6
- Page 18 of 23 33
H CD
-a 0
w w
w w
0 0
0 0
0 U
C)
CD C))
- 3
-I, CD CD
-C
-a 30 (I)
- 3.
CD Cl)
- 3 Cl)H0
(,3 U)
()
(1)
U)
Cow>
r r
I-I 1
00000
.1.
jj UICD 09 CD (DC)
CD3 0 -9 2
- s 0
CD
<° CC)
(71 U)
-I, D
,()
D()
C) 1QCD C) 0.:;
z UI9.
2.2.
<CD 0
UI CD CD CD.
0.
0 CD fl 0
3 m2.
ZC) 0 UI c
C)..
9 0) 2 CD F-P C) 0 o
o o
o U)
U)
CD CD lCD U)
-o
-o C)
Cl)
C) 0
- 5 Cl) 0
-C CD
- 5-0 CD 0.
(1 C
CD CD C
T1
-n UD()
CD
CD CD E
CD, UI CD CC)
CrC CD
-ijCD 3
CD CD 30 CD Ci) 3 3
CD CD 0.
t7 CD CD
CD CD.
0)
CD CD 2.
z V
I CD
-D 3
00 C
UI
-D n
C)
UI Q
Li I
U) f a
I Dcp 0
r CD CD m
CD CD CD CD CD CD CD UIQ
=
F-T a
.a a
UI3 0
0 CD oD CD
- l.
CD
- CD_,
UI UI (1)UI 9-CD V
UI U)
C) 02.
r-CD OUI rflCD 03 UI0 CD 0
CD CD 0.
CD U)
(CC p
<0--u CDCDC)
CD 0 CD CD CD
<2.
OCD CD 3
CD(D CDU) ao OCD UI CD 0
H CD (I)rtzp N)0-C/)
C)
CD
- 5 0) 0zp m
CD
- 5 z
p 0) 3 0)
Co CD N) 0
-C, N)
C..)
CD 0<
CD CYi CD
-D CDP Cn CD o c Co
-C,
-C c0) 0 o
Cl) 003(l)
(0:3?
CD i0 mo 0
- c-13<
0)
Io CD 0
I 0)
C.)
- 5 0.
(j)CD 0
CD 0-00)
III 0)
CD Co CD CD CD0 0
CD
-I 0
C, 0
(ft
-n 0
-I 3
m
-U 0
-u-l C)-I 02 m
1 C)
-4 02 (0
-40 z- -
0 CD CDI
-CD.
CD
<CD tn.
CD U)
U) mo 2 0 Qci.
0 0
0)
CD CD (VI 0
U)0.
0 (V
CD CD CC)
CD
-a
-o 0
(IC U)
(II If)
-4 I (Dx am
p.
l)
-,0 J_
c3 (ft ZCDv G)
CD (no CD0 0
CD o
03 o
m-o oO D
(D
(nO ro o
3 0
I F
QC)
<0 0)
CD M -
0)3 Dci
-U rn 3.
C)
C) 0 CD o
C)
C)
C)
C)
CD
=
o0.
(ft 0z iii
-1 o6) 0 rn C
ci z
z C) o CD U)C) mC) o 0
E CD CD
C) x C) 2 0
ii p
CD (DC CD 0,
-o
-o Y
ci
.D-5 C)
Co CO 0
cC)
CO 1
3 Cl)
N)
-u
-o Cl)
CD I
I
(*)
CJ C)
C)
(_
(_
CD H
00 ct H
3 jj Cl)
U)
CD n,
ni
ci ci ci ci H
Cl) o CC.
H C) 0 ci o
H ci I
ci p.
p.
QO)
C) y H
- o 00 Cii Cii 3
C) 0 9
9 Cl)
Cl)
<C) 0 00
-(DC-ft
-a
-o 0
0 m
CD i
C/)
0__
g i-n a
6)
Ci 2
CDÜ)
CD-urn 0
CD 01 CD Q_C3)
N)
_.o D
CD.
HD 0
CoCD N) o 0 (0 1
CD 0 0)
CO Ci) 0 CD o
oQ CDD
.o P
COD?
mo
-u<
rn ID) m-CD D)
Z
-0 P
0)
(1) coCD CD C)rn
-uD) 0 I
I;RD)
N)
Cl)
Ci)
CD 0.
CD
.0t CD0.
0 CD1 0
C) 0=
C)
D 0
a, w
w w
0 0
Q Q
U H
CD 1
Cl) 01 C)
CD OC)
C-)
Co 0
zo
C) o 0
zo o
6)3-
=
03 (DC0 000 CD C))
p.
HO C))
>0 (1)3 1C0 Do Co Z3.
Z Zo
-ti 0)0 CD Co
- 3-CD 0) 0.
Cl) 0
-D 0
0)
- 3 Cl-i 0
0
- 3 C,)
0 uJ CD
- 3-0) 0 F-P p.
F 32-11j C 00
-o0 Cn C)
C)=
ci°U) 0 0
D
?
zo
.g C) o a
CD r
Cii Z(
3
°° P
rCD C)cpC)
C)
CD CJC) og C
0 z
(D Z
a-CD g.
Z3-0 (pm C)
Z z
ci
-n 0
m Cl) 6
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-302 Scenario No.:
1 Event No.: 6 Page 14 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 7.
Verify Pump Operation a.
At least two high head SI pumps running a.
Manually start high-head pump(s).
BOP b.
Both RHR pumps running b.
Manually start RHR pump(s).
8.
Verify SI Flow a.
RCS pressure
- LESS THAN 1600 PSIG a.
Go to Step 9.
[2000 PSIG]
b.
High-head SI pump flow indicator
b.
Manually start pumps AND align valves to CHECK FOR FLOW establish an injection flowpath.
c.
RCS pressure
- LESS THAN 250 PSIG c.
Go to Step 9.
[650 PSIG]
d.
RHR pump flow indicator -
d.
Manually start pumpsQ align valves to CHECK FOR FLOW establish an injection flowpath.
9.
Realign SI System a.
Verity Unit 3 high-head SI pumps
- TWO a.
Perform the following:
RUNNING 1)
Operate Unit 3 and Unit 4 high-head SI pumps to establish injection to Unit 3 from two high-head SI pumps.
2)
Direct Unit 4 Reactor Operator to align Unit 4 high-head SI pump suction to Unit 3 RWST using BOP ATTACHMENT 1 of this procedure 3)
GotoSteplO.
b.
Stop both Unit 4 high-head SI pumps place in standby BOP Places the handswitches for the 4A and 4B HHSI pumps to STOP.
36
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 15 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 1.0.
Verify Containment Isolation Phase A Valve Perform the following:
White Lights On VPB ALL BRIGHT a.
Manually actuate Containment Isolation Phase A.
- b. E any Containment Isolation Phase A valve is closed, THEN manually close valve. IE valve(s) can 2I be manually closed, manually or locally isolate affected containment penetration.
11.
Verify SI Valve Amber Lights On VPB Manually align valves to establish proper SI ALL BRIGHT alignment for an injection flowpath.
BOP BOP 12.
Verify SI RESET Reset SI BOP 13.
Verify Containment Phase A RESET Reset Phase A 14.
Reestablish RCP Cooling a.
Check RCPs AT LEAST ONE a.
Go to Step 15.
RUNNING b.
Open CCW to normal containment cooler b.
Stop all RCPs valves BOP MOV-3-1417 MOV-3-1418 c.
Reset and start normal containment c.
Stop all RCPs coolers BOP If RCPs are running, then resets and starts Normal Containment Coolers.
37
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 16 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 15.
Monitor Containment Pressure To Verify Containment Spray NOT Required a.
Containment pressure
- HAS REMAINED a.
Perform the following:
LESS THAN 20 PSIG
- 1) E containment spray 2I initiated, PR-3-6306A IjJ manually initiate containment spray.
AND 2)
Verify Containment Isolation Phase B BOP PR-3-6306B
-ACTUATED.
3)
Verify Containment Isolation Phase B valve white lights on VPB
ALL BRIGHT.
4) i.E any Containment isolation Phase B valve did NOT close, THEN manually or locally isolate affected containment penetration.
5)
Stop all RCP5.
16.
verify Containment and Control Room Ventilation Isolation a.
Unit 3 containment purge exhaust and a.
Manually stop fans.
BOP supply fans OFF b.
Verify Control Room ventilation status b.
Manually align equipment for Control panel
- PROPER EMERGENCY Room emergency recirculation.
RECIRCULATION ALIGNMENT I
NOTE BOP Hydrogen Monitors should be in service within 30 minutes of a valid SI signal. They should be available in a timely manner to support decision-making related to hydrogen generation in containmenL a a a
a
I 17.
Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST BOP ACCIDENT MONITORING SYSTEM 18.
Verify All Four EDGs RUNNING EMERGENCY START any available EDG NOT running.
BOP 38
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 17 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 19.
Verify Power To Emergency 4 KV Buses and Load Centers a.
Check the 3A, 3B and 3D 4 KV buses a.
Perform the following:
ALL ENERGIZED 1)
Inform the Unit Supervisor that ATTACHMENT 3 is complete with the exception of the de-energized bus or buses.
2>
IF the Unit Supervisor decides not to energize the de-energized bus or buses, THEN go to Step 20.
BOP 3)
IF the Unit Supervisor decides to energize 3A, 3B, or 3D bus, THEN perform the following:
a)
IF 3A 4 KV bus de-energized, jJJj restore power to bus using 3-ONOP-004.2, LOSS OF 3A 4KV BUS.
b)
IF 38 4 KV bus de-energized, IHi restore power to bus using 3-ONOP-004.3, LOSS OF 38 4KV BUS.
c)
IF 3D 4 KV bus de-energized.
THEN restore power to bus using 3-ONOP-004.5. LOSS OF 3D 4KV BUS.
20.
Notify The Unit Supervisor That The PROMPT ACTION VERIFICATIONS Attachment Is Complete And Discuss Any BOP Safeguards Equipment That Is Not In The Required Condition 39
C,)
0 w0 (I)
Cl)
- o0 0
5;;
5;;
-I
-I C)
C)
H CD a
0 CoCo m
0 003 0
,I1Cn 00
-h Cl, ID-00 CD
-I CD CD Cl) w I-0 C) 0 01
-4.
0 (V
p.
p
£)
o 2
C)
C C)
D O
U) zz-m 2.
G)
- 0=
0 0
0 m
(3-otI O
C/)
Z 3*
0
(/)9.
-< E 2
=
- 0 t3 CD (3
((3 z
g-I 01 U)
D H
H m
0 Z
H Z
H CD
- 5 U) 0
- 3 U) 0 Cii) 0 C
CD C) (is CD Cl)
-D0 Z5 U)
CD U)
(0 (IA) m0
-P
çn
-o C)
CD
- 3 U)
C) 0
- 3 U) 01 w
CD
- 3-CD 0
U C) m 4
C)
O D
X*
CD
cDz
>z C
mo zo Z
- 9U)
CU, 0
rn5 c5 (1)0 QlJ cO z° Hm
z
-0 0
Nr Q
C)
H mm r-C
-n 0
H r-J m
mm F
ID C)
0 P0.
>0 ZD zm z
C) z C) E Z 9
0,
mm.(3.<
H m C) ro
>H ZU) -
U) m (3. C
. -IU) z.
CD(S)
- 3 EU) 220
-U-a U)
- 0 cC)
- 3:3 U)
CD (1)
U)
-I-CD
- 3 r.J 010 I
0
- 3 v-f-0
-4 U)
A) m0
-P
-I
-Il 00 0C -o CD (0
CD U)
CD CD
- 3 CDx -o CD (0
CD
-I, 0
-4
-h 0
Q 0C CD Q?
O:3 H
CD U)
CDC7iCD 0
W*
M o c (0
-h
-D CD E5 C
C)
CD 0CD
- 3
°cs-CD 5:3=
- 3.
00
-F*
0 Q) z
- C d D)U)Q mo 0-a<
m ID) m-CD cSCD CD a
I U)
(A)
CA)
C5l U)CD Ca oc CD 0
I-U mU) mU)
(A)
U)
CD x
CD 0
CD 0
C) 0 Cn 1
0 m
Cl)
I1 I
I H
I I
I I
I
-ID I
Q)
(ID I
CD I
I I
I jo H
I I
I I
I I
p-p DC) o o
o 0
U)
<V (1) 0 0
N-4 p.
p 00 o
0 o
o U)
(1)
(V (V0
((1 M
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 19 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior 3
Maintain Intact S/G Levels a.
Narrow range level
- GREATER THAN a.
Maintain total feed flow greater than 6%[32%]
345 gpm until narrow range level greater than 6%[32%] in at least one S1G.
b.
Control feed flow to maintain narrow range SRO/BOP level between 15%[32%] and 50%
c Narrow range level
- LESS THAN 50%
c.
Stop feed flow to any SJG with narrow range level greater than 50%.
narrow range level in any S/G continues to increase in an uncontrollec manner, THEN go to 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE, Step t 4
Monitor Secondary Radiation a
Direc: Nuclear Chemistry to take periodic activity samples of all S/Gs b.
Direct Nuclear Chemistry to check DAM1 SRO/BOP monitor reading c
Direct Health Physics to take radiation readings on main steamlines d.
Secondary radiation
- NORMAL NEAR d.
Go to 3-EOP-E-3, STEAM GENERATOR ROUTINE OPERATION VALUE TUBE RUPTURE, Step 1.
CAUTION SROIATC If any PR2 PORV opens beca use of high PRZ pressure, it is required to be verified closed or isolated after pressure decreases to less than the PORV serpoint.
5 Check PRZ PORVs AND Block Valves a.
Power to block valves
- AVAILABLE a
Restore power to block valves b
- CLOSED b.
PRZ pressure less than 2335 psi 0
SROIATC manually close PORVs. IF any valve can NOT be closed. THEN manually close its block valve.
c.
Block valves
- AT LEAST ONE OPEN c.
Open one block valve unless it was closed to isolate an open PORV.
SROIATC 6
Verify SI
- RESET 41
m CDam 3
O:5
-H CD 3
.ED q
CD CDC),CD
-Za CD mo 0c:5-0 (OCD
)
m 00(0
-I, -CD0 (I)5-C,,
8 2
C, D
- o-D)
=
CD 3
(ç)Q 0
CD z
f-I.
CD(fl C)
CD 0
o 0
mo CD ii<
m CD 0
m-(I)
CD C,
CD 0
-*01
-U CD
() 0 UCD 0
-h mw
-n 3
m C,)
Ci, I
F)
H 3
CD Cl) cn
- v 0
0 0
0 E
-I
C) 5; 5;
-I
-1 C)
C)
C)
C) 0)
-o C) 0 0
CD
- 5 00>
U0
.O 0<
D
.g c.
Cl)
(0 EE 0
Z9
EZ,,
0
0 Z 0 c
mc HD m
4 Cl) 0 0)
OH 0
0
00 H
0 H
H 0
W 0
I CD QO CD
£2 2:
g CD 0
o.
-o 0
I z
CD m
3
0 CD Cl) 0 5
_*r) z 0) 0)
0
>90
=
CtC J0 C))
.HI9 0
0 zQ.0 z
mo H
(P CD 0)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 21 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior SROIATC I I Check if SI Should be Terminated a
RCS subcoolng based on core exit TCs a.
Go to Step 12.
GREATER T[4AN 36F[Refer to Foldout Page Item 3 Adverse Value]
b Secondary heat sink b
IF neither condidor sadsfied, THEN go to Step ii Tota feed flow to intact SGs GREATER THAN 345 GPM OR Narrow range level in at [east one intact SIG
- GREATER THAN 6%[32%]
c RCS pressure c
Ga to Step 2.
Pressure
- GREATER THAN 1600 PSIG[2000 PSIG]
Pressure
- STAELE OR INCREASING d.
PRZ level
- GREATER THAN 17%j50%]
d.
Thj to stabilize RCS pressure with normal PRZ splay. (3o to Step 12.
e.
Go to 3-EOP-ES-Ii, SI Termination, Step I TERMINATION CRITERIA EXAMINER NOTE: The scenario is terminated when a SI Termination decision has been made or earlier based on the discretion of the Lead Examiner.
43
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 22 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior ATTACHMENT 4 (Page 1 of 1)
ESTABLISH CHARGING FLOW 1.
Verify CCW Flow Alarms To All RCP IF COW flow to ROPe thermal barrier is lost.
Thermal Barriers
- OFF perfomi the following:
A 1/I ROP THERMAL BARR COOLING a.
Verity seal return temperature for each WATER HI FLOW RCP to be less than 23e F.
AND b.
IF seal return temperature for each RCP
is less than 235 F, THEN go to Step 2.
A 1/2. RCP THERMAL BARR COOLING WATER HI TEMP c.
IF seal return temperature is 235 F.
THEN locally isolate seal injection to affected RCP(s) before starting charging A 1/3, RCP THERMAL BARR COOLING IVATER LO FLOW 3-297A for RCP A 3-2978 for RCP B 3-2970 for RCP C d.
WHEN seal injection is isolated to each affected RCP, THEN go to Step 2.
2.
Check Offsite Power Available jf offsite power s NQI available. THEN check diesel capacity adequate to run one charging pump. j. diesel capacity is Q1 adequate, THEN shed non-essential loads.
Refer to ATTACHMENT 3 for component KW load rating.
3.
Start One Charging Pump 4.
Place RCS Makeup Control Switch in STOP 5.
Establish Desired Charging Flow a.
Start additional charging pumps if needed a.
E offsite power is NQI available, THEN and ofisite power available check diesel capacity adequate to run additional charging pumps.
c.
Adjust Charging Flow To Regen Heat Exchanger, H CV-3-1 21, to rnamtain proper seal injection flow cI.
Verify charging pump suction auto transfers to RWST 6.
Notify The Unit Supervisor That The ESTABLISH CHARGING FLOW Attachment Is Complete 44
Appendix 0 Required Operator Actions Form ES-0-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 23 of 23 Event
Description:
During plant stabilization, Block Valve MOV-3-535 develops leakage with PORV 456 leaking. The crew responds using 3-EOP-E-0 and transitions to 3-EOP-E-1. RCPs are tripped with the loss of Subcooling Margin.
Time Position Applicants Actions or Behavior FOLDOUT FOR PROCEDURE E-1 1.
ADVERSE CONTAINMENT CONDITIONS IF either of the conditions listed below occLrs. THEN use adverse containment setpoints:
Containment atmosphere temperature 180F OR Containment radiation levels L3xI0 R/hr WHEN containment parameters drop below the above values, THEN normal setpoints can again be used IF containment integrated dose rate has not exceeded 10 e Rods.
2.
RCP TRIP CRITERIA a.
E all conditions listed below occur. THEN trip all RCPs:
- 1) High-head SI pumps
- AT LEAST ONE RUNNING SI FLOWPATH VERIFIED
- 2) RCS subcooling
- LESS THAN 25F[65F]
- 3) Controlled RCS cooldown is NOT in progress b.
phase B actuated THEN trip all RCPs 3.
SI TERMINATION CRITERIA IF all conditions listed below occur THEN go to 3-EOP-ES-1.1, SITERMINAT1ON, Step 1 a.
RCS subcooiing based on core exit TCs
- GREATER THAN 30T[See be ow Table]
SI TERMINATION ADVERSE SUBCOOLING VALUE RCS PRESSURE (PSIG)
ADVERSE SUBCOOLING VALUE
< 2485 AND 20C0 55 F
<2000 AND 1000 a85F
<1000 210F b.
Total feed flow to intact SGs
- GREATER THAN 345 GPM narrow range level in at least one intact SG
- GREATER THAN 6%132%j c.
RCS pressure
- GREATER THAN 1600 PSIG2000 psg] AND STABLE OR INCREASING d.
PRZ level
- GREATER THAN 17%F50%]
4.
SECONDARY INTEGRITY CRITERIA IF any S!G pressure is decreasing in an uncontrolled manner has comple:ely depressurized fl that S/G has NOT been isolated, THEN go to 3-EOP-E-2, FAULTED STEAM GENERATOR ISOLATION, Step t 5.
E-3 TRANSITiON CRITERIA j any S/G level increases in an uncontrolled manner OR any S/G has abnomal radiation, THEN manually start SI pumps as necessary and go to 3-EOP-E-3. STEAM GENERATOR TtJBE RUPTURE. Step 1.
S.
COLD LEG RECIRCULATION SWITCHOVER CRITERIA RWST level decreases to less than 155.000 gallons, THEN go to 3-EOP-ES-i.3, TRANSFER TO COLD LEG RECIRCULATION, Step 7.
RECIRCULATION SUMP BLOCKAGE RHR pump flow AND amps become erratic abnommliy low after recirculation has been established, THEN transition to 3-EOP-ECA-11, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step I 8.
CST MAKEUP WATER CRITERIA IF CST level decreases to less than 10%, THEN add makeup to CST using 3-NOP-0 18.0 I. Condensate Storage Tank (CST).
9.
LOSS OF OFFSITE POWER OR SI ON OTHER UNIT IF SI has been reset either ofisite power is lostQ SI actuates on the other unit, THEN restore safeguards eouipment to required configuration. Refer to ATTACHMENT 3 for essential loads.
10.
RHR SYSTEM OPERATION CRITERIA j RHR flow is less than 1000 gpm. THEN the RHR pumps shall be shut down within 44 minutes of the initial start signal.
45
CD 0.
C)
CD CC)
CD CD.
9 CD CD On
CC CD
-C CT C)
-D CD
<0
CD 0.
9-
-C CD
=
I I
00 c
CD
-o U)
U) 00 I
Cd)
U)
- )
I
-l m
U) 0.
CD9-cC_ -<
CCC)
CD CC)
CD CD (0
-D IL!
p-P
)?
z ii C
C, n
C))
CD CD CD
-C
-C
-C
)
CD U)
-C CD CD C)
-C U)
=
03 3,
CU) i2o U)
C-C o
CD U)()
0)
CD(
(0CD
<CT CD C
CD DC 0
0 o
)U) 0 3
rri9.
ZO 0
CD C
3 W
CD C
CD O
0 CD 0
o o
Ci)
Cl)
CD Cl) 0 0
C)
C.,)
HO C
CD<0 I
C.,)
C.,)
C)
C)
C)
T 0
0 W
> I r
I I
r r
N 00 C) 00 o C)
<CD 10 (C,
mo zC)
G)o.
ø.
0 0
(C)0.
C)
(0 CD CD U)C
-C-o
-C CT CD (C)
CD (C))
z rn 0
I
-a Jn 8 p
3-.
CD CD CDao CD H
-I F.
0 0
0)
CD
- 5 3
CD o
F.
D CD C)
C)
- 5-3 Cl)
CD C)
- 5 0
C-)
0
-D CD Cl) rfz 0
N)0 CD (0
CD 0
0)
CD
-I CD 0
CD CD F.
0 C,
I.
0 Cl)
H 3
CD a
0 w
w w
w 0
0 0
0 0
U
-o CD x
0)
CD0 CD Cl)
CD
- 5
-n CD CD I
P
-C-C 02 rn o 03 U)0 CC) 0 CD CD CD CD0 C-n U)
-tJ.+/-
9(.
00 CD CD CC)
CD 3
0 9
3 CDI-CCC I0C I3 U)
CD 00
-n 0
C)
CD
- 5 C, C) 0 Cl) 0 QJ CD
- 5-CD 0
C)
C)
CD
- 5 CD 0z p
m CD
- 5
-4zp 0)
-U 0
-U
-I, o
CCC)
Z CD
<m C,)
4 0z Cl)
-n 0
3 m
C,)
6
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 2 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position Applicants Actions or Behavior 4.
Verify Proper ICW System Operation a.
Verity ICW pumps
- AT LEAST TWO a.
Start ICW pump(s) to establish at least RUNNING two running.
b.
Verify ICW to TPCW Heat Exchanger
b.
Manually close valve(s). E valve(s) can ISOLATED be closed, locally close the BOP following valves:
PO\\/-3-4882 CLOSED 3-O-3i 9 for PO\\i-3t882 POV-3-4883 CLOSED 3-50-339 for POV-3-4883 c.
Check ICW headers
- TIED TOGETHER c.
both ICW headers are intact,I direct operator to tie headers together.
5.
Verify Proper ccw System Operation a.
CCW Heat Exchangers THREE IN a.
Perform the following:
SERVI CE I)
Start or stop CCW pumps as necessary to establish ONLY ONE RUNNING CCW PUMR 2)
Verity Emergency Containment Coolers
- ONLY TWO RIJNNING 3)
Go to Step 5c.
b.
CCVI pumps
- ONLY TWO RUNNING b.
Start or stop CCW pumps as necessary BOP to establish ONLY TWO RUNNING CCW PUMPS.
c.
- TIED TOGETHER c.
IF both CCW headers are intact, THEN direct a field operator to be the headers together.
d.
RCP Thermal Barrier CCW Outlet, d.
IF containment isolation phase B NOT MOV-3-626 OPEN actuated CCW radiabon levels are
- normal, RCP number one seal leak-off temperature is less than 235F.
I manually open MOV-3-626. IF MOV-3-626 can be manually opened.
direct operator to open MOV-3-626 locally.
6.
Verify Containment Cooling a.
Check emergency containment coolers a.
Manually start or stop emergency ONLY TWO RUNNING containment coolers to establish
- ONLY BOP TWO RUNNING.
b.
Verity emergency containment filter fans -
b.
Manually start emergency containment AT LEAST TWO RUNNING filter fans.
BOP Places the handswitch for the 3C ECC to START. [EVENT 8]
47
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 3 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position
[
Applicants Actions or Behavior 7.
Verify Pump Operation a.
At least two high head SI pumps running a.
Manually start high-head pump(s).
BOP b.
Both RHR pumps running b
Manually start RHR pump(s).
8.
Verify SI Flow a.
RCS pressure - LESS THAN 1600 PSIG a.
Go to Step 9.
[2000 PSIG]
b.
High-head SI pump flow indicator b.
Manually start pumps AND align valves to CHECK FOR FLOW establish an injection flowpath.
c.
RCS pressure
- LESS THAN 250 PSIG c.
Go to Step 9.
[650 PSIG]
d.
RHR pump flow indicator -
d.
Manually start pumps align valves to CHECK FOR FLOW establish an injection flowpath.
9.
Realign SI System a
Verify Unit 3 high-head SI pumps
- TWO a.
Perform the following:
RUNNING I)
Operate Unit 3 and Unit 4 high-head SI pumps to establish injection to Unit 3 from two high-head SI pumps.
2)
Direct Unit 4 Reactor Operator io align Unit 4 high-head SI pump suction to Unit 3 RWST using BOP ATTACHMENT 1 of this procedure 3)
Goto Step l0 b
Stop both Unit 4 high-head SI pumps AND place in standby BOP Places the handswitches for the 4A and 4B HHSI pumps to STOP.
48
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
1 Event No.: 6 Page 4 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position
[
Applicants Actions or Behavior 10.
Verify Containment Isolation Phase A Valve Perform the following:
White Lights On VPB ALL BRIGHT a.
Manually actuate Containment Isolation Phase A.
BoP b
IF any Containment Isolation Phase A valve is NOT closed, THEN manually close valve. IF valve(s) can NOT be manually closed,IE manually or locally isolate affected containment penetration.
11.
Verify SI Valve Amber Lights On VPB Manually align valves to establish proper SI ALL BRIGHT alignment for an injection flowpath.
BOP 12.
Verify SI RESET Reset SI BOP 13.
Verify Containment Phase A RESET Reset Phase A BOP 14.
Reestablish RCP Cooling a.
Check RCPs AT LEAST ONE a.
Go to Step 15.
RUNNING b.
Open COW to normal containment cooler b.
Stop all RCPs valves BOP MOV-3-1417 MOV-3-1418 c.
Reset and start normal containment c.
Stop all RCPs coolers 49
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
I Event No.: 6 Page 5 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position Applicants Actions or Behavior 15.
Monitor Containment Pressure To Verify Containment Spray NOT Required a.
Containment pressure
- HAS REMAINED a.
Perform the following:
LESS THAN 20 PSIG
- 1) j containment spray JjQ] initiated, PR-3-6306A THEN manually initiate containment spray.
AND 2)
Verify Containment Isolation Phase B BOP PR-3-6306B
-ACTUATED.
3)
Verify Containment Isolation Phase B valve white lights on VPB
ALL BRIGHT.
- 4) j any Containment Isolation Phase B valve did NOT close, THEN manually or locally isolate affected containment penetration 5)
Stop all RCPs.
16.
Verify Containment and Control Room Ventilation Isolation a.
Unit 3 containment purge exhaust and a.
Manually stop fans.
BOP supply fans OFF b.
Verify Control Room ventilation status b.
i1anually align equipment for Control panel
- PROPER EMERGENCY Room emergency recirculation.
RECIRCULATION ALIGNMENT I
NOTE BOP Hydrogen Monitors should be in service within 30 minutes of a valid SI signal. They should be available in a timely manner to support decision-making related to hydrogen generation in containment.
I
a 17.
Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST BOP ACCIDENT MONITORING SYSTEM 18.
Verify All Four EDGs RUNNING EMERGENCY START any available EDG jQJ running.
BOP 50
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-302 Scenario No.:
1 Event No.: 6 Page 6 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position Applicants Actions or Behavior 19.
Verify Power To Emergency 4 KV Buses and Load Centers a.
Check the 3A, 3B and 3D 4 KV buses a.
Perform the following:
ALL ENERGIZED 1)
Inform the Unit Supervisor that ATTACHMENT 3 is complete with the exception of the de-energized bus or buses.
2)
IF the Unit Supervisor decides not to energize the de-energized bus or buses, THEN go to Step 20.
BOP 3)
IF the Unit Supervisor decides to energize 3A. 38, or 3D bus, THEN perform the following:
a) E 3A 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.2. LOSS OF 3A 4K\\J BUS.
b)
IF 38 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.3. LOSS OF 3B 4KV BUS.
c)
IF 3D 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.5, LOSS OF 3D 4KV BUS.
20.
Notify The Unit Supervisor That The PROMPT ACTION VERIFICATIONS Attachment Is Complete And Discuss Any Bi..,P Safeguards Equipment That Is Not In The Required Condition 51
ILC-27 NRC Scenario #2 Event Description Facility:
Examiners:
Turkey Point Scenario:
2 Candidates:
Op Test.:
2011-302 US ATC BOP Initial Conditions:
Mode 1 100% nower at BOL.
Turnover:
Maintain 100% power.
Online Risk Green with B Train protected on both units.
Event Malf.
No.
No.
Event Type Event Description 1
N ATC TS LCO 3.5.1 was entered for 3B Accumulator level at greater than 6,820 1
N/A
gallons. Use 3-NOP-064, Section 5.2 to lower 3B Accumulator level to the (N) SRO normal operating band (6,552 to 6,788 gallons). After reached, the SRO exits the LCO.
l ATC VCT Level Transmitter, LT-3-1 15, drifts high over 7 minutes to divert water 2
TVB1 LCDV to the Hold Up Tanks. This requires manual operator action to reposition (I) SRO 3-LCV-1 15A to the VCT position. The crew responds using the ARP or 3-ONOP-046.4.
3 TVUTPMPA (C) BOP 3A Heater Drain Pump trips on high amps which require starting an (C) SRO additional Condensate Pump to support this power level.
l ATC The Master Charging Pump Controller, LC-3-459G, signal fails high. The 4
TFH2L9FH RO takes action to control the Charging Pump Speed Controller in manual (I) SRO and maintain program level per Enclosure 1 of 3-ONOP-041.6, Pressurizer Level Control Malfunction.
ATC Turbine First Stage Pressure Channel, P-3-447 fails low. ATC determines TFS1 MAML no runback. Rod Control is taken to manual per 3-ONOP-028 or 0-ADM-(ITS) SRO 211. 3-ONOP-049.1 is entered for mitigation. The SRO will address LCD 3.3.1 and 3.3.2. This channel is declared inoperable.
I BOP S/G Steam Flow Channel Fl-474 fails as is for A SIG. The A S/G Feed Reg 6
TFSI MWEA Valve does respond properly during power maneuver. Action is necessary (l,TS) SRO for manual control and/or swap channels. When discovered, the SRO will address LCD 3.3.1 and 3.3.2. This channel is declared inoperable.
(R) ATC Engineering reports 3B S/G Feedwater Pump High Vibration. SM directs a N/A (N) BOP 3-GOP-100 power reduction to remove the 3B S/G Feedwater Pump within (R) SRO the next hour.
TVFAHDR2 8
(M) ALL A common Main Feed Header break occurs, the crew responds to the TVFALN3 reactor trip using 3-EOP-E-0.
TAFK1 44 9
TAFK244 (M) ALL During the loss of Main Feed, a common loss of suction to all AFW pumps.
The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed.
TAFK344 (I) BOP 10 TFU100005 The Main Turbine fails to automatically trip. The BOP will take (I) SRD compensatory action to trip the Turbine manually.
(I) BOP The ICW to TPCW Heat Exchanger Valve, POV-3-4883, does not TFKC883A I SRO automatically isolate on a Safety Injection signal. The BOP takes action
while performing Attachment 3 of 3-EDP-E-0 to manually close the valve.
(N)ormal, (R)eactivity, (I)nsirument, (C)omponent, (M)ajor I
ILC-27 NRC Scenario #2 Event Description SIMULATOR SETUP INSTRUCTIONS 1.
Reset to IC-lI (100% BOL) or other IC with correct setup conditions.
2.
Place Simulator in RUN 3.
Open and Execute ILC27SCN2N.lsn.
4.
Ensure 3A SIG Steam Flow Channel Control Transfer is selected to FI-3-474.
5.
Ensure Channel Select First Stage Pressure Control is selected to CH4 YELLOW.
6.
Increase 3B Accumulator level to greater than 6,820 gallons.
7.
Store IC with initial conditions setup if desired.
8.
Trigger lesson steps:
SETUP
- LOSS OF AFW PUMP SUCTION SUPPLY insert TAFKI44 0.000000 delay=0 ramp=0 on=0 off=0 insert TAFK244 0.000000 delay=0 ramp=0 on=0 off0 insert TAFK344 0.000000 delay=0 ramp=0 on=0 off0 SETUP
- MAIN TURBINE FAILS TO TRIP insert TFU10005 TRUE delay=0 ramp=0 on=0 off=0 SETUP
- FAIL POV-3-4883 AS IS insert TFKC883A TRUE delay=0 ramp=0 on=0 off=0 9.
Provide an in progress procedure of 3-NOP-064, Safety Injection Accumulators.
- 10. Place Simulator in freeze.
- 11. Provide Shift Turnover Checklists
- 12. Perform Simulator Operator Checklist
- 13. When ready to begin, place Simulator in RUN.
2
ILC-27 NRC Scenario #2 Event Description FACILITY OPERATOR INSTRUCTIONS EVENT I TS LCO 3.5.1 was entered for 3B Accumulator level at greater than 6,820 gallons. Use 3-NOP-064, Section 5.2 to lower 3B Accumulator level to the normal operating band (6,552 to 6,788 gallons). After reached, the SRO exits the LCO.
EVENT 2 VCT Level Transmitter, LT-3-1 15, drifts high over 7 minutes to divert water to the Hold Up Tanks. This requires manual operator action to reposition 3-LCV-115A to the VCT position. The crew responds using the ARP or 3-ONOP-046.4.
When directed, Trigger EVENT 2
- LT-3-115 DRIFTS HIGH.
insert TVB1 LCDV 1.000000 delayo ramp=420 on=0 off=0 SM
- If directed, respond and acknowledge the failure of LT-3-1 15.
- If directed, respond and acknowledge the failure of LT-3-1 15 and to write a PWO for troubleshooting.
EVENT 3 3A Heater Drain Pump trips on high amps which require starting an additional Condensate Pump to support this power level.
When directed, Trigger EVENT 3
- 3A HDP TRIPS ON HIGH AMPS.
insert TVUTPMPA 1.000000 delay=0 ramp=1 20 on=0 off=0 SM
- If directed, respond and acknowledge the failure of 3A HDP.
- If directed, respond and acknowledge the failure of 3A HDP and to write a PWO for troubleshooting.
EVENT 4 The Master Charging Pump Controller, LC-3-459G, signal fails high. The RO takes action to control the Charging Pump Speed Controller in manual and maintain program level per of 3-ONOP-041.6, Pressurizer Level Control Malfunction.
When directed, Trigger EVENT 4-MSTR CHARGING CONTROL LC-3-459G FAILS HI.
insert TFH2L9FH TRUE delay=0 ramp=0 on=0 off=0 SM
- If directed, respond and acknowledge the failure of LC-3-459G.
- If directed, respond and acknowledge the failure of LC-3-459G and to write a PWO for troubleshooting.
3
ILC-27 NRC Scenario #2 Event Description EVENT 5 Turbine First Stage Pressure Channel, P-3-447 fails low. ATC determines no runback. Rod Control is taken to manual per 3-ONOP-028 or O-ADM-21 1. 3-ONOP-049.i is entered for mitigation. The SRO will address LCO 3.3.1 and 3.3.2. This channel is declared inoperable.
When directed, Trigger EVENT 5
- PT-3-447 FAILS LOW.
insert TFS1 MAML TRUE delay=O ramp=O on=O offO SM
- If directed, respond and acknowledge the failure of PT-3-447 WCC
- If directed, respond and acknowledge the failure of PT-3-447 and to write a PWD for troubleshooting.
FS/TO
- If directed, respond and reset AMSAC by Trigger EVENT 5
- RESET AMSAC insert TCL4RST TRUE delay=O rampO on=O offtO EVENT 6 S/G Steam Flow Channel FI-3-474 fails as is for A SIG. The A S/G Feed Reg Valve does respond properly during power maneuver. Action is necessary for manual control and/or swap channels. When discovered, the SRD will address LCO 3.3.1 and 3.3.2. This channel is declared inoperable.
When directed, Trigger EVENT 6
- SG FLOW TRANSMITTER SB-FT-474 FAILS AS IS.
insert TFS1 MWEA TRUE delayO ramp=O on=O off=O SM
- If directed, respond and acknowledge the failure of FI-3-474.
- If directed, respond and acknowledge the failure of FI-3-474 and to write a PWO for troubleshooting.
EVENT 7 Engineering reports 3B S/G Feedwater Pump High Vibration. SM directs a 3-GOP-i 00 power reduction to remove the 3B S/G Feedwater Pump within the next hour.
When directed, call as Shift Manager and report, Engineering has completed a walkdown of the secondary system. They have reported 3B SIG Feedwater Pump has high vibration. I am directing you to reduce Unit 3 power to 50% using 3-GOP-I 00 and remove the 3B SIG Feedwater Pump from service over the next hour.
- If directed, acknowledge power reduction.
- If directed, acknowledge power reduction for the removal of 3B S/G Feedwater Pump.
SYSTEM DISPATCH
- If directed, acknowledge power reduction to 50% for the removal of 3B S/G Feedwater Pump.
ENGINEERING
- If directed, acknowledge power reduction to 50% for the removal of 3B S/G Feedwater Pump.
CHEMISTRY
- If directed, acknowledge power reduction to 50% for the removal of 3B S/G Feedwater Pump and to sample the RCS for the power change.
4
ILC-27 NRC Scenario #2 Event Description EVENT 8 A Main Feed Header break occurs, the crew responds to the reactor trip using 3-EOP-E-0.
When directed, Trigger EVENT 8
- MAIN FEED HEADER BREAK WITH SGFP BKRS TRIPPING.
insert TVFAHDR2 1 delay=0 ramp=0 on=0 off=0 insert TVFALN3 1.0 delay=0 ramp0 on=0 off=0 insert TFFI DIAT TRUE delay=1 20 ramp=0 on=0 offz0 insert TFF1 Dl BT TRUE delay=1 20 ramp=0 on=0 offz0 When directed, Trigger EVENT 8
- PAHMS.
insert TAC2VO2A 1.000000 delay=0 ramp=0 on=0 offz0 insert TAC2VO2B 1.000000 delay=0 ramp=0 on=0 offz0 insert TAAAV21 1.000000 delay=0 ramp=0 on=0 offz0 insert TAAAV22 1.000000 delay=0 ramp=0 on=0 off=0 insert TACAOO5.000000 delay=0 ramp=0 on=0 off=0 EVENT 9 During the loss of Main Feed, a common loss of suction to all AFW pumps. The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed.
FSITO If dispatched to investigate loss of Auxiliary Feedwater, the operator will respond they cannot enter the Aux. Feedwater Cage Area due to steam in the area.
EVENT 10 The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually.
Conditional Trigger EVENT 10-MANUALLY TRIP MAIN TURBINE.
Condition: IMU1 PR4Q insert TFU1 0005 0 delay=0 ramp=0 on=0 off0 EVENT 11 The lOW to TPCW Heat Exchanger Valve, POV-3-4883, does not automatically isolate on a Safety Injection signal. The BOP takes action while performing Attachment 3 of 3-EOP-E-0 to manually close the valve.
Conditional Trigger EVENT 11-ALLOWS MANUAL CLOSURE OF POV-3-4883.
Condition: 1MK28830 dellA TFKC883A 2 delay=0 5
ILC-27 NRC Scenario #2 Event_Description SCENARIO QUANTITATIVE ATTRIBUTES Target Quantitative Attributes (Per Scenario; See Section D.5.d)
- 1. Total malfunctions (58) 5 2.
Malfunctions after EOP entry (12) 2
- 3. Abnormal events (24) 4 4.
Major transients (12) 1 5.
EOP5 entered/requiring substantive actions (12) 1 6.
EOP contingencies requiring substantive actions (02) 1 7.
Critical tasks (23) 2 CRITICAL TASKS 1.
Manually trip the Main Turbine prior to Step 5 of 3-EOP-E-O as read by the Unit Supervisor.
2.
Initiate feed and bleed cooling so that the RCS depressurizes sufficiently for HHSI injection flow to occur prior to completing Step 16 of 3-EOP-FR-H.1.
6
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 1 Page 1
of 4 Event
Description:
TS LCO 3.5.1 was entered for 3B Accumulator level at greater than 6,820 gallons. Use 3-NOP-064, Section 5.2 to lower 3B Accumulator level to the normal operating band (6,552 to 6,788 gallons). After reached, the SRO exits the LCO.
Time Position Applicants Actions or Behavior Observes high 3B Accumulator level.
High 3B Accumulator level above Tech Spec limit SROIATC Drains 3B Accumulator level by 3-NOP-064 Exits Tech Spec limit 5.2 Draining Accumulators SROIATC NOTE This Section allows one or more Accumulators to be drained to reduce level or pressure or for draining in preparation to increase boron concentration.
SROIATC 1.
CHECK RCDT available to receive discharge from Accumulators.
NOTE a
MODES 1. 2, or 3 with RCS pressure greater than 1000 psig. Technical Specifications require Accumulator levels between 6520 and 6820 gallons:
SROIATC however, to account for possible instrument inaccuracies, the required range has been administratively established at 6552 to 6788 gallons.
a Technical Specifications require Accumulator pressures to be maintained in the range of 600 psig to 675 psig.
2.
IF in MODES 1.2 or 3 with RCS pressure greater than 1000 psig, AND Accumulator will be drained to less than 6520 gallons, THEN ENSURE the remaining two Accumulators are OPERABLE with:
Water levels between 6552 to 6788 gallons.
Nitrogen pressure between 625 to 665 psig.
SRO/ATC 1
1
H 3
CD Cl)
Cl)
Cl)
Cl)
Cl)
- ti Cl) 0 0
0 0
0 E
I
C.)
0 I
H
-1
-1 C)
C.)
C)
C)
C) 0
-a CD Cl)
C)
Cia) 03 01 N)
C)
C)C C
CD 0-Ui 91 CD
- 3 (D
C,)
r)0C 3C 0) 0 I
ni z
-o C)
CD
- 3 Cl)
C) 0 (I) 0
-I LJJ CD
- 3-CD 0
w U,
()<0 0
&jj j
(
-Um 0
CD 0
0gCPz Z
o2 0)0 3
0 7
U)
2 CU,-
0 C:
OG) m-CD
.-0 m3 0
CD U.
C)
- 3 1
z1
- i
- CDU, 0-D CD C
H 0
U1 fl H
O>o (flo (D
m u
z m
0
-nm
-0
- u z
01 0
1 CD CD CD CD N
CD Cl)
(I)
CD-o C/)z CD
- 30 0
0 CD C
Cl)
CD0
-h 0
C)
C)C 3
CDa-0 00 C,)
ID 00 3
C CD a-0
- 3 a
CD CD (P
- 3z 0) 0)
(1)
I-0 (0
01 =
CD 010 D
a a-l) 0,
CD
-j CD (0 Z0 CD
- 3 00)
CI)0 CDC)
- 1 a
-CD° CD C) 01 CD CD Ci)
CD a-D 0 -
(D 3o CDCc Oo C
(Do
0)
CD
- 3 30) 0
9) 03 CON) 00 0)
- 3 0
-o if CD (I)az p
N)0
-A 0)
C)
CD
- 3 CD 0z p
N) m CD
- 3 az 0
-a CD(a CD N) 0
-4, U,
CD 0
00)
ZC,)
mu) 0)0)
(0 P
0)
Z1 0C)
-o LZ CD 0
>(
CD
-Q 0.
CD CD
..I.0.
a-,.
0 (ft 1
0-,
3 m
Cl)6
)
- 0) Z_.
0 0
0
(,)
(,)
(.)
0) 0)
(0
&)
Ui 01 01 N)
N)
N)
N)
C,)
()
(,)
0*ID CC,.)
C)
C) 0 o
0 C) 0 c
C C
C C
C r
I I
(P-i H
H H
o 0
0
- a
- I o
ci ci
.a) a
- u D
((0
?
z 2:
z ir 3i CD 0
C 0 3D0 a-(I)
H
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 1 Page 3 of 4 Event
Description:
TS LCO 3.5.1 was entered for 3B Accumulator level at greater than 6,820 gallons. Use 3-NOP-064, Section 5.2 to lower 3B Accumulator level to the normal operating band (6,552 to 6,788 gallons). After reached, the SRO exits the LCO.
Time Position Applicants Actions or Behavior C.
IF using alternate Accumulator drain path, THEN:
(1)
IF Accumulator is to remain pressurized as water level decreases, THEN REFER TO Section 4.2.4.
(2)
IF Accumulator is to be vented. THEN REFER TO Section 4.2.6.
SROIATC (3)
DIRECT Chemistry to drain 35 Accumulator per 0-NCZP-064. Obtaining Accumulator Samples.
(4)
WHEN desired level or pressure is obtained per Plant Curve Book, Accumulator Level or Accumulator Volume Verses Pressure Graph, THEN DIRECT Chemistry to terminate draining per 0-NCZP-064, Obtaining Accumulator Samples.
SROIATC 0.
LOG 35 Accumulator final level in Narrative Log.
CAUTION SROIATC Chemistry sample results are required within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> by TS 4.5.1.1.b. after each solution volume change of greater than or equal to 1% of tank volume.
E.
IF 3B Accumulator was drained due to in-leakage, THEN:
NOTIFY Chemistry to sample the Accumulator.
(2)
LOG time Chemistry was notified in Narrative Log.
SRO!ATC Realizes Step 6 is N/A and to be used for 3A Accumulator.
7.
NOTIFY Chemistry to sample Accumulator(s) for boron concentration.
SROIATC 8.
ENSURE Chemistry samphng results for the Accumulator has been entered in the Unit Narrative Log.
3
(0 0)
Co E
° Lii (0
LL a,
(0 U) cU) 0)
2° a,
G) 0 (0
I Th c
Co 0
t7)C 0
(U 4-I 9
S a,
00 0
0 0+..
C-)
o L
(ft a,
a, a,
a)
Z (ft 9
0
>2
- 0
-g 0
w 9>
(aa) ti E_
U)
(U C
0)
.2 0
a, 2;
(U 5
o 2
0 0
a, 00 a,
I-.
0 c
0
.2 o
0 D
0 a,
U)
(U
.C C
.0_0 0
3 a,
0)-
E CU
.12 a
>0) a, z
c 1) 3 0
U)
Co 0
U)
C co mo
- 2 C
C/)
_j-
..!°
-CCw C.)0 0<
U)0 Q(U Cx 0
OW 0
(N OZO)
X 0
Q o
Z Z
C U) wZ L()
U)
LU
c1 Q
U) w EI0 U
U, 0
4..
C.)4 0
a) 0
- 3 0*
0 x
G) 0.4 c0 U)>
U)
U)
U)
E F-I0 0.
c I.()
U) 0 (Y)
I
-E c0 Co
-C C)
- 5
-2 (N
U)
Q)
(1)
H 0
H
.9j 0
4-c_)
4-4-,
o U)U)
-C t4 U)
>4-0 U)
.9-J (N
N-I_O o
Z U)
O c0..
U)>
w 0
t c9
- c o 00 L() U)z
- 0 I
4 (N
()U)C)
I I.
o
- jQ z
o U)w c
U)
EcU) c U) 0 o
c 0)
C/)
EU).9 HU)
- D U)D
> 0 U) w1 U) 0
_J I
(N o
oc (N
U) o oQ-Z DH D2 ci) 4-ZOO H
CI2 I
U)
U) o_
o Wo.
0 U,I U
c U)
C?
I-
-J Fzw>
U;J Izw>
a 0.ii 4..
Q U,
0 O
C0 a
I..
ci
- 0) c I
o.
w Oo
- 0 L.00 U
4..
0w 0)
U) 0 0
U) 00 0) 0 0)
CU)
U) w I0z 0 00 (U.C L()...
0 IL 0Cd)
U)
C)
U)
C,
__I >
0H H0>
0 IL.I w>
0 0
-J 4:
It) 00
_juj
-Jo 0>
zo I-c 0) itjO 4-
-C<
u,H
-J L)
-J
- 3 0
a)
U)0
-o0 0
HO
_J
_i 0
-J.
uJ0)
U) 0.i,
>.J
-C 0)
C) c.
0
_J_
(C w.2>
o ci F-0>
U)
-c 4-c
-c C-)
4-U)
C (5
-c 0
.U)0 (U
0.
-oC U) 0)
-C
-c U)
U)
CU
-C IC)
-J Cl)
NO U)U)
C U
C C
2 0
U C.
.00 C
IC 2
C
, 2.0
.2 (1)1-2 U U c -
U,w U)
U 0
U)
-ca) 0 U)c0 0
U) 4C U)
C) 00 C0 4-(000 U) 2 H
4:a>
C0
-Jw>
Lii
-J 0
4:0) z-J 00 4:0
-j4:
OX wo I0.
C)z0 I
C-)
4:
0 I-.
4:
w00 0
C.)
C.)
C.)
C.)
C)
C.)
0 0
0 0
0 0
a U)
U)
U)
U)
U)
U)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 2 Page 2 of 3 Event
Description:
VCT Level Transmitter, LT-3-1 15, drifts high over 7 minutes to divert water to the Hold Up Tanks. This requires manual operator action to reposition 3-LCV-1 1 5A to the VCT position. The crew responds using the ARP or 3-ONOP-046.4.
Time Position
[ Applicants Actions or Behavior 2.
IF VCT has an actual HI level, THEN:
SROIATC A.
ENSURE LC-3-1 12, VCT LEVEL CONTROLLER setpoint is between 37% to 40%.
B. CHECK LCV-3-11SA diverts to the HUT according to \\!CT level program.
SRO!ATC NOTE LCV-3-1ISA fully resets at 76%
SROIATC C. ENSURE LCV-3-115A fully diverts at 86%.
D.
ENSURE proper charging and letdown flow balance.
3.
IF \\JCT has an actual LO level, THEN:
A. WHEN VCT level lowers to 4%. THEN ENSURE charging pump suction swaps to the RWST, with LCV-3-115B, RWSTTO CHARGING PUMP SUCTION, OPEN and SROIATC LCV-3-1 15C. VCT OUTLET ISOLATION VALVE, CLOSED.
B.
ENSURE auto makeup rate is greater than charging flow.
C. ENSURE suction source swaps back to VCT at 11%.
SROIATC 4.
IF LT-3-1 12 or LT-3-1 15 have failed, THEN REFER TO 3-ONOP-046.4, Malfunction of Boron Concentration Control System.
SRO 5.
REFER TO Tech Spec 3.1.2.1 and 3.1.2.2.
SRO Enters 3-ONOP-046.4, Malfunction of Boron Concentration Control System, for additional actions.
EXAMINER NOTE: The crew may have entered 3-ONOP-046.4 directly which is an acceptable flowpath.
SROIATC I
Check Boric Acid QE Primary Water Makeup Observe note prior to Step 28 and go to Flow Rates - ABNORMAL Step 28.
NOTES I
LT 112 and LT 115 share a common wet variable leg and a common d reference I
RO/ATC I
leg.
A false high level will be produced if the common dty reference leg fails.
I Steps 28 through 38 assume stable charging and letdown flow; therefore, a transient I
could mask the symptoms being used to determine which level transmitter has faiied I
L_______._._.__J 6
H CD CO CO Cl)
Cl)
CO CO CO U) 0 0
0 0
0 0
0 g
-I
-I
-I
-1
-1 C) 0 C)
C)
C)
C)
C)
C-)0 G) 0
-I 0
U)
CD
- 0 m
zm z0
-Im 0>
0 CD 0-,
CD CD o
- s -.
00
<C)
CD -
CD 0 U) 0 U)
U)
CD 0
- 3-CD0 0
U)
I-CD U)0 m
U)
- 5 CD U) 0 CD 0
- 0 CD O a>
0=
CD
-I E.
0.,
-3 D
CD CD CD 0
C0.
9-C CD XICD CD io 09 Zo
-rlZ C
0 0-CC) 0 CD CDj 1
DC 0
CD:
C/)
CD 11 mz
<0 CD DC 040 0
CD OD 00 C
- 0 CD 00
-4 0
0 4CC 0
3 CD 0
CC)
C:
0 CD CD0 0
0 CD
çC C:
0 C
C)
CC, CCC CD CD 3-0 CO C:
C, CD 0
N 3-0
- -1 0
rn t3 0
U):
Co 0 0
- 5 U) 0 CD
- 3-U) 0-
-I, C:
3-0 C
CD C-.
C)
CC, 0
- 4-CIC C)
C,)
- 4-0 0
CC):4 (0
o_
C- 0 o
CD
-40m o
44 L. -n o vi 0<
00
-CC)n o
<CD-fl CCC
o C.)
2
<-l.a 4:3 C)
- 4 2:>
?.
O o
C-S n
C) crO C.)
<40I y
CD 0
40 j
CDSo S CD CD on rn Hrj o
oZ
>0 0
C rn 40
-nC C
C-r I
on<
U)
CD 00 HCU)
CD CD 0
.U)..
CD H 0
0 (0
N;
- 5 Co U)
D
- 5-U)
CDD_*
U)
CD tJr I
LI ZU) 0-i C 0tQ 0)
- 3-0 d
CD 0
3 I
-I U)
A 0
>0
.4-0 CD CD 0
-a CD U) z 0
N)0-(I) 0 CD
- 5 U) 0z p
N) m CD
- 5 Z p
- 3 U)co CD CD) 0
-I, CD) 1%)
00
-Tic)
CC)
C Oo CC, 11<
.I 0
n CD C-01 0
I I
4.)
cn 0
0 0
C)
CD
-o C.)
z 01 I
CDza x
CD a-0
-c CD I-I.0
-I C,
4.4.
0 Cn
-n 0
-I 3
m (is,
Co
- u0 w0
-U w0
-U Co 0
w0
-U w0
-U Cou2w0
-U Cou0
.-.w0
-U Co U0
..w0 U
H 3
CD Cl);0
..w0
-U U
U CD a.
x ci (I) 2 w00 0
C,)
0 D
OD 0-om
-I0 C.)
I 0z CO 0) 0 C,)
0 Ci) 0 0.0 0
0 D0.
CD
- 5 (I) 1)
I-CD
-a C3
-p
- D,
-1 z
CD CO C) 0 0
CD CD (CD (CD DC)
D 00
- 0 CD C)
CD D
mz(nC m
0)
C:
0 3
0)
C)
Cl) 0)
0-.,
0 CDI E1 C)
Cl)m (CD 00 CD 0
I 0>
m DZ
-T1 DO
-D Z
30 D0 C)
DC) 0 D
(CD 0
D C)0 D
((C0 DC 0
C C)
CD0 0
- 5 H
-5 cT CD 0
0)0.
0) ci)
CD C)
CD Ci)
C,)
0) 3 0)
- 5 4.
0)
- 3 CD (I)
C,)
-4.
- 3-0)
Z5 000 0
00 0
CD CD0 0
13
-o 00)
- 5 U) 0 0
- 3 (0
0
-5 CD
- 3-0) 0 1
F) o
>j C) j CO E
CO, I m
0 (DC c
D C)
CO C)
-o o
COD 0
3
-D CD 3 CD CO D
((Ccl)
CD D
D CD
C)
ZcC)
D CO
-iJCO D
0
-U
-D
!Q.
CC) 0
H 1
C))
CO 0
mz rnciC C-)m I
0 0)
-53 Co OD 0)
- 50 0i (A)
CD CD C) 0D 0
CD CO CD c2 CO D
CO 0
CD C)0D0.
CO>
CD CO B
DC)
(p C)0D0 CD0 CO CD U
CD CD (I)
C)
CD
- 5 0) 0z p
C/)
CDCD H<Ti C
2.
CD 0
00 0oO 0.*
CD.
<4-4.
II
- 0 k)Cfl 0(fl 00 0(0 0
- Il-U 0
mz
-I CA)>
ci
-o
-I
-o Co 0z C)z
-U Co 0
ci 0
CD CD Cl) 1 0
- 5 Ca 0) 30 Co 0
- 5
(.4) om 0
0<
-o
- 5CD I
1 CD-CD Do
ØCD 0(0 Z
P 0>
(A)0 CD 0
CD U)
-o D
CD 10 0
0
- 3
- 3-CD
- 3-0) 3
-o (0
- 3-0
- 3-
.0 CD 0
U)
- 5
-a O
CD
- 5 O
01 0
M U)
CD CDa.
0
-o CD 0
C) 4-4.
0 Cl) m CD
- 5 zp C))
Ic, L
0 rD 0
-u 1
0 3
m Coo r*J
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 3 Page 2 of 2 Event
Description:
3A Heater Drain Pump trips on high amps which require starting an additional Condensate Pump to support this power level.
Time Position Applicants Actions or Behavior EXAMINER NOTE: If Engineering is contacted, they will recommend maintaining full power operation with an engineering walkdown to monitor secondary performance. This condition will feed into Event 7 where 3B SIG Feedwater Pump is running with high vibration. If the crew decides to reduce power in accordance with the table, then proceed with Event 6 with SIG Stm Flow Channel Fl-474 failed as is.
4.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, PERFORM of the following:
A.
ENSURE minimum heater drain pump operation as required by table below using 3-OP-081. Heater Drain Pumps, or3-OP-081.1, Feedwater Heater Extraction Steam Vents and Drains Valve Alignment.
5.
OBTAIN Engineering concurrence to maintain full power operation.
SROIBOP C.
REDUCE power as required by table below using 3-ONOP-100, Fast Load Reduction.
Turbine Load HDPs Required Above 450 MWe Two 300 to 450 MWe One Oelow 300 Mwe None SRO,BOP 5.
CHECK HDP locally for abnormal indications and HDP Breakers 3AA07 or 3AB03 for I
targets.
EXAMINER NOTE: After power reduction is addressed or at Lead Examiners discretion, then proceed with Event 4.
9
0 C.I Cl)
Iii E
0 U
U)
C0 4-C.)
0 4-CuIa)0.0 a) x
-VC 0.
0.
0 Cu 0
-CL...
I0)
.0 ci)
- g 0)
Cu Cu
.4-,
L1 Cuc C 0 C)
- 0) C C
-ct
ØCuCu 0
Cu C
C U) ci) o C j CC)
(1) 0 N
(
0
- U)
C0c,)
6
.g L.
U)
Cu 0
o
.cE I
C/)
Cu VcZ o0 Cu
- Icv,
_C L
)..
r 4
C0 o
(N j 0 5CC 0.2W U)
I-;-
00 Q
o a) 0 0
C-)
0.
E ZT0.
0)
C 0) a)
-c0 C) a)
E a)
-c
-UC a) a)
0 C00 ci.
E
- 7 ci.
0)
C U) a)
-c0 CO
- 7
-U
-UC 0
a)
-C0
(-I p
U D
1)
=
- Q c-U)w (1)
- 7 C-)
-J0 Iz0 C.)
Qz (9
- i:
C.)
lx co
?
Zn 0
0-Il U)>
4--
00-o Cw U,
wF 0
t 4-a)
I...
U) 4-a) 0-i
.ø Cu 0)
UIf)
C) l-J 10) 1-2 (50.
- -0 C
(00 0>
-U
-U)
(Uc1
-CI-
- 7:7 (1)0 (00 z0iz -
E a)
-C LL0
=IJ I
ci:
ft:
-J waor uj
- ci.
(00 2>
- 3.
Co u
0 t
J C
c
-i U) -
(0cc
CI-2 z 2
E = -0 0
0
0 G)
C (0>
U)
O-_
U)
-J
-j 4
C
- 7 Co _
C C)
U)
U)
U) 01)t c6 o
- 7 i-2
-ci-C)
C) cL cL o
0 Z
U)>
Z 0 :
0 b-s
(
o w
0 I- -
I-o 0
(3 0 a).L
< L (N
(0 0
0.)
C a)
-Q 0
E (0
I
-C a)0
>0
)
a) 0 0:7
-0.!Q 5a)-
a a
0)
C U)
Cu0)
C.)
C 15 00(/)
00 (N
C))
0
EI
.4-0)0).-
CC Cu Cu
.C C
00<
C0
.4-,
Cu
[
L 0)
C 0
U) U)0 a)
U) 0 0
UI U)
L..0 U)
C0
-I-,0 U) 4-,C Cu0 0
ci:
C
.4-,
U)0a U) 2 F-z0I ILz0 C-)
ci:
I
.cE C)
C)
C) 0
0 0
0 0
0 lx lx lx lx lx Cl)
Cl)
Cl)
Cl) 0
_?.
I Dcc p
0
I E-Q 03 I
02 030j 0
-_jt P
I 03S33 0320 I
03 03 p
I (0Co.
030 0)
I 0.)
U) 10 C
)<-:
Q3p u
rT (o
uo Ii-j O
T-° I
H I
I p,__><-
03 030)
I
-g I
1 0
_0 I
H C)
S!
-0 I
-0s E
I 0)
H c P0)
I HI S
11.;
Q C)w E10 U
U)t0 C.)
0 Cu 00.0
- 0ciI ci) 00.
0.
0)0 0)0 0
z0.
I ;E[
1,)
T?
I
- H
p r
.0)0 0
iL!1 J 0).0
-0.,0)c
)7 pL
_50
-z;0 0)
!4 jI 0p0 gc) --I
-e i P
Cl IL) o In 0
9-U)
O CL.
1-0)
.0 CI)
.2 0)
.C.
U)0 U)
C C D C.)
!2c C
.U)U)
U)
O)C 0
Lf)_
.4-.
(Y)
C CI) 0.
__j uJ
- F; 0
C j CQ )
0 N
(
(N Qci)
U)
COj) 0 2
D)E
- L CD 0
L
çj C/)
4 U)
.1
øQQ U)
I (0)
(0)
_C 2
CQ o
(N C.)
U).2W UU)U)
(1) 4 U)
I
-I-,
(CI DC U)
C
-U ci)0 U)
D 0)
L() o (0) C 4.-
-U) 00 C
O --.
0.9 U)
EDCI)
Cl)
.5 ci)
U)ø G)CU
-I-,
U) 0) ci)
- C F-U)
- 0 U) ci) cci I0 U)C0
-I Ci U).C U)
C.)
0 a
C 4-z 00)
U)C 4-x0 0
-C 4-C0 Co CI)
I-
=
U)0 C-)
Cw wI0z wz w
c_)
C_)
C.)
C.)
I-I-
I-I-
Co2 0
0 0
0 U)0 D_
U)
Cl)
U)
Cl) ci)
E F
Appendix 0 Required Operator Actions Form ES-0-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 4 Page 3 of 3 Event
Description:
The Master Charging Pump Controller, LC-3-459G, signal fails high. The RO takes action to control the Charging Pump Speed Controller in manual and maintain program level per Enclosure 1 of 3-ONOP-041.6, Pressurizer Level Control Malfunction.
Time Position Applicants Actions or Behavior ENCLOSURE 1 (Page 1 ofi)
PRESSURIZER PROGRA1MED LEVEL
% of PRZ Leve{ Span 50 45 40 35 30 25 20 545 550 555 560 565 570 575 Tavg °F EXAMINER NOTE: When Pressurizer Level has been stabilized or at the Lead Examiners discretion, then proceed to Event 5.
12
C;1 C
Cl) w 0
LI..
0 0
4-C.)
0 4-I...
U)0.0 a.
U) x
- 0 a)0.
0.
0 a)
--00 0)
Ci) a)
t3Q
- 0 z
HZ ci) a)
C-)
LO o
N-Z ci<N
C 0
Cl) c?i_cc)
LU
-5cJ C
CQ-c a)
_C C)
QZ 0
(N d
OL..(j)
(i)U)U) 0QU) 3
.2 a..-o 3-..
-o a)
CI)
C 0) a)
a) rn 0Q Wwu) a)a)a)
C C-o (Y)
D 0
rQ
C a) o O0)
(N 0z o
O,.L Z
U)IJ ci)
U) a)L.a)
H CDa)c)
I l)
Q_
C o
W2o.
LLZ Ui 0
C, WI C
U,CC 0C 0
C 0
-o 0
C 0
C-I ciU
.E 0
E 0.0 C C oc.9 c.
Cl)w C,)
D C) a I
D<C
.9
.9 0.
C 1
_5 0
0(00 (0
w 0
z Ci) ox j3 zo WZE LL c
U)0 C
- 30 (000 C
0
0 0
C CO 0
0 0
C 1) ci) cc, 2
E I.-.
-.2.
C (0
(0
E00 Q:
.C0
(_)
C a)
C)
U)
U)
C
..0Eo 3
0
.2 C
ci) 0
.2 D
0 C-o:
9.
C Q
L a)
U)<Q
.C4-$
U)
-i-1 5cC) 0
-J
<C Dz
<C C
0 C00 00 w
C.)
-i zw.
I.2 Qo
.2
.2 3.
-U
- 0) 0 C
-C 0
oci)
Oo Wa) 0
-j U)
-I L1 Ia.
I)Iz w>
w 0.
00 Oo 00 0
ii 0
00)0.
0)E
-0 o
4->,
LC0 Ow uJ 0.
0 (j)
L1 j.
4-I Ow U)
U)>0 (0c U)
.0 (I)
(000..
00 WCI) z.
(I)
U)
(I) 0 C
(00 U)CO U
U, H:,
Lf Ci)
Ii ci)
LI-0 C0 (0
(0U 0
cL0z0 cc) 0.
LI..
(U LIis ZL w.2 (00 Cci)
Oci)
Co Cci) 2i cOG)
.9 O
- 3(0
-00 a)DC a)
C 000 I-0 U)
C) a)0
-D C
a) 0I I.-
CI) 4-C ci) 2 I
4-0C C
a) 0a)N C0) 00 ci) a)
0 (0
C0 C-)
cc3 Co0 C
LL 0
CO Co zW(0 o
0 ZHQ 0<
ui
<0O
-j 0>
C0 (0
0 (00 C
i)
- 3 (0
Cl)w 0.
w0)
(0 CO I))
w a
00 0
0 ci) a)
a)
CU.
CO 9-C 00 cU
a)
I C0 I...
0 C -o 4-1...
CU 0
00 Q-5 C
0 jcU DC-)
00 Z
15 Oa) 4-L0 4-C) 9-CU 00 0
a) a)
I0 U)C0 40 Cl)
-I-C a)0 00 C0 U)0 a) 2 H
0 C.)
0 C.)
0 0
0 C.)
I-I-
I-0 0
0 0
0 0
0 0
0 D
U)
Cl)
U)
U)
Cl)
Cl)
U)
U)
c1 U) w E
0 LI 0
(N ci)0)
U)0 L()
cZ C
ci)>
LU U)
C0 4-C.)
I0 4-U) a.0 U
a)I a.
a)
-)
..o w
m IL.
)
U) 0)
O)
O 0)
i-*
_uI COW
- OIi, 0)
U 0)
C oC w0 S
[
(W C)
W_.
OUj OW W
C)
UC) 0 ci). t5 C
ci)
C-)
--. 0 1) ci) 0 U)
HZ a)
.C)
U)
>o -
Q O-rj
.-co C
j5c CcLCY Oc 0Z 0
Qo D C).-J U)UJ ci) 0- cu D -o ci)
U) 0)
Cu U)
C LL D(f)
C
E cof 1
C
°og)
U - -
o 4-U)
I U)
_Q ci) 0_
ci)>
C LU L..
ci)
- 0 0
I I
I
° 1ij4 I
I c
--j I
I I
I I
o 0
C) 00 I
I I
I I
I
.0::
I 0)N
- 1 (I) 0 I
lw g
I I.-
-0,_
2 0
I I
I I
0 00 I
I o0:
I rO 00 I
0
- I OQ.
I I*
I I
,.2 I
I
- a2D I
0U)o J
I I_
I (N
6z 0
U)C a)0 (I)
I)
V
)
0)
0 0
0 2
w 0)
0 V
Q CO V.
1) o 0
..0):
0 g
00 V
0 Ho
-0 02 co Ii r.i0 H
ILi Lio C0 4-C.)
Cu ci) 4-cu ci, E
E ci, 4-I ci) a.
E0 C.)
0 4-4-
U)I II a
ci) ci, 1-IC ci, ci)
C cu C.)
co C10a_cu f,
C 0,,
ci, C) wI0z Uiz Ui I-0 U)
-C U) 0 U)C0 C)
U) 4-IC U)
C) 00 0
p 0
C 0
C C
V cfl C
0 C
Cu C
Cu C
-2 Co 0
a) ci)
C)
-o0 0
I-4-C0 C)
U) a)0 Cu C
ci C
C (ID 0
0I-C0 0
0 C0 V
0 C
0
- 0 C0
-I-,
U)00 (N0 6Z 4-I U)
U)H 00 Cx C
ci)0.
0.
C C)I S0 Q
U) r
N
(
10 10 10 0I:0a U) a)
E H
C)I 0a Cl)
C,I<
C.)Ic0 Q
U, fit
ID
-S CDa U)
-I CD U)
-o0 D
Ci)
CD
-o CD CiA) 0z0
-tJ H
rri tm 0
o tT1
ó
Q (Jqo
L
- 11. IF I
- 4; 1 ON 0
EgI ON
(
C)
C)
(D 0
5.
(J
=0
C)
C) 4--
- -)
0 C) 0
1
()
C) 0 E
o)
=
C)
C) o-.
o L)
B 9
C)
CD2m 0
0<
-o 13 Cl) 0-CD CD CDOmCI)
Z 0
(aeo 0
U)
- 3 (A)
- -S 0
- r :3 CDCD CDCD
-n lJ R
OU) o
C)
=U)U)
CD
- 3(1)
- 3 CD 1
CD o CD CDU)
(J)-Q) 06CD N) 0 zC)
M!.
m (A)iJ sj>4 Z
IDi 0
CnU) o=3-.
U)
(A).
- 3
- 30>
!ZH 0
o IjQ-U)
QI CD (1)
CD0--
CD C)
(A)
CD_:3 0
-U)CD
-I, U)
(0 0
-1 3
CD (I)
Ci)
-U u
C) 0 0
0 C)
W
-I o
g C)
C) 0
-o C)
U)
- 3 U)
C) 0
- 3 U) 0
-S CD CD
- 3-U) 0
-S
- riii, I
I H
II Ii I
I
C)
I 0
I rn 0
C)()
I cOn) 0 o.)-
I j
cn0<
I I
C) o.nn H)
I
-° I
I a
i
-d
- a a
!1 I 94 I
I 4c l
9 I
C
-I I
4rj 7C)j I
l_
H
0 rr I
=
CJNC 0
c_I (tO I
o0.
q ThL o
I I
C)j I
C
.o-rH CD U)I 0
U)
-1 U)
(0 H
-4, 3
Cl)3 U)
- -4.
0
- 5-CD
-S0 a
0:3 ci)
CD CDa Cl)
-o (A) 0)
0
- 3 C)
- 3-CD
- 3
- 3 CD ci)
CD CDa
-n C/)
U)
(1)
CD C) 0
- 3 CD
- 50.
x CD
.0t CD0.
0 V
CD
-I CD 0
C) 0
- 5 C,,
-n 0
-I 3
m Ci)a
D 2 m C).
D CD T CD CD CD CD CD
- s-CDCD CDCD m CD D
CD CDt CD C0 CD U)
O6CD ozo CD D °-a C,:3-.
CD (.
- 5 5>
CD Z1 E
0 C) ci) -Do I
CD CD C)
-+
CD
-I CD CD Cl)
- 50 0
0 CD Cl) zp N)0-m C
0 0
CD
-I 0
C, 0
C, CD 0
x a)
Cl) 0 CD CD 0zp N) m CD
- 3 z
0 (n
-a CD (0
CD 0
-h (0
1 0
m (I) 3
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 5 Page 5 of 9 Event
Description:
Turbine First Stage Pressure Channel, P-3-447 fails low. ATC determines no runback. Rod Control is taken to manual per 3-ONOP-028 or 0-ADM-21 1. 3-ONOP-049.1 is entered for mitigation. The SRO will address LCO 3.3.1 and 3.3.2. This channel is declared inoperable.
Time Position Applicants Actions or Behavior 5.1 1 IF a containment pressure channel has failed, THEN place the failed channel in the tripped condition by performing the following:
S ROIATC 5.11.1 Remove frises for thuled channel using Attachment 7.
5.11.2 Verify channel is in tripped condition by observing corresponding status light (VPB) lit.
5.12 IF any other channel has failed. THEN perform the following to trip bistables for the failed channel.
5.12. 1 IF plant conditions are such that all required bistables associated with the failed channel may be tripped without an undesired RPS or ESF actuation, THEN perform the following:
1.
Place all bistable switches for the aftctecl loop in test position using.
2.
Verify bistables tripped by observing corresponding status light (VPB) lit.
SROIATC 5.12.2 plant conditions are such that all bistables associated with the failed channel may be tripped due to an undesired RPS or ESF actuation, THEN perform the following:
1.
Place only the bistables which will NOT cause an RPS or ESF actuation in the test/tripped position using Attachment 4.
2.
Verify bistables tripped by observing corresponding status light (VPB) lit.
3.
Follow action of Tech. Spec. /4.3 andjor 3.0.3 for those bistables which were placed in the tripped condition.
SRO References Attachment 4 for Bistables and Function. (Page 8 of 9) 5.13 IF any of the following channels are failed. THEN place the Bypass Switch(es) for the failed channel to Bypass position at the AMSAC panel using Attachment 5:
5.13.1 Any Steam Generator Level Channel I (LI-3-474. LI-S-4S4. or LI-3-494)
OR SRO!ATC 5.13.2 Any Steam Generator Level Channel II (LI-S-475, LI-3-485. or LI-3-495)
OR 5.13.3 P1-3-446 OR 5.13.4 PT-3-447 SROIATC Directs ES/TO to bypass/reset AMSAC per Attachment 5. (Page 8 of 9)
EXAMINER NOTE: Technical Specifications are on next two pages.
17
i-cD I
I a)Q)
I L1.
I I
I I
I c
i Er-I a) 4-(/)C)
I
.Q..
I-I o
lz I
(Ucj)
I E
I I
II I
I I
I I
a)
U)a)
I e0w E
0 U
U) 0 C.,
0 a,0.
0 0*
x 0
a0.
0.
U) -C)
- Cl)
-C)
C Cl) C)
U))
F-C F
U)))
o C
U H
H C
C)
-F I-c I
LU Cl)
LU 0
4-
-c C) 4-Cl) 0 13 a,
a, U) a)
0 I-.
a, U)C a)0 00.
cC D
0 t- -
CO a).c
-I U)a, C
0C 0)
-o C
U)
(0 a))1 0 a) 00.)
C) a)
t3 a)
-Ca_U)
D HZ a)
>(U) a)
C-)
LU oZ cJ-<Ci
.4-(c) a-OTJ LU OZO EQO f-COG)U)
.g
°-g a) a, C
C)C a,
a)E 5E
-.20 U) c Q Wa)a)
C C
(\\1
øH 0
-E (I)
I L
0 C
a) 0 000)
(N o
0°L U)L1 0
H I-0
>a)
-c a) 0 U)C0 4-0 U)
C a)0 0
0.
G)
(U U,
CC) a)
(UH 0
U)
F-)0 U)
C
-F-,C (U
(I) a)CC (U
C)
C0 (U
C ci)
E U)C E
a)
U)
Cl) 0 H
0
(-F (Ua) a)
E C)
C C
Euj (U_i CC)Q c0 0I L1J z
ft C
I (I)
U)
(
I C) 4-)
LI)
C) 4:I-I 0
F C) a:
ZI0 F:
C-)
Lu
-J Lu
H io 0
(I) LIII 2iijjj C)
(N 0 0 U) iiiza zi-
c-i
<0 II
(/)1 diii zz
-iz
<<j F-I 00 F-u.
41)
F)
U)
C)
-J U).Cti-C) 4z0 F:
F-)
C) a)
wo IIIw C
Lo) 4
>4 o (U0 Q
(U U)c (UCC s
C) a, 4.- >
C 0
C)
C z o--a czu 0a, CU.
U)
U)
- - 0
-c U
I z0I0 co C)
C.)
.2 0
+/-
0 0
a-L10 0
z0 I
4:
Iz LU D
I (I)z LU I
Cl)
(I) 0 H
0H0 4:
Ui C-,
I
-4 ft LL U
C ft C
LC 4
C I
C 4
C C
F II)
-Q (U
H C
C 3:0 U)
C-,
a) 0 C
U) 4:
C 0
Z 3:
0 0
-c CL H
U)
CL 0
u, 4:4:4:
a)
E I
2 C
I-4:F2 LL H
(ID2 C)
C)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 5 Page 7 of 9 Event
Description:
Turbine First Stage Pressure Channel, P-3-447 fails low. ATC determines no runback. Rod Control is taken to manual per 3-ONOP-028 or 0-ADM-21 1. 3-ONOP-049.1 is entered for mitigation. The SRO will address LCD 3.3.1 and 3.3.2. This channel is declared inoperable.
Time Position Applicants Actions or Behavior INSTRUMENTATION 3I.3.2 EMGIIIEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMiTING CONDrI1ON FOR OPERATiON 3.32 The Enaineered Safaty Festers Actuation System (ESFAS> instrumentation channels and interlocks shown in Table 3.3-2 shalt be OPERABLE with their Thp Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-i APPLICABILITY:
As shown in Table 3.3-2.
ACTION:
a With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-3, adjust the Setpoint consistent with the Trip Setpoint value within permissible calibration tolerance.
b.
With an ESFAS Instrumentation or Interlock Trip Setpotnt less conservative than the value shown in the Allowable Value column of Table 3.3-3, either:
1.
Adjust the Setpoint consistent with the Thp Setpoint value of Table 3.3-3 and itetemtine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the affected channel is OPERABLE or 2.
Dectare the channel inoperable nd app the applicable ACTiON statement requirements of Table 3.3-2 until the channel is restored to OPERABLE status with its aetpoint adjusted ccnlstent with the Trip Setpoint value.
I c.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-2.
TABLE 3.3-2 (Continuedr ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MaNIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONALUNIT OFCHANNELS TOTRIP OPERABLE MODES ACTION f.
Steam Line f,owHigh 2/steam line 1/steam line I/steam line 1, 2, 3 IS Coincident with:
in any two in any t.vo steam lineS steam lines ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4.
Steam Line Isolation (Continued) d.
Steam Line FlowHigh 2/steam line 1/steam line llstearn line 1, 2, 3 15 Coincident with:
in any two in any two Steam Generator steam lines steam lines PressureLow 1/steam 1/steam 1/steam 1,2,3 15 generator generator generator in any two in any two ACTION 15 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST or TRIP ACTUATING DEVICE OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within hours.
19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.:
2 Event No.: 5 Page 8 of 9 Event
Description:
Turbine First Stage Pressure Channel, P-3-447 fails low. ATC determines no runback. Rod Control is taken to manual per 3-ONOP-028 or 0-ADM-21 1. 3-ONOP-049.1 is entered for mitigation. The SRO will address LCO 3.3.1 and 3.3.2. This channel is declared inoperable.
Time Position Applicants Actions or Behavior ATTACHMENT 4 FAILED CHANNEL BISTABLE LIST P-3-447 Max Deviation As Compared to other Channels Turbine First Stage Pressure 50 PSIG DEVIATION Ref Dwgs 5610-T-D-ISA,18B,12A.12B &17; 5610-T-L1, Sh 17.21
& 22A RACK BISTABLE BISTABLE STATUS FUNC ANNUNCIATOR LOGIC AFFECTED No.
No.
FUNCTION LIGHT TION P-7. 1.2 turbine I/rat stage pressure >10%
Turbine Power po to allow at power trips (P-lU also 25 BS-3-417-1 Input to P7 an input to enable at power trips>.
2/2 turbine first stage pressure >10% and (Turbine >10% Pwr(
PC447E1 3/4 power range channels >10% blocks a oower trips.
Turb PON 2/2 channels >70% turbine power, allows Allows Load Limit 25 55-3-447-2 Load Limit P
load limit runback for NIS/RPI rod drop Run back PC447E2 signal (Runback on Rod Drop Deleted)
Program Steam Flow LOOP A HI SO A 1/2 channels on 2/3 S/Gs high steam flow 24 BS.3.475 Versus STM FLOW C 7/1 STEAMLINE S
> program with 213 low Tavg (543°F) or Turbine Load FO475 HI FLOW 2/3 low 5/0 pressure (614 psig)
Program Steam Flow LOOP B HI SO B 1/2 channels on 2/3 S/Ge high steam flow 25 BS-3-485 Versus STM FLOW C 7/2 STEAMLINE S
> program ruth 213 low Tasg (543°F) or Turbine Load FC485 HI FLOW
213 low S1G pressure (614 psig)
Program Steam Flow LOOP 0 HI SO C 1/2 channels on 2/3 S/Os high steam flow 25 BS-3-495 Versus STM FLOW C 7/3 STEAMLINE S
> program with 2/3 low Tavg (543°F) or Turbine Load FC495 HI FLOW 2i3 low Sf0 pressure (614 psig)
- CONTROL RELATED I
Its
- RX PROTECTION RELATED S
- SAFETY INJECTION RELATED ATTACHMENT 5 AMSAC CONTROL PANEL Place the Normal/Bypass switch(es) to BYPASS for the applicable failed channel(s) at the local AMSAC Control Panel.
a.
Processor A (1)
Level I (A S!G Level. Channel 474)
(2)
Level 2 (B S!G Level. Channel -184)
(3)
Level 3 (C S/G Level. Channel 394)
(4)
Power I (First Stage Tuabine Pressure, Channel 446)
(5)
Power 2 (First Stage Turbine Piessure, Channel 447) b.
Processor B (11 Level I (A S G Level. Channel 475)
(2)
Level 2 (B S/G Level. Channel 485)
(3)
Level 3 (C S/G Level, Channel 495)
(4)
Power 1 (First Stage Turbine Pressure. Channel 446)
(5)
Powea 2 (First Stage Turbine Pressure. Channel 447) 2.
At the AM SAC Panel, depress and release the SYSTEM RESET pushbutton.
20
m CDm 0D D
CD CD Cl)
-4.
CD m
z Ci)
E 0
o (D
0 I
o
E c
0 HO)0 I)
-o I_u C(
M CI)CD-T-I ir
in (D_j Jo J
Z
-D 0
ØD)
CD 0
W u
u j
4 CD CD C
CD
w C) 00 0) oCCD 0
zZmO
0 (DØ C-)
1 (T)
I-((DO)
-fl 2.
U, in 0z oo CD
<C) 0)
(1) 1/
CD
C) Q 3M 3 0
I (DO H
CD 0
Q (ft C)
-u A
C))
N)
O Iv 0
o-
-D 0
))
j CD CD CD
-0 (0
CD 0.
(0 C)
FJ>J Z
03 CJ-J o
3 CD
-H D_.
CD 3
czH
-rj O
C 0
CD m
(DO CD 0
Co CD
--h.
3 CD rn (I)
Cl)
(0 Q0 0
z
-J2 c1e0w E
L..0 LI (0
C0 4.
C.)
I0 4.
I-a) 0 Va, z
a) x C
a)0.
0.
Lf) 9-c) o
LL 0)
C a)
(E 0)
C/)(Y Cu 0
Cl)coO
- 0 CD CI)CG) o
<*-0 Z
c0 0
Cu a)a)
C C Ill.
j (N
1L.cD Ujj d
C 0
0
.2 0L I.
Cu f.
C a) c
°>-° IL
(1)0-Cu 2j 0
) 0. C.E ci a,
o (
9 QCL.
c)
_c1 I
IIJQ)Q 0
CL.
o 0
(N 0-
o 0
0C Z ° 0
-Cc a)>
U)
L.JCu_C a)
I-;-
a,0) 0
>a) 0
..c o
WoH 0
(0 a
U)
- 0) 0 Co
_1 0 Wa Ci ZU)
(,i
<C, Cl) w I
0z I
C0 (0I-ZE 4.
t3 (ow CD 0r::
(OF (0<
05 0) 0 U) 0<
0<
LI 0 F-.
0
. I LI (00i C0
.0 C0()
a,a,a, a, ii.
C.
(90
<N U)w U,
U 0
C0 (U
U)0 at 002:0*
owC Ic WC U
U) wo DO
=
(U (Ua)
WO Dcl)
CU)
U)U)
- 3 9
-o C° U) 00 C
00 0
-C 4-C0
- 0 0>0 C.)
Co
- 0 C)
.0 (0
4-a Ca) w C
C)>w 0
4-00 w
H0z a::
uJz uJ Cu C0) 0 I.0 0
a)>
a)
C C
0,
0 U)
O Cu
-oC CU c00 CUDC Cu S
Co a)
(UI-a, a,
a a,
C
.a
.a a<
a,
a
0 0
0 U
C C
C U
p.
s a,
U a
.0 0
0 U
a, p
a, a,
a, 0
0 0.0 U
U.
zw I
U) 0 C
U) 0
>0-U) c (I) o C
CW 0
Cu
-c a) 0 U)C0 0
U) 4-,
Cu0 0
0-.
C U)0a-ci)
S H
C!)Z0I C.)
I0S0 a-z0I 2
11-.z00 Sa:
-j C
4-C 4-C 4-C%J c\\J 0Z0 I0 a::0I a::w a-0 o_
o_
0 0
0 0
o o
o o
0 0
0 0
C)I 0o0
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 6 Page 2 of 5 Event
Description:
SIG Steam Flow Channel Fl-474 fails as is for A SIG. The A S/G Feed Reg Valve does respond properly during power maneuver. Action is necessary for manual control and/or swap channels. When discovered, the SRO will address LCO 3.3.1 and 3.3.2. This channel is declared inoperable.
Time Position Applicants Actions or Behavior 5.1 a control function was placed in manual control due to the failure, ThEN verify the control function is returned to automatic.
5.5 j the failed channel is QI related to Technical Specifications is an input to SRO!ATC Reactor Protection or Safeguards, THEN go to Step 5.16.
5.6 Refer to Technical Specifications 3/4.3, Instnsmentation veri1r the minimum chamiels operable.
5.6.1 Take appropriate actions as specified in Technical Specifications.
CAUTION The failed channel bistable(s) is required to be placed in the tripped mode within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of the failure determination, except if other channel bistable(s) are in the SROIATC tripped or test position and would result in an undesired Engineered Safety Features actuation or Reactor Trip actuation.
The overall effect of a failure of this type is a reduction of instrumentation redundancy and, therefore, a possible reduction in plant protection.
5.7 IF a 4KV bus480V load center undervoltage channel has failed. THEN perform.
S ROIATC 5.8 IF a turbine stop valve closure channel has failed, THEN perform Attachment 2.
5.9 IF a turbine auto stop oil channel has failed, THEN perform Attachment 3.
SROIATC If l&C determines a Test Sequence Processor for an Eagle-21 Channel has failed, then that associated Eagle-21 Channel may remain in service if Attachment 6 is performed once I
per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. (Reference Safety Evaluation JPN-PTN-SEIS-95-OO1)
--I 5.10 IF I&C determines a Test Sequence Processor on an Eale2l Channel has failed AND no S ROIATC f-nonual bistables are lit. THEN perfonn Attachment 6 once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the associated Eagle-2 1 Channel is removed from service for repair.
5.11 a containment pressure ehannel has failed, THEN place the failed channel in the tripped condition by performing the following:
S ROIATC 5.1 1.1 Remove fuses for failed channel using Attachment 7.
5.11.2 Verify channel is in tripped condition by observing corresponding status light (VPB) lit.
23
ci LU I
I-)
U)
U U4 C) a,0
-J 0
U H
gIi al_c 0 C
c o
l)(Cf)
(No A;_
ID Cl) o v
U
Ca a) a, 17 o
C C (U (NO flAO (N IDI c.1 e
C,)
Ui E
L..0 U-U) 0 4-C) 0 4-a) 0
-Va)
L.
a) x a)0 Q.
-sf-P CD
.2 Cl CD
a III C
2
C) a a-
- s Al
-° CD
ID in
a,)
IA ID.
2
° IA 0
C/)
a E
a a
a a
)i-In
-CD° CDI IV Q
o CD)
C) 11 11
.1I
.;D 0
aL 1
rC I P fl
- 1 a,
0 ID rJ F-ii ID cI 3
DC C
Q 2
z a-0:C r7
in t
n
.0 aC
.0 0
ID i.1
II, Cl)
CD
.a,;CD C) 0 C
.0
-a 3C C
U) o
)
LICC I)I In 0.
IV C)
ID.
C) b i
IDn2) 11.
.00.
1-)
0.
ID 0
11
.0
£1 0
- CD-0
=
ID 2
- a,.IDn
C)
CD ID
>1 ID ID.t
,_c 0
0 a,
C)_
CJ IDID
)-I 0))
- 11 J{
(i Ir f-lI Cl)
Il) c)
,n 0)
Lf) a)5 U)
S C
1) a)
a)
(Y) 0)
CI)W 0
-(U C) coc1)
(0 o
L 0
Cl) a-l 9
-U)
U)G) a)>
(l)0t5 i5 t >0 ria)
(N LL(UU) 5E ca)t3 o*
CO o0_>
a)o Cl)
WDzy
-c
>. a) _o (U -
a) a)
a) 0 flL.
o
?
ci
CQ o
Oa
(-I 0
-a) ci) o OCO(U Q
>(UC 0
W>CUO 0
(U
-c a)c 0
(I)
C0 0
41:
U)
C (U0 0
0.
0 FUJ
-Jw 0I-2°-u-OX4 (J IL ID 2222
.C.0 0000 IIXXX
- alCoa, ID (N
LU LU Ui Ui 0000 xxxx 44.4<
0000 Or-.
V Vi A Ii
((Va)))
0000
- a. a o Q
,IV V
V CC CC 0000 IS1 V.
-U a)
C)0 E0 C-)
cc
-. C-)
>L ala)
(U U) 4-a) cW
.t ci)F a)
<Ui CU o0
>a) 4-C CO CC) 0-V.-
G)G)
CUC 014 oci)
C)
- 0. C 4-CUd 4
ci)
I-C
.C C.)
ci) 1C1)
C.)
UiI0z Uiz Ui a
2 ZQ (I) 0 C)
U I
D C
0 Ui IL LL
)-
£k
A (I) 0 V
I Ui C)
-)
F-LU 2
Cl)
IL D
4 CD)-
ID ID (1)1))
(0 (0
0 0
0 CD U)
<a, S
0.UC
>1t 2 o3
- i U)..>
F-LI) r IDci 0
0
- D U
E WZ U
U U
2 UI O
-C
)-
ID IL U-IL U)
(I.
(N
a d
r-ID ID r
T r
-z 17 0
(0 (7
U?
ID C0 2
0 0
a)
E I-4-C ci, E
C)
LIe 42 DC (0
N-N.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 6 Page 4 of 5 Event
Description:
S/G Steam Flow Channel Fl-474 fails as is for A SIG. The A SIG Feed Reg Valve does respond properly during power maneuver. Action is necessary for manual control and/or swap channels. When discovered, the SRO will address LCO 3.3.1 and 3.3.2. This channel is declared inoperable.
Time Position Applicants Actions or Behavior 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.
APPLICABILITY:
As shown in Table 3.3-1.
ACT1ON:
As shown in Table 3.3-1.
TABLE 3.3-1 (Cortinued REACTOR TRIP SYSTEM INSTRUMENTATION MIN I MUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 12. Steam Generator Water Level--
2 stm. gen.
1 stm. gen.
I stm. gen.
- 1. 2 6
Low Coincident With Steam/
level and level coin-level and Feedwater Flow Mismatch 2 stm./feed-cident with 2 stm./feed water flow I stm./feed-water flow mismatch in water flow mismatch in each stm. gen.
mismatch in same stm. gen.
same stm.
or 2 stm. gen.
gen.
level and 1 stm./feedwater flow mismatch in same stm.
gen.
ACTION 6
- With the number of OPERABLE channels one less than the Total Number of Channels.
STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within S hours.
25
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 6 Page 5 of 5 Event
Description:
S/G Steam Flow Channel FI-474 fails as is for A SIG. The A SIG Feed Reg Valve does respond properly during power maneuver. Action is necessary for manual control and/or swap channels. When discovered, the SRO will address LCO 3.3.1 and 3.3.2. This channel is declared inoperable.
Time Position Applicants Actions or Behavior INS9UMEThTICN 3!.3.2 E\\GINEEED S4FETY FETUPES ACTUK1ON SYSTEM INSTRUMENTATION LltlTlNG COIflITION FOP, OPERA11ON 3.3.2 The Engineered Safety Feature Actuation System ESFAS instrumentation channels and interlocks shown in Thble 3.3-2 shaL be OPERABLE wth their Trio Setpoints set consistent w th the values shown n the Trip Setooint colUmn of Table 3.3-i APPLICAEILITY:
As shown in Table 3.3-i ACTION:
a.
With an ESFAS Instrumentation or Interlock Trip Setponz less conseriative than the vaue shown in the Trip Setpoint column but more coneeRative :han the value shown in the AIcwable Value column of Table 3.3-3, adjust the Setpoint consistent with the Trip Setooint value whhin permissible caLbration tolerance.
b.
With an ESFAS Instrumentation or Interlock Trip Sezpoinz less conservative than the va:ue shown in the Adowable Value column of Table 3.3-3, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-3 and determine with:n 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the affected channel is OPERABLE: or 2.
Decare the channe inocerable and apply the applicab e ACTION statement requirements of Tab e 3.3-2 untL the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.
c.
With an ESFAS nszrunientation channe or interlock noperab[e. take the ACTION shown in Table 3.3-2.
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4.
Steen, Line Isolation IContinued) d.
Steam Line Flow--High 2/steam line 1/steam line 1/steam line 1.2.3 15 Coincident with:
in any two in any two Steam Generator steam lines atsam lines Pressure--Low i/steam 1/steam 1/steam 1, 2, 3 15 generator generator generator in any two in any two steam lines steam lines or TLow 1/Loop i/loop in i/loop in
- 1. 2, 3 25 any two any two loops loops A CTION 15 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALCG CHANNEL OPERATIONAL TESTer TRIP ACTUATING DEVICE OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
26
0 0
15 a,
0 0
-J U)
Cu U
C0 cL0 0)
U) ci)
Cl) 0 a)Q LU 420 o -
ci) t)
Cu cL2 F
C I
I I
N I
LU I
I C)
I I
I C)
I g)s I
-t C)
I I
- c II cOS..
- C)
I I
IL) 1W I
so..
Ic,
-C) z
)i))
I
-1 I
I I !
I I
I ii! I I
I L
I I
.ccc i_il e
U)
LU E
L.0 LL U) 0 4-0 I0 4-a, 0.0 a,
0*
a, x
- 0 a,
a)0)
Cu x
a)C ci) a)
(1)
U)C0 0
Cu a)0)
Cua 0
-o 0
L1 00 0
(9 c)
U) a)
>a)
LU Cu U) a)
0-U)
OC
G)
>.E N-c o
Zo Z
QE C
a)
D 0_--
w cDCu 4-CU> -o (N
LL(9 C/)
o COca z
o (Y)a)
.C Cu C
a) a)
1>
o C/)
a)
I UJ ci)
C-o o
(N
- .a) cL 0
0 z
1;;
D ci)
F-Co I
ci)
Q_
o uJØ I
Or, U)
OF OF C) bi) cv a
vi cv OF C) cv
-4 U)
Cu 0
a)
-c0 0
LO C) ci) W ci) 4-
- 4dca, Cu
-0 Ci
-0 Cu 4-(1) 0<
0 E
a) o ci 9
0 C))
z a)
C
-e F
0C cv 0
c-c cva)a:
w cv 20 cv a) 0 C
2 9 F
uJ UcJ a-
>.a o
o w
cvLU Cc Ic)
I0 Cu
-c a) ca I-0 U)C0 4-s0 U) 4-C (U0 0a C))
U) a)
CC c
U)
U)a E0o cc z
2w (Jo 0)1 00) zv3 L)
.J(J) a 0) o.
ci a)cv r2 90) cv a)
C))
00 C)0)0)
OX!)
00 ci Q
t H
cv cc.
0 ci,a
-a 0
OW C
Q Fri 0
2
- OF ci, cci o
o a) z 0
a:
cvci IL ciU) 0 C)Q cc-)
(0 Il Lao 0
-C
- ii:
ci-)
F
-v.2 r
z z
I x
><ocv H
F a:
a:
2 UI w
H acvoO v
rcOO UJ LII a:
a:.j 00) 0 0
OV)5Z
?
F F
Cl)
C))
a:u)o..
dci cv C,
9 C,
C, P
0 a)t U) cv U)
C, cv U) z UII F-a, cv E0 00 C,
Ui
-a, o
Cl) 0 c_
9a)-2 (I)
Li 0
a 0
cv c
° cv 0
cO a 00 a:-a:
-C a)
U a) c_c ci aci a
d ci I-a, CU (U
U)
E0 4-a, C.,
U)
CU 0
1K) 0 4-a, 00.
ci)0=
Va, LU I-0z LUz Ui C.)
c0 U) 0 a_
Cl) a)
E I-Ui C)
C*;1e U)w E
0 U) 9-0 (N
U)0)
U)0 C) a)
(I) 0 0
z w
I 0a)
D ci.
a) 0 C
0 C0 Ca C
.0 I.
ci Ca C
Ct a)
.0.2 z
.4-J U)>w ci Ca a) a)
c
. El ci 0
Cci 4;
cc) or ci Li Co 0
.1-i 0
1-Cu a) 0 0
U) ci C,
0 a) 1)-
U)
C,)
0 U)
)ç C
QE U)Cu t3
-CU)
U) W
ço)
C)
U)
Cl) 0.. o
.C 0 U)a)C 0)15 U)
L.Q U) 0 Ca C
0.0 Ca) 00 C,
cia)
C 4;
O ci ci ci a) a) Z UI
.2 a)
=
a) r j5(.o cc.
O.
a) o cc 4;
C
.2 ci
. C) a)
a)
I 4;
ci 4;
2 o
a) 0 a)
C C0 C-)
0 U
0 0
Ca WI 0
-*0 00 LL.5 (Dci Li 0
.00 Cl) 0 0
a) a)
C,)
0.
0a)
Ca 0
0 Ca Ow a)1:
oQ
.20 0-CO 0
(N az 0
U)C a)
C.)
C,)
NO
<.2 00 cn 00 Ca 0
0 C) 0 C
C0 0-Sa)
Ca (I)0 a) 0<
.21-0-u)
I0 U) a)
ca 0
Cl)C0 4-,
C.)
U)
C U)0 0
0..
Ca00 CO U)C ci0 a).0 0)
U) 00 0 c
=
00 oo u._
1)
Cci ca)
F-JEi:
0z.
0) ciI I,
C C,
S a)
U)
CCcc C0 1
.01)
C a)
U) 0
.0 00 0
a) ci a,
0 0
CC.2 Li I
I I
I Ui II-0 I2 1_
C0 ca Ca C
dc m
S Uj a o
ç
.2 a) 4;.-)
.2><
I
-C I
cc ILl cc, cci
-C ccii I
I I
C) I-.
I
.2 Lij 0) 0cI I
>1 I
a cc 11-Iii I
a)Oj 1;
ci C0 0=
.0a)
.0 C)0 4;
a Ca)
<a) a)
.0 a)
CC ci 0
-j CO 0
CO C
ci 0
ciii)
CU))
Cu) 1..0
.01-C a) p
.0 1
Lii 1)
(1)
I-IC C.
ILl ci II)
CL 0
C)
I-4o 0
C)
D t
.0 0
cc z
cc.
a)
- 0) 9
.0, ao ui
,_C a0 10 C1 I.
a IL0 0
C C)
ILI0 U,
(1) cL,uj co (N
C)I.
(N0 az U) a)
I-;00 C0 4-,
U)0 a-x a) 00 0
0::
U) ci)
I-II C)I 0
U) 0 U)
C-)I 0
U)
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 7 Page 3 of 5 Event
Description:
Engineering reports 3B SIG Feedwater Pump High Vibration. SM directs a 3-GOP-i 00 power reduction to remove the 3B SIG Feedwater Pump within the next hour.
Time Position Applicants Actions or Behavior 7
Check Plant Response a
Check pressurizer evel following program a.
IF directed by the Unit Supervisor, THEN increase charging flow as follows:
1)
Start an additiana[ charging pump 2)
Place ar additional letdown orifice in service.
3)
Place LID Temp Controller TC-3-l4dA SRO!ATC in Manual and Control letdown temperature manually.
4)
WHEN letdown temperature is 1 15-l21F and statue.I place TC-3-144A in AUTO.
h.
Verify load reduction rate and auto rod h
Stop or slow power reduc:,on m control control is maintaining the expected TavglTref temperature.
If necessary, piece control ST identified in ATTACHMENT 3 rods ir manual AND maintain Tavg within the expected TavgiTref sT of ATTACHMENT 3.
SROIATC 8
Energize Pressurizer Backup Heaters 9
Verify Turbine Load Less Than 570 MWE WI-lEN turbine load is less than 570 MWe, THEN open the SGFP recirculation valves for SROIBOP the first feedwater pump to be stopped.
Open the SGFP recirculation valves for the first feedwater pump to be stopped p
=
=
=
=
a n a =
= a = a a
S ROIATC Boration should he stopped above the target power level to prevent excessive boration.
1 0 Monitor Turbine Load Within 10% Of Target Go to Step ii.
Power Level Stop the boration as follows:
a.
Place the Reactor Makeup Selector Switch to SROIATC AUTO b.
Set FC-3-i 13A, Boric Acid Flow Controller pot setting as desired c.
Place the RCS Makeup Control Switch to START 29
(3 (3)
(32 (3).-
0 2
C
.9 2
2 U)
.2
+1 c
.9 0
.2 U)
U)
U)
U) 0 U:3:3Z2 o
CL _J0 z
220 C
H 0..
CL
(/)
-e
0.
H
.9 U)
U)
U)
U)
(1) 0
£ 3)
(3 U) 0(
1))
.2 Z
U)
U)
WC U)
U)
CO D
.9.9
.9
.2.2
.9 $
.2
-t U) 0 0
0 U)
CO C)
(3(3
[UJ Ii-U) 0 (3
0 o
1(3
-z 0
.C U
c.I U)w 0
L1 U) 0 C.)
0 U)
I-a, 0.0 a)
I..
a, x
a, 0.
0.
I.f)
U)
Q-U) o U)
U) :
4-,
>iz N-c o
ia..
Z oE 4-,
c::3 c:
ci)
D QL w
L-cDU) 4-,
U)> 0 U)
LJ LLØ o
øca o
(Y)Q)
U)
-I-,
C (1)
U) 0>
o U) z ci) 4-,
I I
CQ I
U) 0.
o UJ(9 UI
.0 x U) 0 CL 1)
(3 2o U)
-Th U)
E.2ci
-3
.9
.9 0 U)Z
.9 (3
z UII
.b I 4 C0 U
0 0
0.
CU)
In U)
JO 0-OW UI C%J Z*U)
UJO I-5 0.9 C
U)
(0-0(3
£ H
Ez
- 1
-(3
- 3 ZU) woo)
I o.9
- =3:3 0
IL
- 00 0
0.
Cl)
U)0 CU)
.9 1
D 00 04 Cr) 0 U)
-c U) cri 0
(1) 0 0
C,)
4-.C U)0 00 I
I U)
I I
U)
CL I
U)
I U)
U)
I
-3 I
j 3)
-3)
I q
I CL I
o 2
.9 I
3 I
I 00 CL I
CL-U) 0 I
CL.9 I
U) 1W o
.9 U
I I
22
.9 I
CL I
I I
I I
36 I
2 I
I LLZJ
.4-.
C D
0
-v U)C0)
CU U)
E CU U) 4-,
(I) x Cl) ci) 4-.
cci0
-oC
.44 U)
-C C,)
a)>0C D
F-C, U)
£3 C
1)
C
-:3 0.
C F
- 34 cLWI) 2W0 00 3(3 3-
.0 U) 30 00
-C C
C)
U) 0 (1) 3 0
(3 C
.9 U) 2
- 3 C
- 5 o
2 20
-= -
U 0.
oOJ LL
-W (0
0Cfl CU CDi COO U)0 CL 0C o
U)
C)
(3 W
UI 0
0 U) 0 0.
I C
C C
(3 CL U)
.2
.E
.2 C
U)
.2 v
z c
U)
(3 900 0
o c
J H
I U) 3)
00
£3 C
C-)
U)0.
U) 0 a,.
4-4-
a, Ea) 0.
E I0z Cci E
I-.0
>4 CU E
0 0::
Cl) ci,.tI-a, 4-0z a,
E (Ux LU 0
Q_
0_
ci C
I 0
0 I
o 0
2 0
0 0
U)0 0
U)
U)
U)
Cl)
U)
E I-00 0
Cl)
w I
-I LLZ
-ax 0<
3.9 U)
I-wE r
Wa W(i)
C;4 C
U)w E
0 U
(I)C0 4-,
C.)
0 0C0 V
a)I 0*
G) 0 x
V C
a)
C.
0.
U 0
C E0 a.
a) 0.
I
<C LiD
()
LO U)
LI)
D ci) 0 cc1) oc
=
ci)
C
>.c N-C-
o Io z
CD C
L ci)
- 5 Q_I LU U)CU,
(5>0 ci) ci)
(N 00) o
øcD o
C)O.)
_C U),
C ci) ci) 0>
o C/)
E C
cDC C2 C)
C:5 I
LUcs ci) o o
(N U) o oo z
U U)
I Co I
ci)
Q_
o wO adIzw>w 0
4-,
-o a) a)
ci.,0I C.
- 0 a)
C.)
- 0 a)
.4-C a) ci.)
C)
C a) a)
.0 U,
Co
-C L.
a) 0 C.
C a)-c wI0z Uiz 0
(5 ci) 0 U)C0 4:
U)
-I-,
Co0aa 4:
C0 4-,
U)0a-ci).r 0
0) 01 C3
<zI T
(1) 10 C
F-00 0
-Q C
ci) 0
-2 II) 0 0.9 U,
u r-p UI U) ci) 0 ft U-0
-g C
00
.Dj5 0
-H o
0 0
ZIUJ 00 0
L1JI IL 00 Cl) 0 0
II CO 0
(f)
U)
- t:
H>.
°
.9 (1
2 c
I[i Cl)
E 0)
CLL CO
>:E.
E 0
0 0<
N r
z 0
0
øC)
CD C
uii 0.
o 0
i xC5.z C
z
()
ci)
(,)0 W
0(/)
C
((
1 Q
H (9cC) r HI ci) 0.
EF-W W
(
0 t
.s U-c F-I-
øc0 5
(1)
U)
W
F-0 (Dci) o E
(9 C)
C) 0 C
CC L.
(5
oa 0
CO 0
0 00)
-O CD.
(I)
CU CU E
.2 ci)
C)
Ci)
H H
CO 00
()
(I)
Cl) o
>Q 0
0 0
()
Q.,.
ui1 U
CD CL 0
LIJ
!Ic c
-ó
ó Z
i0 I
ó
ó w
C, I
00
-J0 LI.
(5 1) 4.?
I-.0 C0 Cl)C CUIF C
ILl o
cL o
Li 5
0 C?
Cv) ci)
E I-ci
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 1 of 12 Event
Description:
During the loss of Main Feed, a common loss of suction to all AFW pumps.
The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed. The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually. The ICW to TPCW Heat Exchanger Valve, POV-3-4883, does not automatically isolate on a Safety Injection signal. The BOP takes action while performing Attachment 3 of 3-EOP-E-0 to manually close the valve.
Time Position Applicants Actions or Behavior Direct Facility Operator to trigger lesson step, EVENT 8
- MAIN FEED HEADER BREAK WITH SGFP BKRS TRIPPING. (insert TVFAHDR2 1 delay=0 ramp=0 on=0 off=0, insert TVFALN3 1.0 delay=0 ramp=0 on=0 off=0, insert TFF1 D1AT TRUE delay=120 ramp=0 on=0 off=O, and insert TFF1 Dl BT TRUE delay=120 ramp=0 on=0 off=0)
SRO Directs response using 3-EOP-E-0 starting at Step 1.
CREW Steps I through 4 are IMMEDIATE ACTION steps.
Verify Reactor Trip Manually trip reactor. E reactor power is greater than 5% OR intermediate range power Rod bottom lights ON is NOT stable or decreasing, THEN perform the following:
Reactor trip and bypass breakers
OPEN a.
Monitor Critical Safety Functions using 3-EOP-F-O. CRITICAL SAFETY SROIATC Rod position indicators
- AT ZERO FUNCTION STATUS TREES.
Neutron flux DECREASING b
Go to 3EOPFRS.1, RESPONSE TO NUCLEAR POWER GENERATION1 ATWS, Step 1.
2 Verify Turbine Trip a.
All turbine stop or associated control a.
Manually trip turbine. IF unable to verify valves CLOSED turbine trip. THEN close main steamline isolation and bypass valves.
b.
Verify Moisture Separator Reheater b.
Manually close valves. IF any valve can Steam Valves CLOSED NOT be closed. THEN close main steamline isolation and bypass valves.
MSR Main Steam Supply Stop MOVs SROIBOP Reheater Timing Valves MSR Purge Steam Valves c.
Check Mid and East GCB5 OPEN c.
Manually open breakers. E breakers do (Normally 30-second delay)
NOT open, THEN actuate EMERGENCY GEN. BKR. TRIP SWITCH for the affected breaker(s).
32
c, C
C C
D
)
V t
oC) t a)
Q)
C i
9g)s C)
C, C) 2 C)
C.
! fi DI C
øajL1i C
a.
LJ
<C Ivc,a-E C
C C
D
<C Q-
.d 0
0 C
C C
C.
.0 C.
z E.
W C.Ui
>o..
()o o n
OW OW C.
C)S V
V
>clD
>CC Q
C
.0
(.)
d c1 Cl)w E
0 LL U)
C0 C.)
0 4-cu 0.
0 C)
I.
0 ci)a:
x C
ci)0.
0.
(N U)
()
()
D i
EOa)
C o
c F- - E (N
.4-a)
Wøc 0
O
)
<CDa)LJJ
= _o c
L1 a)a)QQ OF E
o u C)
CD ci
- HQC z
- COt, (5
-I-SC ci)
-OO cIJOa) w o -D 0 C
ci a)
E ci)
>, (1)
L 0 o (N
rn4 a)
-.a) ciz
.2 0Ec o
C.)
coO
..a)
Co
U)
(1) 0)10 a)Q (N
2a)cfJ Co
.x o
o-.2-LiJ (N.9-c a)
_U)
U) 1?F
-o L1JFw.25 I-I U)>
0 w
I-I D
a)
Co C
E a)
U) c n:
(I)
U)
U)
_c (1)
U)
CO o
2-
.b a) a)
C c
cu a)
U)
Cu 9w 00 uI Cd)
II0 K) 0 a) 4-.
Cl) 0 4-0 I..0 a)C-I.
L0 U) ci)
CU 0.
U) 4 C
o.D
-a) 4
-.C
>,4-0
>a)
-C a)
I0 U)C0 4:
U) a)0 0
4:
C))
D W
cC 0
))IX C
OW C
CZ CW V
.W
>W 00 C)
W 0
W CDZ
>Z
,W
)w
- CX z C
C C_j CH c<
CZ
))I_
.,H z
uZ c)Z C
,1);;r CE
.C.
O O
1.1 C
41)
C) 41)
Sw 0I.
41) 0a.
C)
I
>a)
-c U) 0 U)C0 0
4:
Cl)
C a)0 00 4:
C0 cci 00 U)
E I-00 o
U)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 3 of 12 Event
Description:
During the loss of Main Feed, a common loss of suction to all AFW pumps.
The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed. The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually. The lOW to TPCW Heat Exchanger Valve, POV-3-4883, does not automatically isolate on a Safety Injection signal. The BOP takes action while performing Attachment 3 of 3-EOP-E-0 to manually close the valve.
Time Position Applicants Actions or Behavior 4
Check If SI Is Actuated Perform the following:
- ANY ON a.
Check if SI is required:
OR Law p esauner pressure 1730 psig Safeguards equipment AUTO OR STARTED High containment pressure 4 psig OR C
High steam line differential pressure 100 paid a
SROIATC High steam flow with low 510 pressure - 614 psig OR low Tsvg (543 F) b.
IFSI a required, manually actuate SI and containment isolation phase A AND go to Step&
c j SI is required, jj perform the following:
1)
Monitor Critical Safety Functions using 3-EOP-F-0, CRITICAL SAFETY FUNCTION STATUS TREES.
2)
Go to 3-EOP-ES-Oi, REACTOR TRIP RESPONSE, Step 1 r-----io.T------I CREW L
POLDOUTPage shall be monitored forthe remathder of this procedure. -
CREW Monitors 3-EOP-E-0 Foldout page (see next page) 5 Continue With Attachment 3 To Complete SROIBOP The Prompt Action Verifications While Performing This Procedure Examiner Note: 3-EOP-E-O, Attachment 3 commences at Page 38 and at Page 46.
Examiner Note: The SRO and ATC will complete the remaining steps in 3-EOP-E-O, while the BOP performs 3-EOP-E-O Prompt Action Verifications using.
34
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 4 of 12 Event
Description:
During the loss of Main Feed, a common loss of suction to all AFW pumps.
The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed. The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually. The ICW to TPCW Heat Exchanger Valve, POV-3-4883, does not automatically isolate on a Safety Injection signal. The BOP takes action while performing Attachment 3 of 3-EOP-E-0 to manually close the valve.
Time Position Applicants Actions or Behavior FOLDOUT FOR PROCEDURE E-O 1.
ADVERSE CONTAINMENT CONDITIONS IF either of the conditions listed below occur, THEN use adverse containment setpoints:
Containment atmosphere temperature 1 80°F OR Containment radiation levels 1.3x10 5 R/hr WHEN containment parameters drop below the above values, THEN normal setpoints can again be used IF the TSC determines that containment integrated dose rate has not exceeded Rads.
2.
RCP TRIP CRITERIA a.
IF both conditions listed below occur, THEN trip all RCPs:
- 1) High-head SI pumps
- AT LEAST ONE RUNNING SI FLOWPATH VERIFIED.
- 2) RCS subcooling
- LESS THAN 25°F[65°F]
b.
IF phase B actuated, THEN trip all RCPs.
3.
FAULTED SIG ISOLATION CRITERIA IF any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized, THEN the following may be performed:
a.
Maintain total feedwater flow greater than 345 gpm until narrow range level in at least one SIG is greater than 6%[32%].
b.
Isolate AFW flow to faulted SIG(s).
c.
Stabilize RCS hot leg temperature using steam dumps when faulted S/G has blown down to less than 10% wide range.
4.
RUPTURED SJG ISOLATION CRITERIA IF any S/G level increases in an uncontrolled manner OR any S/G has abnormal radiation, AND narrow range level in affected S/G(s) is greater than 6%[32%], THEN feed flow may be stopped to affected SJG(s).
5.
AFW SYSTEM OPERATION CRITERIA a.
j two AFW pumps are operating on a single train, THEN one of the pumps shall be shut down within one hour of the initial start signal b.
E two AFW trains are operating and one of the AFW pumps has been operating at low flow of 60 gpm or less for one hour, THEN that AFW pump shall be shut down 6.
CST MAKEUP WATER CRITERIA i.E CST level decreases to less than 10%,
THEN add makeup to CST using 3-NOP-018.01, CONDENSATE STORAGE TANK (CST).
7.
RHR SYSTEM OPERATION CRITERIA IF RHR flow is less than 1000 gpm, THEN the RHR pumps shall be shut down within 44 minutes of the initial start signal.
35
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 5 of 12 Event
Description:
During the loss of Main Feed, a common loss of suction to all AFW pumps.
The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed. The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually. The lOW to TPCW Heat Exchanger Valve, POV-3-4883, does not automatically isolate on a Safety Injection signal. The BOP takes action while performing Attachment 3 of 3-EOP-E-0 to manually close the valve.
Time Position Applicants Actions or Behavior 6
Check AFW Pumps
- AT LEAST TWO Perform the following:
RUNNING a.
Manually open valves to establish bvo AEW pumps running.
b.
an APW pump is tripped, THEN dispatch an operator to locally reset the AFW turbine trips.
- c. j both units require AEW AND only one AEW pump is available, THEN perform the following:
SROIATC I)
Vemy all RCPS -TRIPPED 2)
Establish 270 gpm AEW flow to each unit.
3) tJse a setpoint of 270 gpm for reqLiired APN flow instead of 345 gpm specified in subsequent Steps and Procedures.
EXAMINER NOTE: The Aux. Feedwater Pumps initially come up to speed. This scenario simulates a total loss of suction in the Aux. Feed Water System. The key parameters to watch are SIG Levels and AFW Flow. A Red Path for 3-EOP-FR-H.1 will come in quickly due to this massive break.
7 Verify AFW Valve Alignment - PROPER Manually align valves to establish proper AFW EMERGENCY ALIGNMENT alignment.
SRO/ATC 36
uZ oz (I) Cl)
Li LU I oUJZD cQZ 0
a0 Cl) 0 o LU LU U) ft Cl) C))
.0 c.1e Cl)w E
0 U
U) 0
.1.
C.,
L..0 4-Cu I-a, 0
Va,I 0*
a) x VC a)0.
0.
Cl)
In
.0 In 0=
LLEH 1) 0 00 t°Q Cl) ca a)t a)>V L()
0 a)=
Cu..
LIl)
< EE gii
<oLfl
-DV)H ic Li d
a)
C0 C)C...
2)1
. ZI a) 0 Cii 10 LU U-F LU 10 o-C 0_
a).0-..
(ill) a);;
d co c.SJ
()
C) cu 0_
- 5 E° C
0
.C>
F E (0
U)
LLacu 0
o
)
<.9DWj
.0 C
LJ OF E 0)0
c.9 c -
o CC CuE (OØ._c C
LC U) 00 ccOCu uJ 0-3 E
C 0 4-C Cu
- 0 0) 0 D 0 C
C oa(ucI a)
>, U)
Lj 0
(N
,i
(
U)
)CuOCCQ w2a z
.2 oEc 0
U) 0 c
-cu LI (I)
U)
U)cO
>cu w
L1
- 0) 0 U)Q.
(N
.cHOC CO o
o.2-W (N
0.
L.(U_U)
0 O-r0)W
_Cu U)
L..
0.2 F-
°D-tU) o WHcu2E5 0
4-0 U)0.
0 O
U)
U)
-c
-I-,
(I) b E0 0)
I)
(Y)
-I-,
(0 Cu U) 0 00 4-CD 0)0 0
U) 0 Wa)
<U) z>
D E 0
Cu
-c U)
L.0 (I)
C0
-S0 CI) 4-,c Cu0 00
- 00),
(DC Ccl) 0>
C0 0,,
Cu 0) c L
QCu
-s*0C Wo 0
CC U) 9-C 0
00 CO
-0 o _J <-4-,
13o.
a)cI)
- b U) cc DCC))
)z IN 0C 1
)
a)
C) a,
.E i 00 V
C Cu C
l) 1-Cu a,
- i:
CU 0
C.)
CO 0
00
-i o
1-0
<Ix 0L C)
UJO p
N CC 0
I C02 0
0 Ix 0
o_
U)
U)
E H
C)
C)
I-H 0
Ix Ix U)
U)
cle Cl)w 0
LI (N
4-0 a)0)(0 a) a)
.0 0.
0.
(a a) a)0 (a0
-j a)
.0 a)(a0 0
oz 4-C LU
-c IICI cL-c>
0 0.
a) ci, 0
0 CD (a
0.
a)
Cl) 0 C
CD a,
I (a.
(a.0
>, 0.
U)
(a (I)
C0 4.0 I0 4.
(0I a,
0 a,
a, UC a)>
(a a)a,C 0
(a
.0 vi a)>
(a
ü)
U)C 0
(a C
(a L
a)>
(a>
a)
U)C U
(aU0
-J
-d U) 0 ca
EQa) c D
c: >,
LL W(Q
- 3 ui
(
OQ_
E G)4-LJJ 0
0 C)
HC) g o-E c
0 (U
4-.
-I-t5 CU C
C 0 E
0 0) 0 0 0 C
0W0E ci) >, ci)
LL 00 0-0 ci) rn-I CU
..(j)
CU oCr) c co ci) CO
._ oct 0>
C
- +/- a)° i - D CU
.CO
>C3 LU
-I-0)iQ ;j3Q C) a 0)Q 0
C (I) 0
.C ci)
..cFoc C.2 ci
>< I U) 0
&5>
C 0.2 C Q (I) ci) a).H ci)
U)
>.CD
- 0 LIJF-cu.2-5 (N
az 0
CUC ci)0 (1) w law
. z ow (a
(a (a(a
-(acu-0 oa)N a) 01
.0 a..
a)a)
.00I-U c,)
(.r Cl)
>a,
- 0) (a 0
C C
C (a
U) o
- z
.00 U)CL (a
-0 C
U)
.E
,-o
0<
E Cl) o>
If, E>
caz
)..f U(a
-0
<D 0.
laO
.0>,
.0)
Olu 0.0 0a, QS2 o
0
-J U) 0000
_J
._J
_J
_J 00 i U)
C.,
U)
C, 0
U) a)
0.
(aa)
OsC (a
C C) ta a,a,(a0.
- 0C Ca ID0 (a
0a, So LU
.5(1)
(aD O _J
- 0 O a,a)
C>
Li 0
a, C])
.0 L) a U) 0.
CD C
0.
0 U)
(a
cic
.5 i
(a
-(a S
(aLL (21 Cal OCI) a-(2)>
0 ED LU (I)0
-J (I) a, (a>
Ca>
0 0C U
a)
Ca 0
(a (a
LL C
LU C/)0
-J0 L)
C])>
(a>
(a If, (a0.
.0 ID 0
-D (a
(a U-L U
LL0 a,0.
SD0.
a) a)
.00 (a
a, (a>
a)
U,>0 C
(a 0a, a,
(a
-D ci)a)
II) a,00 t3 co (V)
(N0 x
C ci0.
0.
d
w0
-o p
CD 0.
x 0
-S3H CD U) z p
N)0
-A C?)
Co CC) 0)
CD Oco 0CD razg C-)
C-)
0 CD C)
C)
CD CD0 CD U)
-1 rn H0 C) m
-4
-a m
- 0 C)
C) 0 3
V U) 0 2:
C Cz 2:z C)
- cJ1 p
-o 0
CD C)
C)
(I)
CD 0
CD CD 0
U)C) mc)
I))
>(0 CD (C)
CD Hz rn m
z 0
C-)
CD CD C)
C) 0 Ci) ni ID 0
(,)
CD CD C)I0 Cl) rn ci p
0 CD C)
- 3-CD CD CD-CD Ci)
H ci H0 C) rn H
-am p.
C),
0 na 1z 1)1 c
0 H0 C) z CD CD m
- 3-CD
- 3 Co CD p
ZC) 3 V
If)
H Fm U)H 0
CD I
-U 0
CD C)
C.()
0 CD 0
CD CD 0
(I)
C)
CD
- 30 0z p
N) c20 Hm 0.
C<
Cr)
CD CD CDiU 30 oO
_D <
CI)
- - U) m-*2o H-0:3
- 5-CD j
0 CD C
- 5 0-0(0 CDC?)
0CD 01(0
- m
÷ 0<
0 0-D<8 c.)3.
-o C?) U)
CD CD-0--
CD 0
-400 o 0
-n (1)<
CD 3U)U)CDO
- 3:5 C)
(0 0
. 0
3 3 0 0 C) 0
5-3 CD U) 3CD.-
CD H-si
- S-U) lCD c
o_*C C)
. U) -
d.
C?) 0 0 0 m,-,-CD
0 (D
Ho 0
0 O
I))
CD 1
3 -H
- 3-CDO3 C
-o 0
C) ci)
CD.
CD 0
CD-0) 0 C,
0 Cl)
CD C0 0
C)
CD V
Ci)P p
3 CDCD CD C)
FC) 0.0-CD0 CD C))
00 C-F corn p
0 Z3 CD 3,
0 (p
p*
03,C1 C
0 3, u3,o (1)0 C-)
IC) 0-Co zcfl CU)
(1)
C) 0 F-i C)<
00 0 0)
CD rn Q0 r
CD C)
- 03, C
CD C) 0 (1)
C 3, 2: CD 0-2:0 3,
C) 3,0 C) 0 C)
C)
C V Z(M n-CD
-<0 0
2:rn Ri CD zp Ci CC)
(0 IcC 3,
-D0 U) 0)
CD Ci C-,
CD C-T 001 0)
-D
oC) 00)
CD CD 00 00 CD 0
C-,)
C-f)
CD U)
Co CD 010 U)
-F---
CD CD p-i 0
1 F)
CD 0 rn co 2:3, 0
0 o -n II-CD c?Ci)
DC)
B V
(1) 0 CD0 CD0*
(IC0)
CD CD CD U)
-o 0
(0 CD 0,
0-h N)
.1 0
m Cl)o 3
(I) 0.
E
- 30.
- 0 (aa)-c
-C0) a)
U)
(U
=1 C
(U Ui U)
U E
- 30.
I Vt (U
U)
CU C
(a 2
(U U)
U) a)
2 2
(U (U
C C
0).
0).
1=-c Ca17; (U1 DU z
U)
U)
U.
0.
E.
92
- 30 0
U.)
t.
0) 0)
0.
U)CU 0.
U)CU
.i
>.r U)
U) 0
.0 0
- 3.0 CU)
CU) 0 (a
0 (9
a)
(9 a) ai
.0 d
- 0 a) o.
U)
E 1U-C C/)
9.29 u.2c.
9 Cc U)c 0-
- 2) b° o.2-a)L (1)0
-_H EEz CD E2C D,
0 0)
E:3c t 7
D.<
o 0uz D<
(9
CN U) z0 0
C CU) a)
17 Ea) a)
0 0.
0U)
U)a)
Vt 0 U) a)Z ED
-.9 DCUQ Cc:
(00oF (Ii (I) a)
000 C
I)
C 0)
.9
- g 0
0 a-)
c CD Il) 50 C-)00 (0
C a)
EC (0
C00 C
a)
U) a)
Ea)
Vt (U
(U U)
=
C (a
- 3-.-
Li U)C a)
C U)9(9 cZ cZ CD a)0)
EU)
HJ a)F
>4:
Li cI e
U) w E
0 LI (I,
0 4-C.)
L.0 4-0.0 0
0 x
C00.
0.
(N u5 0
- 3 4-Eoa)
C o
F - E 0)
U)
LLU)U)CDQ
)
<c:3U) 1 jj
=
Q C
LJ.
OF E G)LiJ C.C_
o
((U) i co U)FC) i:
- !0 d0 W
°Z3cU)
E C
2 0)
Qt3-
.E Qq)U)0 2
U) > U)
L LL Oo (N
(1
.4 U)
Ø U)U)Q)COQ oz
.2 oE o
(,)ILO C)
U) 11*
U)
U)£0
>U) w L4.
0)10 U)0 (No
?
Qci--C
..CFO.C
Co
.x o
o.2-W (N.2-C 0
U)_U)
Fs-
-Fo 0
WFU).9Z5 40 U)
U) 0 U)C0 4-.
C)
(I)
C U)0 00 C
.2 (I)
E
U)0 0
1/)0.9
- 3ci Cl)
CD U)
-C
-C C)
(1)
(9 z
i5D
>D::
Ui U)
.9 C
CD C
(.9 U)
11 U)
U) 0 CL 0
0 9
(0 U)
- 3 (U
((
CL 0) z U)
.9 U
C hi h
.2
-c U)
-C 0.
9
- 3_i
)
- 3 0.L(_
(1) 0 a::
I-3 °o
0.0 C).
5 U)CD 9I-0 E
17i Z
CQ 0.0.
0.
U)o UJ U)o rrui
0 00 91 0(1)
II 4:
D 10 0
QC)
C
.0 Ui Li 0
0 0I C) 0 C,)02
- 30 Cl)
C 0
0.
9
- 3 U-(I)
U) a)
Cl) 0 C
a)
U) d C
a.
a_
a.
.2 0
0 0
0 0
500 U)2 F-
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 10 of 12 Event
Description:
During the loss of Main Feed, a common loss of suction to all AFW pumps.
The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed. The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually. The ICW to TPCW Heat Exchanger Valve, POV-3-4883, does not automatically isolate on a Safety Injection signal. The BOP takes action while performing Attachment 3 of 3-EOP-E-0 to manually close the valve.
Time Position Applicants Actions or Behavior 10.
verifS Containment Isolation Phase A Valve Perform the following:
White Lights On VPB ALL BRIGHT a
Manua[Iy actuate Containment Isolation Phase k BOP b.
IE any Containment Isolation Phase A valve is QI closed. THEN manually close valve IF valve(s) can NOT be manually closed, THEN manually or locally isolate affected containment penetration.
11.
Verify SI Valve Amber Lights On VPB Manually align valves to establish proper SI ALL BRIGHT alignment for an injection flowpath.
BOP 12.
Verify SI RESET Reset SI BOP BOP 1.
Verify Containment Phase A RESET Reset Phase A 14.
Reestablish RCP Cooling a.
CheckRCPsATLEASTONE a.
Goto Step 15.
RUNNING b.
Open CCW to normal containment cooler b.
Stop all RCPs valves BOP MOV-3-1417 MOV-3-1418 c.
Reset and start normal containment c.
Stop all RCPs coolers 41
H B
CD
-a 0
w w
w w
w 0
0 0
0 0
0
-o
-D N) nzr 2o 1,-ti m
00 Zz D o?o o z.
(O_15*
mC°
-I CD C
Cl)
CD
-Il 0
m 1,
C) 14 Cz 2
C) 210 0
-.ini G)
- 510 DC-)
C)
-1 Cl)
- 5 Cl)
Cl)
Cl) 53-CD 01 ci G)
-D 0
C)
Co D
Co 0
r4 0
C) 0
-5 w
CD 0) 0
-5 I
i II I
I W3 Ld II IOQ I
I 0
I 3
3 I
Cl)1:
I 33 (4
I 0O N
I (DCl Cl)
I I
ac)
I 3
I CD 10:)-
(D I
zc H
0) 00 ClC.
- 5 3-)
CD0 (I).
.53:5
<CD 0-ti (DV)
. 0 CD I
I I
I I
I I
I I
I Zi 0-1 m
I I
I I
I I
I I
I I
53-Cl)
(DID
- 5 u0<
°c m!
Cl)
-u-:
jC) 53
)
3 33 i
0CD rn;i 03 o
0o 91CD
- 5 Z
0 flD Cl)
>-3 m<
):U In ZG)0 CD CD mZg 0
3 3
(Cl Q
p-FCC u
OW Cl) 0:5 D
3 I:
CD 3*<
(Dl))
CO 0
CD:5
-O (D
3
<.0
- 5
(0 CD!. 3
<)(D c:5 DC -
- 0) 0 0
z 0
0:5 0
°CoHm 0
5-2.
C (j)CD 0
(D(D CD.1JBo 1
g9 0
CDZ,CD z
<_.r5:i-o 0
CD>:5.
< o CD Cl)
N) m-5-° 0
H.
OD 3
0HD CDD-D-coD
))
UJCD 0
00 j C)D N)
]J(D 0(0 IJE;:
co=4o Co-C)
CD],
8-5-
.-oD (Dm 0
000 CD CD-CDC).
N) z.QQ 0 0
- Il
-5 (D<
CD
. C CD 8
- 3Dg (0 0 Co
.I D-o m
jjD OO_5--
CD BDCDCo Bo 0
oCo z
DOH 2
p T
U)
(A)HCDC V1-!*
t 0
CoL
-o ID:5ci 0) m0)CD>
(0 oCoCDm CD BH0
- 3-.-. C
-i CDOB
ç,
C
-o Co 0
i)
=
N) 1()
100 COD 0
CO 13 C)
I c,
t3 c3)
Iz
>CD
()
ID C
Z o
o 0) 0)
0) 110 (I) 01 z
10 ci p
0)
C.)
M CD
-o D 0 <
l <
C) to Im 0 3
=o C(-)
D CD u
o
>o
ç)
DU,25 cp3 2-
- 53
=
-a ao3 r1.
CD 4
Wj COD D
23 3
- 5 WOW WCD CD COD o2-2-
(DCD D_
Cfl
(/C
2.
(DZ 9
00 8
i
- 5
- 5 3C (0
In pCD CDLID CD CD tO 0)
-o CD x
CD 1*
CD 0
CD 0) 0
-I C)1 q.
0 C) 1 0
m Ci)o
. a
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 12 of 12 Event
Description:
During the loss of Main Feed, a common loss of suction to all AFW pumps.
The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed. The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually. The ICW to TPCW Heat Exchanger Valve, POV-3-4883, does not automatically isolate on a Safety Injection signal. The BOP takes action while performing Attachment 3 of 3-EOP-E-0 to manually close the valve.
Time Position Applicants Actions or Behavior 19.
Verify Power To Emergency 4 KV Buses and Load Centers a.
Check the 3A, SB and 3D 4 KV buses a.
Perform the following:
ALL ENERGIZED 1)
Inform the Unit Supervisor that ATTACHMENT 3 is complete with the exception of the de-energized bus or buses.
2)
IF the Unit Supervisor decides not to energize the de-energized bus or buses, THEN go to Step 20.
3)
IF the Unit Supervisor decides to BOP energize 3A, 3B, or 3D bus, THEN perform the following:
a) JE 3A 4 KV bus de-energized.
THEN restore power to bus using 3-ONOP-004.2, LOSS OF 3A 4KV BUS.
b)
IF 3B 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.3, LOSS OF 3B 4KV BUS.
c)
IF 3D 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.5, LOSS OF 3D 4KV BUS.
20.
Notify The Unit Supervisor That The PROMPT ACTION VERIFICATIONS B
Attachment Is Complete And Discuss Any
Safeguards Equipment That Is Not In The Required Condition 43
H B
CD CO CO Cl)
U)
CO
-u J
C) i 0
0 0
Co 0
0 00
-I
-I
-I
-I
-I C
C)
C) 0 C)
C-)
-U I
0 0
-U m
00 C,)
10 B
B CD Co CD
-I 1
0) 0
-I 0
0 Co CD
-o (0
-i (0
0
-4 Co m0
.p
-n
ç(IC U
p(D
C I
00 0
-D C,
Co
- 3 C,)
a 0D Co 0
w CD Co 0
CDa Cl)
()
0
-p
-I]
0 r-Co
- 00D Co D
CD 0
CD
.Q
- 1 CD0.
0 CD
-I 0) 0
-4 C,
P4.
0 C,)
-n0
-43 m
It-)
cJ 0
C
-D H
CD Z
-I]_
]:Co
,.)
Co
(.)
Co n CD CD CDCo C)
CD 0)0
- 3 Co i
0 UJO CDD CD 0
Co N) 0
-4 Ci)C o
CD
=3 Cop 0C
-a Co (0
CD H
- 3-CD C) 9, CD
()
120 Z20 Zr)
QO X
>U)
ZC)
ZCD n*2 0
0
fllCtC CD (J)G)
D 3
Z 0
m CD 121>
2121H mm CD O
C]
In
- 0>
in mz C
m z
0 0.
cC-20 CO cC 0n CD0 0
CD DC D
Ci)
CD V
CD 0
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 9 Page 2 of 2 During the loss of Main Feed, a common loss of suction to all AFW pumps. The crew transitions to 3-EOP-FR-H.1 to initiate Feed and Bleed.
Time Position Applicants Actions or Behavior ATC Manually stops all RCPs SROIATC 1 2 Actuate Si Containment Isolation Phase A ATC Manually initiates SI & Containment Isolation phase A if not previously initiated.
1 3 verify RCS Feed Path Manually start pumps and align valve(s) to establish RCS feed path IF RCS feed path a.
Check high-head SI pumps AT LEAST can NOT be established.
continue SROIATC ONE RUNNING attempts to establish SIG feed flow.
Observe CAUTIONS prior to Step 2 Q b
Venfy SI valve amber lights on VPB
- ALL return to Step 2.
BRIGHT 1 4 Establish RCS Bleed Path a.
Verify power to PRZ PORV block valves a.
Restore power to block valves.
Veiifv PRZ PORV block valves
- BOTH b.
Open both block valves.
OPEN c.
Open both PRZ PORVs ATC Manually opens both PORVs for adequate RCS bleed path.
1 5 Verify Instrument Air To Containment a.
Verify Instrument Air Containment Isolation, CV-3-28IJ3
- OPEN S ROIATC b.
Verify instrument air pressure, P1-3-1444 b.
Restore instrument air pressure using GREATER THAN 95 PSIG O-ONOP-013, LOSS OF INSTRUMENT AIR, while continuing with this procedure.
1 6 verify Adequate RCS Bleed Path SROIATC I
PRZ PORVS
- BOTH OPEN PRZ PORV block valves BOTH OPEN Crew Critical Taski Initiate feed and bleed cooling so that the RCS depressurizes sufficiently for HHSI injection flow to occur prior to completing Step 16 of 3-EOP-FR-H.1.
EXAMINER NOTE: The scenario is terminated when the crew verifies the RCS Feed &
Bleed flowpath of 3-EOP-FR-H.1 at Step or earlier based on the discretion of the Lead Examiner.
45
I0 4-,
>a)
CD L
C a) a)
a 0)
- t Cu
.4-,
4-,
CN oz
.co Ic.)
Cl) ci) j cQ o
z
.! w oz LU U) q)
a)>
C.)
0 (3
()
0 N
_i
_I
_i
_J
_i a)2 0
0 x
()
C)
C) c, a)a)
.c.C:
UI-
-c (I)=
cc 9
ma)
C:o S
o a p=a)
LJ cC 0
UC ci) if) if)
I)
D.
cci 0
0 C:
Ui Li.s i,.-.
£ LI 0
a)
LL.
.c LU U
(I (1
C)
()Q I
I C:
C)
C)
CU 0
a)
U) c Cl) c Ci.
(-
a) 0 a) a)
C_C
.0 vS a) ci,Q-ci)
LL a)
Cl)
.5, Ci)
(1)
Cl)
DC1)
U U
C) a)>
a)
.0 C-)
0 a)
U) 133 U)
.0 CD0
- 3 U)
U)
U)0
-o (U0
-J U)
.0 U)
CO0 (3
c.1 Cl)
Iii EI0 C)C0 4-,
C)
I0 4-Cu I.
a)0.0 a)
C-a) ci x
C a)0.
0.
U)C0 1-(30 9-I ci)>
C0 13 0
E0 0
(U)
C ci)
E C-)
(3 4-C0 4-C-)
ci)
C (3
Cl)
I0 a.
I C.0 4-,
C-)
(3 ci) c IJJ a0 L
CU) 0 (3
CI)
CD I0 U)c0 C-)
Cl) 4-C (30 a
0.
f) a).
a).
ci)
CD l)
Cfl o
o o
0 (3
(3 c
LL c3 C) a)
W 00 o
Z coc.2
.0 C:
ci)
CD U) i)CL c0J 5.
.5 f
9.
i5 D
C/)
.9 CD (i)(f)
._(J)
(DC-)
(3)
C:>
CDc 5
q)
.00)
Q_
(3.0 C
C-)
0 Co C
U)
CI)
-c 0
E C
CD C
o_
o_
o o
o o
Co Co Co CO 0
a-ci)
E I-
H 3
CD
-U 0
w w
03 0
0 0
-a 1
P.
P P
P c_)
c_)
cnn C)
C)
C) fllC)
<D
- r H
n1 JCD Cl, m
(IC x
cD) 0
-a z
cC)
U) m D
C)
(CD C)
C) 00 0
H° C
- E-Ifl m
z C)
-o
- 0 C.)
U)
- 3 Cn C) 0 U) 0 w
CD
- 3-U) 0 C) m0
-U m
CD U)
C.)rt 0
H 0
CI)
U)
- 3 CI C) 0
- 3 r4 U)
C)
- 3-3 CD
- 3
()
030 C)
K-0
- 3 CD
-4, C)
U)
-I-0
- 3 U)
P.
-U U)
C)
CD U)
-I-
- 3-CD
- 3-U):30.
ci) C)
- 3-z 0
H m
CD (I) 0_I
oz_
Z 3.
CD k)
D) cD-k Q.
0.
0 Ij 0
U)
(I)
C)
CD U)
C, U) z.
30 CD Z
N) 0 m
CA CD
- 3 o
CD P
03 U) r+
U U)
(0 CD CD CD N) a.
0 o-0)
CD U)
U) 0 V
V CD a.
C CD
.0 C
1 CDa.
0
-o CD U) 0-C, 0
CA 1
0-3 m
Cl,6 0
C))
p 0*
CD OD.
D.
5 FQ ZC)
- E
y c
tD C) 03 CD 0,
H c
cn r
-n CD U)
I I
(2 (I)
()
C) r p
H 0
0 CD Er 0
cc 0
H C)
CD m
D H
(CD m
P E
P
(.0
()
cDEr P. 5 (CD
(.0
(.0
- z CD.
(.3
a°-
(p
<(l, Er Er cC 9
Er C))
P
(
(t(
(0 5(
(IC CD_.
-(I-
-I-CD CD 0) 0)
j-ii C
(((CD CD D
Er (DC))
E5 CD CD P
p Er-Iii JErU)
-o
)CD$C)T CCDCD CD Er C) 0<
JDC1) 0 C
C)
G)
CD r
2 c-z oEr o
P
<D C)o0 n
-t< 93 g
on 0-C) c=-o CD jCl)
OQ r_CD z-0 CDfl Z
Zz CD CD C) zEr 0
m 0
C
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 3 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position Applicants Actions or Behavior 6.
Verify Containment Cooling a.
Check emergency containment coolers a.
Manually start or stop emergency ONLY TWO RUNNING containment coolers to establish - ONLY BOP TWO RUNNING.
b.
Verify emergency containment filter fans -
b.
Manually start emergency containment AT LEAST TWO RUNNING filter fans.
7.
Verify Pump Operation a.
At least two high head SI pumps running a.
Manually start high-head pump(s).
BOP b.
Both RHR pumps running b.
Manually start RHR pump(s).
8.
Verify SI Flow a.
RCS pressure
- LESS THAN 1600 PSIG a.
Go to Step 9.
[2000 PSIGI b.
High-head SI pump flow indicator
b.
Manually start pumps AND align valves to BOP CHECK FOR FLOW establish an injection flowpath.
c.
RCS pressure
- LESS THAN 250 PSIG c.
Go to Step 9.
[650 PSIG]
d.
RHR pump flow indicator -
d.
Manually start pumps align valves to CHECK FOR FLOW establish an injection flowpath.
9.
Realign SI System a.
Verify Unit 3 high-head SI pumps
- TWO a.
Peiform the following:
RUNNING 1)
Operate Unit 3 and Unit 4 high-head SI pumps to establish injection to Unit 3 from two high-head SI pumps.
BOP 2)
Direct Unit 4 Reactor Operator to align Unit 4 high-head SI pump suction to Unit 3 RWST using ATTACHMENT 1 of this procedure.
3)
Go to Step 10.
b.
Stop both Unit 4 high-head SI pumps 9 place in standby BOP Places the handswitches for the 4A and 4B HHSI pumps to STOP.
48
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 4 of 6 NOTE: This is an additional Attachment 3 which is conveniently at theend for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time
[
Position Applicants Actions or Behavior io.
verify Containment Isolation Phase A Valve Perfomt the following:
White Lights On VPB ALL BRIGHT a
Manually actuate Containment Isolation Phase A.
BOP b.
IF any Containment Isolation Phase A valve is NOT closed, THEN manually close valve. IF valve(s) can NOT be manually closed, manually or locally isolate affected containment penetration.
11.
Verify SI Valve Amber Lights On VPB Manually align valves to establish proper SI ALL BRIGHT alignment for an injection flowpath.
BOP 12.
Verify SI RESET Reset SI BOP BOP 13.
Verify Containment Phase A RESET Reset Phase A 14.
Reestablish RCP Cooling a.
Check RCPsAT LEAST ONE a.
Go to Step 15.
RUNNING b.
Open CCW to normal containment cooler b.
Stop all RCPs valves BOP MOV-3-1417 MOV-3-1418 c.
Reset and start normal containment c.
Stop all RCPs coolers 49
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 2 Event No.: 8 Page 5 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position Applicants Actions or Behavior 15.
Monitor Containment Pressure To Verify Containment Spray NOT Required a.
Containment pressure
- HAS REMAINED a.
Perform the following:
LESS THAN 20 PSIG
- 1) E containment spray JQ,] initiated, PR-3-6306A THEN manually initiate containment spray.
AND 2)
Verify Containment Isolation Phase B BOP PR-3-6306B
-ACTUATED.
3)
Verify Containment Isolation Phase B valve white lights on VPB
ALL BRIGHT.
4)
W any Containment Isolation Phase B valve did NOT close, manually or locally isolate affected containment penetration.
5)
Stop all RCP5.
16.
Verify Containment and Control Room Ventilation Isolation a.
Unit 3 containment purge exhaust and a.
Manually stop fans.
BOP supply fans OFF b.
Verify Control Room ventilation status b.
Manually align equipment for Control panel
- PROPER EMERGENCY Room emergency recirculation.
RECIRCULAT1ON ALIGNMENT I
NOTE BOP Hydrogen Monitors should be in seivice within 30 minutes of a valid SI signal. They should be available in a timely manner to support decision-making related to hydrogen generation in containment.
I a
a a a
a 17.
Place Hydrogen Monitors In Service Using BOP 3-NOP-094, CONTAINMENT POST ACCIDENT MONITORING SYSTEM 18.
Verify All Four EDGs RUNNING EMERGENCY START any available EDG NOT running.
BOP 50
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-302 Scenario No.: 2 Event No.: 8 Page 6 of 6 NOTE: This is an additional Attachment 3 which is conveniently at the end for evaluator comments.
3-EOP-E-0, Reactor Trip or Safety Injection Attachment 3, Prompt Action Verifications Time Position Applicants Actions or Behavior 19.
Verify Power To Emergency 4 Ky Buses and Load Centers a.
Check the 3A, 3B and 3D 4 KV buses a.
Perform the following:
ALL ENERGIZED 1)
Inform the Unit Supervisor that ATTACHMENT 3 is complete with the exception of the de-energized bus or buses.
2)
IF the Unit Supervisor decides not to energize the de-energized bus or buses, THEN go to Step 20.
3)
IF the Unit Supervisor decides to BOp energize 3A. 3B, or 3D bus. THEN perform the following:
a)
IF 3A 4 KV bus de-energized, restore power to bus using 3-ONOP-004.2, LOSS OF 3A 4KV BUS.
b)
IF 3B 4 KV bus de-energized, IH!I restore power to bus using 3-ONOP-004.3, LOSS OF 3B 4KV BUS.
c)
IF 3D 4 KV bus de-energized,
]Jj restore power to bus using 3-ONOP-004.5. LOSS OF 3D 4KV BUS.
20.
Notify The Unit Supervisor That The PROMPT ACTION VERIFICATIONS Attachment Is Complete And Discuss Any B.ir Safeguards Equipment That Is Not In The Required Condition 51
ILC-27 NRC Scenario #3 Event Description Initial Conditions:
Mode 2 3% power at MOL.
Turnover:
Raise power to 5% for rolling the Main Turbine with Control Rods. MODE 1 preps are complete.
After the Main Turbine is rolled, make preps to increase power above 10%.
Online Risk Green with B Train protected on both units.
FaeiIity-Turkey Point
-cenario 3
Op Test.:
2011-302 Examiners:
Candidates:
US ATC BOP Event Event Type Event Description I BOP A Power Range Nuclear Instrument N-42 Control Power fuse blows. The 1
TFN1CP22 ATC checks all PR NI Channels to determine the failure. 3-ONOP-059.8, (I,TS) SRO Power Range Nuclear Instrumentation Malfunction, is entered to remove the channel from service. The SRO will address LCO 3.3.1.
(R) ATC In accordance with 3-GOP-301, raise power to 5% for rolling the Main 2
N/A Turbine with Control Rods. MODE 1 preps are complete for the MODE (R) SRO change.
TFK1A12T 3A CCW Pump trips due to breaker failure. 3-701G, PC-3_611 isolation, is TFK1A61 1 (C) ATC inadvertently closed which prevents the Auto Start of 3B CCW Pump. The TFK1 S61 1 (C, TS) SRO ATC uses the ARP, 3-ONOP-030, or 0-ADM-21 I to start 3B CCW Pump.
Technical Specification 3.7.2 is entered.
4 N/A (N) BOP Swaps from 3A to 3B Condensate Pump using 3-NOP-073, Condensate (N) SRO System.
IAF 1479 (I) BOP 3A S/G Bypass Feed Valve Controller drifts causing the valve to open.
5 After noticing the S/G level change, the BOP establishes 3A S/G control (I) SRO band with the S/G Bypass Feed Valve per 3-GOP-301.
1AH244G (I) ATC PCV-3-455A Spray Valve Controller causes valve to fail partially open.
6 The ATC mitigates this event by manually operating the valve per ARP, (I) SRO 3-ONOP-041.5, or O-ADM-21 1.
7 TFKXSMA (C) BOP The 3A TPCW Pump shaft fails. The BOP will start the 3B TPCW pump using the ARP, 3-ONOP-008, or O-ADM-21 1 to maintain plant operations.
(C) SRO A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew 8
TVSBVL14 (M) ALL responds using 3-EOP-E-O. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B S/G. After 3B S/G isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
TFL3SIA2 (C) ATC During the performance of 3-EOP-E-O, the B Train of SI fails to actuate.
(C) SRO The ATC manually actuates SI to initiate Train B SI.
10 TFSWX6C (C) BOP The 3B MSIV fails to close in AUTO. The BOP manually closes using (C) SRO of 3-EOP-E-O.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1
ILC-27 NRC Scenario #3 Event Description SIMULATOR SETUP IrISTRUCTLQNS.
1.
Reset to IC-5 (3% MOL) or other IC with correct setup conditions.
2.
Place Simulator in RUN 3.
Open and Execute ILC27SCN3N.lsn.
4.
Start 3A COW Pump.
5.
Stop 3B CCW Pump.
6.
Trigger lesson steps:
SETUP
- B TRAIN OF SI FAILS TO ACTUATE insert TFL3SIA2 TRUE delay=O ramp=O on=O off=O SETUP
- 3B MSIV FAILS TO AUTO CLOSE insert TFSWX6C true delay=O ramp=O on=O off=O 7.
Store IC with initial conditions setup if desired.
8.
Place Simulator in freeze.
9.
Provide Shift Turnover Checklists
- 10. Perform Simulator Operator Checklist
- 11. When ready to begin, place Simulator in RUN.
2
ILC-27 NRC Scenario #3 Event Description FACILITY OPERATOR INSTRUCTLO4S EVENT I A Power Range Nuclear Instrument N-42 Control Power fuse blows. The ATC checks all PR NI Channels to determine the failure. 3-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction, is entered to remove the channel from service. The SRO will address LCO 3.3.1.
When directed, Trigger EVENT I
- N42 PR NI CONTROL POWER FUSE BLOWS.
o insert TFN1CP22 TRUE delay0 ramp=0 on=0 off=0 SM
- If directed, respond and acknowledge the failure of Power Range Nuclear Instrument N-42.
- If directed, respond and acknowledge the failure of Power Range Nuclear Instrument N-42 and to write a PWO for troubleshooting.
EVENT 2 In accordance with 3-GOP-301, raise power to 5% for rolling the Main Turbine with Control Rods. MODE 1 preps are complete for the MODE change.
- If directed, acknowledge power increase.
- If directed, acknowledge power increase.
SYSTEM DISPATCH
- If directed, acknowledge power increase.
ENGINEERING
- If directed, acknowledge power increase.
CHEMISTRY
- If directed, acknowledge power increase.
EVENT 3 3A CCW Pump trips due to breaker failure. 3-701 G, PC-3_61 1 isolation, is inadvertently closed which prevents the Auto Start of 3B CCW Pump. The ATC uses the ARP, 3-ONOP-030, or 0-ADM-21 1 to start 3B CCW Pump. Technical Specification 3.7.2 is entered.
When directed, Trigger EVENT 3
- 3A CCW PUMP BREAKER TRIPS.
insert TFK1 S611 TRUE delay=0 ramp=0 on=0 off=0 insert TFK1A61 1 TRUE delay0 ramp=0 on=0 off=0 insert TFK1A12T TRUE delay0 ramp=0 on=0 off=0 SM
- If directed, respond and acknowledge the failure of 3A CCW PUMP TRIP.
- If directed, respond and acknowledge the failure of 3A CCW PUMP TRIP and to write a PWO for troubleshooting.
3
ILC-27 NRC Scenario #3 Event Description EVENT 4 Swaps from 3A to 3B Condensate Pump using 3-NOP-073, Condensate System.
EVENT 5 3A SIG Bypass Feed Valve Controller drifts causing the valve to open. After noticing the SIG level change, the BOP establishes 3A SIG control band with the S/G Bypass Feed Valve per 3-GOP-301.
When directed, Trigger EVENT 5
- 3A S!G BYPASS FEED VALVE CONTROLLER DRIFT.
insert TVFV479 0.500000 delay=0 ramp=60 on=0 off=0 SM
- If directed, respond and acknowledge the issue with 3A S/C BYPASS FEED VALVE CONTROLLER.
- If directed, respond and acknowledge the issue with 3A SIG BYPASS FEED VALVE CONTROLLER.
EVENT 6 PCV-3-455A Spray Valve Controller causes valve to fail partially open. The ATC mitigates this event by manually operating the valve per ARP, 3-ONOP-041.5, or 0-ADM-21 1.
When directed, Trigger EVENT 6
- PCV
- 455A SPRAY VALVE CONTROLLER PARTIAL FAILURE.
insert 1AH244G 2.5 delay=0 ramp=120 onO off=0 SM
- If directed, respond and acknowledge the failure of PCV
- 455A SPRAY VALVE CONTROLLER.
- If directed, respond and acknowledge the failure of PCV
- 455A SPRAY VALVE CONTROLLER and to write a PWO for troubleshooting.
EVENT 7 The 3A TPCW Pump shaft fails. The BOP will start the 3B TPCW pump using the ARP, 3-ONOP-008, or 0-ADM-21 1 to maintain plant operations.
When directed, Trigger EVENT 7
- A TPCW PUMP SHAFT FAILS.
insert TFKXSMA TRUE delay=0 ramp=0 on=0 off=0 EVENT 8 A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-
- 2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SJG. After 3B S/C isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
When directed, Trigger EVENT 8
- 3B MAIN STEAM LINE BREAK INSIDE CTMT.
insert TVSBVL14 0.5 delayo ramp=120 on=0 off=0 4
ILC-27 NRC Scenario #3 Event Description SCENARIO QUANTITATIVE ATTRIBUTES Target Quantitative Attributes (Per Scenario; See Section D.5.d) 1.
Total malfunctions (58) 5 2.
Malfunctions after FOP entry (12) 2
- 3. Abnormal events (24) 4 4.
Major transients (12) 1 5.
FOPs entered/requiring substantive actions (12) 2 6.
FOP contingencies requiring substantive actions (02) 0 7.
Critical tasks (23) 3 CRITICAL TASKS 1.
Trip RCPs due high Containment pressure and Phase B Isolation of CCW to RCPS prior to entering 3-EOP-E-1.
OR Ensures RCPs are tripped due to a loss of subcooling during a LOCA prior to completing Step I of 3-EQP-E-2.
2.
Isolates the Faulted 3B SIG prior to exiting 3-EOP-E-2.
(Closes 3B Main Steam Isolation Valve) 3.
If RHR Flow less than 1000 gpm, stop the RHR Pumps within 44 minutes of their start signal. (3-EOP-E-1) 5
Co CO C))
Cl)
Cl)
J C) 0 Cl) 0 0
0 ii
-I
-I
-4 C)
C)
C)
C, LC.)
_..)
i 0
CD Ct 0
0 0
C)
(5 CD I
C C
H 3
CD
-a 0
U)
C..
0
- 3
-o
-o C)
U)
- 5 I-U) 0 C..
0
- 3 U) 01 w
CD
- 3-U) 0 0
(CD (IC (5
(5 0
0-(5 (5
C C) 3-c U)-,
CD 3Cn 2g 0:3 CD
-0 U)
CD C
C,,
C,,
-Il C
CD 0
0 DC0 CO CD C
DC C
CD 0.
CD 0
0 CD CD C
00 CD rJ0
-U z
m rn Ca co>
CD
- u C
a m
(5 C
C CD 0
-*I 30 CD 0
3 (5*
Z C,)
-h=
(5 C-
Ca-51 0
rn 5
-U.
m 510 (C) 0z0
-El 0
(5 (0
cxD
-u 0
CD I
C,)
- 5 CC CD 0
l\\3
- r 000>
rzz mmm OO0>
uZ cn01
-.C,)
0 cp 11(
DoC)
<H Q,4a C<
°asQ ar H
0 (3
- 5-0 n
0
)
a3 C
CD 0Z3 C,)
C CD 00 U)
CD CD C) 0
-hz p3
-o z
0 0
- 3
-u 0
CD Q
U)
CD
- 30 C,)
Co
- 3-C)
- 3-z 0
- 3-0)
- 3:3 CD
- 3-0) 1
- 3-CD
-h 0)
C
-I-C CD
- 3-U)
U)
-3 C)0
- 3
-h
-3 U)
C.-
0
_C C,)D CflCD
- 1-H-n o
02.
-u
=
f*)
Cl)
H
- Q CD m
C.
0)
CD 0
II 0
0 C,)
3 CD CD o
CD 0
0 Cfl 0
0 0
-o II CD U) zp P30 9
C)0 P.)
0) 0 CD
- 5 U)-,
0z p
CA) m CD
- 5 z
p
-D U)
CD CD
-A 0
-4, Cii w
-o c-fl z
CI, U) p..)
00 a) 0
-I-0
-oi3 0
CD 0
Cii CI) 0 O
- 5Z C) 0
-U ii; 0.
CD (/)-CD CD tJ 3
D CD o
i-.-
- U) ;J-5 z
0_ ci.
0 U)
CD
- 3->
- 5 0 00
ç)U)
Q.U)
-A 0 CD CD
- 3 0CD ci
- 5* 0)
CD 5
- 3 U)
U,
C-.
CO-.-C CDCD
- 0*
-o CD Co 1:5 U)
- 3 0 ZZ CD 0
C;.) 1.J P.)
Z 0
- 3
,., COC D.i 0 0 CD C0 CD CD
- 0) ri ::J -
- 5 U)C U)
CD CD U)
CD 0 0 ZO 0
U)
U)- 6_*
CD
-j H
CD 10 0
-o CD C
CD
.0
-I CD0.
0
- 0 CD 01 C,
0 (I)
-n 0
m(p
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-302 Scenario No.: 3 Event No.: 1 Page 2 of 5 Event
Description:
A Power Range Nuclear Instrument N-42 Control Power fuse blows. The ATC checks all PR NI Channels to determine the failure. 3-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction, is entered for initial response. 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, is used to remove the channel from service.
The SRO will address LCO 3.3.1.
Time Position Applicants Actions or Behavior 4.0 IMMEDIATE ACTIONS 4.2 Mode 2
- Startup S ROIATC 4.2.1 Malfunction of ONE channel:
1.
None 5.2 Mode 2
- Startup 5.2.1 Malfunction of ONE channel:
1.
Maintain manual Rod Control.
2.
Place the DROPPED ROD MODE switch for the failed channel in the BYPASS position.
3.
Place the applicable ROD STOP BYPASS switch to the failed channel BYPASS position.
4.
Transfer the UPPER SECTION comparator defeat switch to the failed SROIBOP channel.
5.
Transfer the LOWER SECTION comparator defeat switch to the failed channel.
6.
Transfer applicable POWER MISMATCH BYPASS switch to BYPASS the fuiled channel.
7.
Transfer the COMPARATOR CHANNEL DEFEAT switch to the failed channel.
8.
Perform the following within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of the failure determination:
a.
Trip the Power Range bistables by removing the INSTRUMENT P0PIER fuses from drawer B of the failed channel.
NOfg I
I The Reactor Protection System bistables associated with the failed power range channel SROIBOP will be in the tripped condition when its bistable test switch is placed in the test (to the right) position as indicated by the red trip LED on the Channel Status Light section of the EAGLE I
21 Test Panel being ON.
I
.I 2
m z
m z0
-I m
C)
-0 C)
CD CD0.
0 0
m CD 4)
Ci)
Cl) 4J Cl)J0 0
W0 0
0 CD) z 12 r-f H
3 CD 0
0 Co 0
-o 0
Co U) 0 0
U) 0 U:
CD Co 0
1 0z F.)
33 0(j)
CD_J CD CCTC 1J 0
CD
- 0
- 3 CD 0-D-
-U-.
CC 00 D
Ow C
ur mm
CDf-z.
- 5 30 CD CD:3
<CD OCD CD 0Cfl 0.
(D..
0 0.CD D
<CD
- 3 U__I w
23 otT o
-CD C:
00 o T o
Ill.
U, DC CD 0
OCD :t
- m CD z r
-o 0 >
mr
.V-0 DC 0 j
o Z3 _
1 (D
g (IC CD CD0.
>C 12.
ZD CD o m 0
- 3
- 5
- 2! 0 C:
XCD
.F
.0
_0 (C
DC 0 0
CD (I)0._I DC: m c
uo cf,0 I
-F, CDCD CD 0 !P.
- 3 0(I)
C:
- 3.< 3. 0*
C,.)
CD C) 0 ICCCD
!!?.
c0
-..-tJ
°m o r o -
03 CD
- 3
0CD 0
CD<
- 3CD (0
0(1
- 5CD CD DC 0
CD
- ij (I) mc
- 1 CO (Pz CD
-IX C:
O.
Mt) 0
-n C
- 3 m>_
- 3.
C,)C4 (1)
-U2.
- 3 Dc
mIC m
C-
-C 3
(,CICD Z
CD
-I.
0 H
0)I00 CD)
CD)
H Co CD) 1 C)
-I 0D Co C
- 3 Co.
0D C.))
CD VZ0 CD0 I
DCD CD -ox CD CDCfl
-ICoO
-I.
0--*1 0 z C,
C)CD 00
-CD CDCfl
.0 CD n
CD Co OCD 0
(0 C
3
-C C
-I 11 C
C I) 0?H
- o CD 3
(I)
CD Q<
CD Co z
E!U p
Coa CD D
c:!-.
M Q_
o_
0 CD Co Co
I c,
j c
Co C) j CD D
D U
0 F\\j Q-OCD CD)
-3
- CD)
-o
° u
Q Co 0
0 CD CD
- 3 CD
- 5
-+(D
- 3 CD i-.-
CD n
- 3
- 3.
CD o
s C
CD 0
o_
?5 C
- 3 Co Co CD
- 3
Ci)
C:.
Co CD
C Co C
CD CD CD Z) m CD CO I
- 3 CD Co Z
0 CD Co ZZ
çD 0
Z 0
Ci)U
-3 I
I CD0 0
Z 01 0
ZI (0
00-
<co U
D 0
CDC0 (0
0 CD CD CD
- s CD)
CD(0CD ca, CD 0
8 O* z 3
DC 0
0 U)
Co
CD Co H
9--
CD H0 Cl)
Cl) 03 Cl)
(.J (J
(J (J
4..)
I.)
I..)
U k.
I.)
4..)
U
()
()
I I
I I
4-..)
U.)
(
c5
,- (f2 o
o 0
0 u-U.)
0 (1)
(F (F
(F IC 0
0 t
C (F
F)
F)
(
c (ID H.
C/D(JQ H
0-(CD F)
(F (ID CD 0.
C CD
.0
-I CD0.
0 CD
-I Co 0
C, 0
Cl) 1 0-3 m
Cl)
C0,
ci)00 I
ci) 00 0
4-,>
-UC (U
4-.
(I) 4-,0
- i:
0 C?
U0 C,,
I ci)0 C0 4-,
0>
ci)
U)
-C 4-.
U) c)
ci)
.4 U
Q U)
Iii 0
U U)
C0 ci I0 4.
U) a)00 a) a)
x Ca)0.
0.
I a I
I OcQ)iC)
I Ci)
I j
-2 I
I
.2 I
.2 Oc I
I 2z I
-0 C)
.2 I
I cl)
I rCD0 I
0 ci)C))
I E.
-0 I
Ocz IL 0 -;
0
()
I CO Ii l.U ci)
LU Q).C)
U
.2 1
UC)
IC Ui I
i:
F 0
Z
.2°-
i)
I CD CD
.2 I
I I
-2 (j
CD C:t; C))
I
I
- Cc1)
I
.O-2 g
.2 0
QZ-$
°-
.2 co5 I
I
-o I
I CDZ 0
C)*
i)Z E°2 (0
CD I
I
- 5):
?
Co I
Occq F
z.2 I
I Fl)
C
-a 4
I C
CU C,)
U) ci) 0 U)
CU-LO o c (N
-:o ao C
ci)
.2a)
Lii L.
- 0 C,)
-:o (E
Z
C) 0 CW 5__
4-i__
CU CU C
(I) c (U 0 3w (N
oU o
CUQ o
w C))
°.E C) -
C-,
- 0
-D QC)
C)
C/)
tc)
CO
C) \\Q C
c09.
C)
CO C)) c-,
0 F.1CJ 0
U)
C U)
I-.
4-.
0 CU U) 15
-oC0 C)
C) 0 4-,
ci)
OC U-a)
Io 0) oa)
CU n (DO Ctl<
ci)
U)
CD 4-(i_C C
CDU)Q)
C 0 (U
C a) 0)
,C C
U) o.
4 4__
- - 0 o
> c 4- >
Ca o
C U)
Q_ U)
C ci) 0. CU L
cLLC) 4-0 CU
-C a) 40 U)C0 4-.0 U)
C CU0 a.0
- a a I
I I
,g I
I J-0 I
C)-2
. -0 I
-C)
I I s I
.2ci cci I
I ci),
I I
Dq I
C))q I
I I
10 I
z :
I I
i
-° i
I C)
I
..2.
C)
I
- q 0
)
0 C)
I DCoC)
I o
C)
I I
I 2.2
-Q C,)
I
.2I C,) 0(0 I
HI C
4-Fl) 4--
-Q 4-a 4-a0 (U
U) 4-C U) ci)
CU
- 0 0
CU U-C)
LO 0
(1)
C/)
-c U)
CiC (U
-U I000 CU C
U) 0 4-,
-U a)
U)
U) 4 ci) 00.
4-0 15 (U
U)
(U Cl) ci)
C.)
U)
CUa
>1 ci)
-C.c0 0
.4-4 a) 4-(U
-o U) 4-a0 D
-a CO
.4-,
C)
CO cO z
-dI)
Cl) ci)
-C
.4.
C
.C C.)
.4-.
CU Fl).t
.1.
C E
U)
U)
CU 0
4-I L..0 0
C.)ci.
oE o
- =0
- I_
>1 4-CU wI0z wz x
Lii C.,
Co 0
IS Cl) 0Q U_
U) a)
E I-Ci C) 0 0
0 0
D U)
U)
U)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 2 Page 2 of 3 Event
Description:
In accordance with 3-GOP-301, raise power to 5% for rolling the Main Turbine with Control Rods. MODE 1 preps are complete for the MODE change.
Time Position
{
Applicants Actions or Behavior BOP 3.
Align the SDTA controllers as follows.
(Reference Attachment 5 for operation of the SDTA controllers.)
a.
Ensure two SDTA controllers are in automatic.
b.
Ensure one SDTA controller is in manual and maintaining Tavg two to four degrees higher than Tref EXAMINER NOTE: Attachment 5 is on the next page as a reference.
rN0TES1 I
I I
The intent is to have a/I three SDTA valves throttled open to maintain Tavg greater than Tref and reactor power below P7 (Target is 5 to 7 percent).
I I
I The SOTA controllers should be adjusted so that the valves do not close at the same time, but operate on a staggered basis and throttle closed as the main generator is loaded.
A difference of approximately 20 psi should be used as the initial staggered setting.
I I
The SDTA controller settings may be adjusted in small increments as necessary to maintain steam flow from all three steam generators.
The steam generator with the lower setpoint will require additional feed flow.
c.
Adjust the setpoints for SDTA controllers in automatic for staggered operation.
d.
Adjust the setpoint for SDTA controller in manual to 1005 psig.
e.
Use the SDTA controller in manual to make minor adjustments to Tavg, as necessary.
EXAMINER NOTE: Once Plant is stable at 5%, Proceed to Event 3
- 3A CCW Pump tripping due to the breaker failure.
5
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 2 Page 3 of 3 Event
Description:
In accordance with 3-GOP-301, raise power to 5% for rolling the Main Turbine with Control Rods. MODE 1 preps are complete for the MODE change.
Time Position Applicants Actions or Behavior ATTACHMENT 5 (Page 1 of 1)
OPERATION OF THE STEAI DUMP TO AL\\IOSPHERE CONTROLLERS A.
To Go to MANUAL from AUTO Mode of Operation 1.
To place the controller in MANUAL. press the M key (Yellow LED) until the key illuminates indicating MANUAL mode of operation.
2.
Note: When the controller is in AUTO. the MANUAL setpoint follows automatically so no adjustments are necessary prior to placing the controller in MANUAL.
B.
Adjusting Output in MAI\\TAL Mode 1.
To raise output on a controller in MANUAL. press the MV Increase key on bottom right of controller (arrow points to the right).
2.
To reduce output on a controller in MANUAL. press the MV Decrease key on bottom left of controller (arrow points to the left),
C.
To Go to AUTO from MANUAL Mode of Operation 1.
Match controller setpoint (SV1) with Steam Pressure (PV1) indication using the SV Decrease key on the right side of the controller (arrow points clown) OR the SV Increase key on the right side of the controller (arrow points up). as appropriate.
2.
Depress the A key (Green LED) on the controller until the key illuminates.
3.
Observe the valve demand indication (MV 1) on controller.
If necessary to prevent oscillating valve demand, return controller to MANUAL Mode.
D.
Adjusting Output in Auto Mode 1.
To raise the setpoint at which a controller is controlling in AUTO. press the SV Increase key on the right side of the controller (arrow points up).
2.
To lower the setpoint at which a controller is controlling in AUTO, press the SV Decrease key on the right side of the controller (arrow points down).
6
Cl)
CO o
C,)
0 m
0 0
C)
C) 0
-Uni
-40 C)
I 0z C) 0)
I-..
LU LU C)
CD 0
C))
C)
C-)
C)
-o 30 0
CD LU LU Cl) 0
-1 3
CD 0
0 C,)
0
-o
-o C-)
LU
- 3 (I) 0 0 0
- 5 (I) 0 CD CD
- 3-LU 0
-4 F-(_)
o0z CD c c
CD 2!
CD -O
-D
=
H3°° 0
£ 0z CD
- 3 30 o
CD
Z3 0
<:3 JJ 1
CD0 CD
-h CD
-s CD 0
(DO e
(30 C) 0300
- 5 CD
- 5 0
C) 00
- 5 (0
0) 0 CD
-5 LU
-h C
- 50 0
- 5 0 0 u
U ni m -Z
,i
,i D
m m
CD
- U -;u
i 3m 00 (DQ)
H (i.)
Co 0
M ii C) cb D° c,j CD P
t3 C)
C.)C CDCl 3
CDD Q
t3 C)
CD 0
CD o
D CD Q(j CD g) 0 z
0 D
Wo,,
0.
CDa 9
C()
CD 3
- 3
-C)
J)-C)
CD C
C (JO o
flC)
- 3
- 0-(DCD CD CD C)-
CD
-C)
CD (JO (0)
C CD 00 0
CD CD LU C
0-h C.n)>
C-)
C)
-U C
0 C
CDm CD t_)
(0)-
(n-fl II Ix leo TH (10 y
CD C).
(JO
<to
.0
- 0
- 0-(0) 0 1
-C)
(JO (C)
CD
-U0
(.,.0
-z C)--,
3 m
0) 0 C
CD 0
-o (JO (JO CD C)
- 1-CD CDC) 0 3
C))
CD C)
C)
-U C30 0.
0 CD (I)z0 I
0)C 4--
0 0 LU 0
CDa) z p
r\\)0-C))0 N)
CI) 0 CD
- 3 LU
-5 0z p
C,)
m CD zp C.)
-U LU (a
CD 0-h
-n CI) 7CD CD
- -1
)1 -n 1LU H o 2.
- 0) =
m-5_ C m
-I cD3
oD-II 0ai
II CD
..,00 0(I)
- 3
Cj,CD Hfl
-I,
>z
- C.)
-H, Cm a-C)
CD 0
Il-U Q
0 0>
CD
- 3 CO o
m ZLU <
a CD
,-d <
4-,-
4 CD CD O
0<
- 3.
-c2---
00
- 5 D0C,)>
_0.00 0
0-s C
LU CD 3 C))
LU m
3D QCD (I) 0>0
<c C
CD 3g
- -CD
-LU CD,.
0 CD 0
- C) =
0 C)C CD H
.3o-0 G) 3- -
- 5CDC)
---I N) j (DO 0
- 5 4-
-- D LU V
V CD x
CD.
1 CD 0
V CD LU
- 0 0
C) 0 Cl) 1 0
m Cl) 3 C))>
C C) o (D
0)-.
3:5 D
0 0:3
_4 CD 0) 0 0
0 0)
CD
- 53 Cl) 0
- 5
-U LU:5 CD 0
LU:5a mm-u 5-U
0 a) a)
.)
a)a)
D
.0 2
ci Q_
>0 a) 00
>0 so::
0uJ Ow a)
U)S C
N E) uJ 2W OC a)fl O-c
>a
>co 00
ci c
0 C)
>s G)
.0.
U) 0 C,)
U 0..
00 N
U c,c5) cc 0
0 Cu 00 cF C3 o
.D QcCl) z a.
C) ci)
CU C
0i I..
- 3 0t o QCUL a).
co o
0 a)
D Ca) o (a
C a)Wa))
LI.
C)c.
C*;1 9
U)w E
L.0 U
Co C0 C.,
I..0 L.a, 0
a)
L.
- 30 a,
x Ca, cv)
C - -o 0
(I)
I 4.
a U
.C
...C r
U I-0
(N (N
ci)0)
(_ia)
Cu D.C CL
.1U (9
.S
-o E 3 r--.:3a) cv) oZ
- 300 0c C
Cl) 0 (1)
(1)
UI
-H U
CI)
CO
- 3:3 Z
13<0 U 00
.2 a_.c c
cu Ucv)
C (I) 00-(N i
-o 200 (N
0Z 3(Y)
D9 ci) 4-
.oa.
F-;-
C.O a.
UZ o
w.o I
I I
I I
I I
A a)
IZ I
I 2
I a)
-0 I
I I
0 C.,
I I
I I
I I
I I-I 0.)
a)0) 0.
I-.0..
0 a) 242 o 0.
ow (I)
D U)
N IL)N 12 a) m
> a<
>0 a) o0 0)>0) 0 U
-c ci) cci 0
U)C0 -,0 U
C U0 a.0 I03:
3:0 a, o.t 2420
.12(5 CLCJ a) 0)
0) a)
CO CO a,
0) 0)2 C 0
_Io c,.o d
(0 a).
22l a) a)
01 C
00 C)
C a)C0a)
- E01, o
(I)
C a,
Cu0.
C 0
a, 4-C0 U) a, Cu0.
1-
- 30.
a,
-cI w
I0z wz w
0 0
I-I.
15 0
0 0
0-.
U)
U) ci E
o_
0 0
I cri 0
0 0
U)
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011 -302 Scenario No.: 3 Event No.: 3 Page 3 of 7 Event
Description:
3A CCW Pump trips due to breaker failure. 3-701 G, PC-3_61 1 isolation, is inadvertently closed which prevents the Auto Start of 3B COW Pump. The ATC uses the ARP, 3-ONOP-030, or 0-ADM-21 1 to start 3B COW Pump. Technical Specification 3.7.2 is entered.
Time Position Applicants Actions or Behavior FOLDOUT FOR 3-ONOP-030 1.
TOTAL LOSS OF CCW FLOW A.
Manually trip the reactor. verir reactor trip using the EOP network. THEN stop the RCPs.
B.
Isolate letdown ami excess letdown.
C.
E stablish one charging pump running at maximum speed AND dispatch operator to establish emergenc cooling water to one of the remaining two charging pumps using.
Monitor RCS pressure closely while running charging pump at max mum speed.
D.
WHEN Attachment 1
is complete.
THEN ooerate charging pump supplied with emergency cooling as necessary to maintain RCP seal cooling.
2.
LOSS OF CCW TO ANY COMPONENT component cooling water flow to any component cooled by CCW is lost. THEN shut down the affected component.
3.
CHARGING PUMP EMERGENCY COOLING CRITERIA IF Cooling Water is NOT available to charging pumps. THEN charging pump operation shall be at maxiimun speed until cooling is restored from CCW System or using Attachment 1.
4.
CCW PUMP STOPPING CRITERIA any Component Cooling Water Pump is cavitating, THEN stop the affected Component Cooling Water Pumps and place in Pull-To-Lock.
5.
REACTOR TRIP CRITERIA IF tripping a RCP is required. THEN manually trip the reactor prior to stopping the RCP.
6.
RCP STOPPING CRITERIA any RCP bearing temperature annunciator alarm actuates ANT) its associated motor bearing temperature is greater than 195F. THEN trip reactor and stop the affected RCPs.
7.
CCW System operation once CCW System Hdr has been restored shall be within the operating restrictions of 3-NOP-030 summarized as follows: [Commitment - Step 3.3.2]
CCW Pumps. Heat Exchangers. and FlowsiLoads.
N-i CCW Pumps (where N = number of CCW Hxs aligned to CCW)
All CCW Hxs in service when RHR in service with only 2 CCW Hxs in service, place 2 CCW Pumps in Pull-To-Lock.
Maximum of 5 out of 6 CCW Heat Loads.
9
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 3 Page 4 of 7 Event
Description:
3A CCW Pump trips due to breaker failure. 3-701 G, PC-3_61 1 isolation, is inadvertently closed which prevents the Auto Start of 3B CCW Pump. The ATC uses the ARP, 3-ONOP-030, or 0-ADM-21 1 to start 3B CCW Pump. Technical Specification 3.7.2 is entered.
Time Position Applicants Actions or Behavior 3
Verify Flow In Both Component Cooling Perform the following:
Water Headers
- NORMAL a.
IF COW flow to RCPs can NOT be FT-3-613A for header A established, THEN manually trip the reactor AND verify reactor trip using the FT-3-61 3B ror header B FOP Network, AND then stop all RCPs Q perform the following:
SROIATC 1.
Isolate Letdown and Excess Letdown 2.
IF any charging pump is runnirg.
operate at maximum speed until Attachment 1 is completed.
3.
Dispatch an operator to establish emergency cooling water to desired charging pump using Attachment 1.
NOTgS The top of the component cooling water surge tank divider plate is located at approximately 25% indicated level.
If a cross tie valve between the units is leaking or open, the surge tank on the opposite I
unit may be experiencing level control problems.
S ROIATC If in Modes I through 3, and CCW System level is NOT maintained within the COW I Head Tank. restore CCW System level to be within the COW Head Tank within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I I
LI-3-613A and LI-3-614A are NOT overlapping (i.e.. Ll-3-614A will go off scale low before L1-3-613A comes off its high peg with decreasing level).
4 Verify Component Cooling Water Surge Perform the following:
Tank Level Being Maintained 1.
Open Component Cooling Water Surge a.
Component Cooling Water Surge Tank Tank Makeup. MOV-3-832 as necessary Level. Ll-3-613A to add makeup.
GREATER THAN 25%
2.
IF Component Cooling Water Surge Tank Level can NOT be maintained, AND THEN perform the following:
SROIATC STABLE OR INCREASING a)
Trip the reactor perform 3-EO P-F-U, Reactor Trip or Safety Injection, while continuing with this procedure.
b)
WHEN rector verified tripped, THEN stop all RCPs.
3.
Observe NOTES prior to Step 8 and go to Step 8.
10
H 3
CD (I)
Cl)
Cl) 0 U) 0 0
0 2-g I
H
-1 C_)
C)
C) 0z CZ 0**
C>
a.
a.
CD 0
C,
-I.
D)CD D
C,
-I CDz0
-I C,
-I CDa.
C, CD DI
-I 0
ca C
a.
CD
-I CD DI C,
0=
Cl,
-I,
-S0 Cl, 0
ou OCD
=ci)
(-4.
<0
<H
-CD CDC)-,
- 0).
C.<
C) cI, CD0
-h C,
U) 0
- 5 C,)
1) 0 CD CD (A)
N) 0
-S
-I.
CD C-)
0 3
-o0D CD C) 0 DC C<
(;J (C
()
D DC
DC C
0 C)
CD 2.
0 CD CD D
-H (C)
C) m DC C)
CI) a.
CD.
C)
Z C) 0 m
-D C)
U)
Ci)
C) r 0 D
U) 0 QJ CD
- 3-U) 0
-S 0
I H
CD Cl) z p
N)0 0)
C)
CD:3 U) 0z 0
(A) m CD
- 5 z p
(A)
-U U)
(0 CD (7
0
-h a.
DC CDCD CD c
cz c
CD Cr, CD -
o o
0 (C) 0
I I
I D
)<
(DC0 C)
CD (0
(,C 0
DC Z3 0.
C)
N) -
CD C)OCD CDH OCDO X0 3
DC 0
C))O 3
C COCCCZJO
_.CD CTC CD3 (0(fl -
DC<ZtC
-DCDC 3.
PCCD0 o
DC(D (D3.C O
D (D
,C0 0
03.
(DNO O,C DCCDDC3.
CD
_(n<
D CO CD 3.
DC (C)
(11 DC (I)()
0(C) o CC).
g()
l CD am DC (D
(D Cl)
DC CD CD DC0.
CD (C)
PC C) 0 0
CI)
CD
-D C-)
o m
ZU) <
CD
- 3 LJCD 0D
.CD CD O
- 3.
00 5 rjC)
_C, C)
-ID 0-CD]J
C D)CD3 l-LT3 (A) U)
m DD QCD (1) 0>0
<CC CD 3 r g 0 -CD CU)
CD
(.CD C)
Jh. C)
C) 0 C
CD C
3 0-C)-
G)
Z3 4J
- 5CDQ)
C)
C)IØ)
- 5fI CDCn
- 5
5.- :r U)
CD 4-
-o0 CD x
CD
.D C
-S CDa.
0 0
CD
-S DI 4..
0
-S C,
4-4.
0 C,
1 0
m Cl)6 0*
D C)
HI Cf)
(Do
-DC)
C,)
Zr (C)
C))a.
CD (C)
(C) 0 3
C))
PC CD C
0 CI)
CD
-O p
p C
Ci) 3.
DC (I)
Zr 3.
CD 0
0.
0 0-00
(
-C)
C3 C),)
CO-I 0
SO 0o-C)CD DC0-0 Q(fl (C)Z(T Zr o°ODC (D0 (DO COHCDO 0
3.
00 CD
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 3 Page 6 of 7 Event
Description:
3A CCW Pump trips due to breaker failure. 3-701 G, PC-3_61 1 isolation, is inadvertently closed which prevents the Auto Start of 3B CCW Pump. The ATC uses the ARP, 3-ONOP-030, or 0-ADM-21 1 to start 3B CCW Pump. Technical Specification 3.7.2 is entered.
Time Position Applicants Actions or Behavior PLANT SYSTEMS 3/4.7.2 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 The Component Cooling Water System (CCW) shall be OPERABLE with:
a.
Three CCW pumps, and b.
Two CCW heat exchangers.
APPLICABILITY:
MODES 1, 2. 3, and 4.
ACTION:
a.
With only two CCW pumps with independent power supplies OPERABLE, restore the inoperable CCW pump to OPERABLE status within 30 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The provisions of Specification 3.0.4 are not applicable.
b.
With only one CCW pump OPERABLE or with two CCW pumps OPERABLE but not from independent power supplies, restore two pumps from independent power supplies to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With less than two COW heat exchangers OPERABLE, restore two heat exchangers to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SRO Enters 3.7.2, Action b for 2 CCW Pumps without separate power.
SRO refers to 3-ONOP-030 and recognizes CCW was restored by SRO starting a standby pump. The following steps will offer minimal direction for current lineup and situation. [This is commonly accomplished with skill of craft in 3-EOP-E-0.]
5.4 Transfer of 3D 4KV Bus from 3B 4KV Bus to 3A 4KV Bus CAUTION De-energizing 3D 4KV Bus places Unit 3 in a Technical Specification LCO action statement due to the associated Component Cooling Water and Intake Cooling Water Pumps being inoperable.
1.
ENSURE the following:
3A 4KV Bus is ENERGIZED.
30 COMPONENT COOLING WATER PUMP is stopped.
30 INTAKE COOLING WATER PUMP is stopped.
12
cIe U)
Ui E
L..0 U
U) 0 4-C.)
I..0 4-U)
L.
0.0 x
C ci a.
0 230 (U
U) 0>
(0 U) 0 CU CU CU CU ci) tY)
(U 0>
U)
U ocD WQ U) 23 U
cy)
CL
- 3 C.)
CD ci)
H 0
0 0)
C 0
=
11 ci)
D 4-0 ci) 0
()
I (1) c 0-I)
(U C C
t
,,U)a)
Cl) 4-0 (N
t (oI 0
r ci)
0)
CU 11
-F--ca (9
-o E N-(1)
(Y) 0c a)
a) a)
LU 9-5 (Ua)t 0 0
(/)D C) 0--
-0<0 U) o cii CU U))
o Ea)
Cl)
-0
> CL÷
(_) or (N
0E L
oD Xo
.200 (N
0Z*
ut9 a)
- 4
_a)o_
I-;-
C_go 0-CUZ o
w.EO CD C)
)
COD o
c D
C)
C)
D CT)
(I)
CO D
D r
0 t
0 o
0 o
WH H
U-0::
o:
-J uj UJ
-J CL o
O Q
j uj 1
j w
D CO LL
)
(0 0
C) 0 CD 0<
<C
)
C)
C)
C)
Z Z
U)
U)
Ui Ui 00 Q_
Q_
_J
__J 00 C)
C.)
L cii)
CU0.
cii)
U)
-c 4-.
a)
-Q U)0.
0 U)0 2
- 3 0t (N<
i-U) 04-i 4.-
COc U) ci)
(i-a (I)
-U)
(I)
-ICo 0
(U
-c U) 0 U)C0 4-.0
<C U) 4-s C
(U0 CL CL
<C a
Da 00 0
C) 4-.C ci)>
LU 0
0 a) a)00 CL C
U)
-c 4-,
a)0 (U
2 U)
C0 4-,
(UC 2
a) 4-.
a)0 (I)
H C
a)
-C LiH0z a::
Liiz LU c
0 U)
U) 0a-a) 2 H
H 3
CD Cl)
Cl)
Cl)
Cl)
Cl) 93 XI U) 0 0
0 0
0
0 w
5 0
0 Q
Q Q
- 5 0
-D D
-U
-o 0
CD CD CD CD CD U)
U, (A)
CD C) 0 a-CD
- 5 (I)
U)
-o C:
3
-o U)
- 5a 30
- 5 0
Cl)
-I U)
C:
-p
-U 3
-o 0) 00 U)
CD CD U)
- 5-CD Er 0
- 5 CD
-o C)
U) 0*
U)
C) 0
- 3 Ci) 0 CD CD
- 3-U) 0 z
0 3
DC 0
0 CD DC D
(0 3
CCC F)
CD F)
CD CD 0
F)
CD CD (I-)
CCC CD C.)
F-.)
CD C,)
G)
CD CD Cl)
U):30 I 0
Cl)
CI)
U)
-o U)
-h
-0 3
(A)>
0 (A) 03 0
0 0
CD
- 3 Ci)
U)
CD 13 C:3
-o C:
U)
- 5 CD (iL)z0 73 0
(A) 0 0
- 50 CD U)
U)
CD CI)
U)
CD CDC (Dril 8
CD
- 3 CD 3D)
(fl CD (C) 00
- 3-CD 0
-9H CD U) rtz p
N)0 (I)0 N)
Cl)
C)
CD
- 3 U) 0z p
(A) m CD
- 3 zp
-U U)
Ca CD 0-h I) 0)
CD 0
CD cT8 U)
CD 0
ci C 0 0 CD 0
D)C
)
(
C jF I
-oC
-o (I)H>
HmC 0
0 0.
CD (11 DC CD 3
-o C.)>
C) 0D0.
CD D
-o 30 C.)
)IC 0
0 D0 CDD (ft DC CD 3
-o C.)
C-)
G)UC CD
(_.) - -
QJ CDCD C))ci G)mm 0)>>
mm 0
JU 0
0) 0)
Urr rnrn mm 0
11I0 C)
(DC, 0
5:3 C)
D 0
CD ci CD CD 00 0
0_
C))
DC))
3 c
-03 CD CD CD0 N
CD
- 3
- 3-0
- 30 3
CD 0
0 C))
- 3 (cC U)
C))
0
-A C
C.
0
- 3 DC C)0 C.
CD
- 3 CO C))
CD 3
V CD 00
- 3
- 3 CD C-C) 1 0
C
-u C
0 JT
.j C)
CD CD CD 0
3 0)
CD CD C
o C)
CD C.)
0 CC(
C)
)
CJ C)
F.)
0 CD CD 0)
CD CD C
x XI CD
.Ct C
0 CD
-I U) 0
-I C,
0 (ft
-I 0
-I 3
m Cl) 1
- 3-CD
- 3 0
2:3 0:3 mc Ci)-
HO mU)
I
)
o CD I
)<
0-o CD0 CD Z
C-0 (C)
D CO CD
- 3 (0
C))
00:3 CD D
CC)
DC CD C
3
>93 C:
CD Ci)
- ø
-A U)
- 3
- 5 CD CD C) uo CD D
a 0
00 U)
-A U)
- 3-U)
U)0 4-CD CD U)
AZ 5-
- 5 C) C!)
G)
I-CD CD Ci,
H 3
CD Cl)
(I)
(0 Cl)
Cl)
CO
-a j
a a
Co W
0 0
0 0
0 0
0-U>
I
-l o
o C)
C)
C)
-o
-o
-a ci C) 0 0
-I.
CD
()
0 C-)
0
- 30 CD
- 3 C)0 CD
-U C
3
-p m
zm z0 Hm G)C)
-F CD(D0 a.
<3 0 -c CD 0
OC)
-U
-lCD I
OCD
- 3 C,0
- 3
- 3 C
CD
- 3-m CD
- 3 01 C)
I0
- 3-CD 0
CD Co (0
D Cl)
CD0 C)0
- 30 CD:3 Co Cl)
CD 0
3
-p o
e 0
Cl)
-Um cm C)
- 3 H
CD Cl)
0
3 Cl) sg 2.
O Cl)
- 3
+/-
(0 0
30-.
0
.5
()
Gm (1)
CD Cl) 3 (0
CD
- 3 CD Cl) 0
.5 CD0
-o 30 (J)
C) 0
- 3 0
CD (I)
(I, C
.5 CD C)
(0 CD Cl)
CD
.5
- 3-0
- 3 00 C)0
- 3 Cl)
>a 0
- 3 C))
01 CD
- 3-Cl) 0
-5 Cl, C
Cl)
-I 0
CD o
z 3
p C))>
M
0 o
C))
O C0 M
0 CD
- 3 (0
Cl) 0 C)
CD CD Cl)
C 30 t3 Z
c P
0c) zCm 0
- 3
-I
)
z 0
- 30.
CD
- 5 (I) a CD
)
(0 C/)
CD CD (3
(I) 0.0 0
-4, e4, CD Cl)
CDn0 0.
D0.
-I 0.
0 0.
0 CD C)
C 0.
CD Co CD CD 3
V (I)
CI)
. :3-CD(DC o
3:3(0 0.
C71 0
CD 0 C,)
CD0.
0 Qo
-0 Cl) 0)
91 (D-0 13(1) c o33 Z
)V Jo m
0 I) 919.
(Do CD (1)
(1)1(1 3
G)
-9 (I)
CD CD C) 0 Cl)m
- 5-CD 0
(I)0:3-Co (0
CD CD Z3 Cl)
CD CD 00 CD
- 3 CD0
- 3 (1)
CD0 0
- 3 I)
C/)
CD
-o PS CD
- 3a CD-a C
-I CDa.
0
-O CD 0
0
-I C) 0
- 3 C)
-n 0
-I3 m
Cl)
P 2
0
- 3
?5C)
-C)
I CD corn Cl)rn 0.
30 zJ c
(0_Il CD CD
- 3 0..
Z3 0)
CD Cl) 0
-U
- 5 C3 CD CI)
-.4 C
CD C) 0 1:
- 3 (1)
-0
-.5 CD C
C 4
CD (0
-o CD C
Cl) 3
-0 CD CD CD
- 3
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.:
5 Page 1
of 2 Event
Description:
3A SIG Bypass Feed Valve Controller drifts causing the valve to open.
After noticing the SIG level change, the BOP establishes 3A SIG control band with the S/G Bypass Feed Valve per 3-GOP-301.
Time Position Applicants Actions or Behavior EXAMINER NOTE: This disruption is to cause a rise in 3A SIG Level while in manual.
This is accomplished with causing an increase in valve leakage while in steady state conditions. Once the operator recognizes this adverse trend and closes the 3A SIG Bypass Feed Valve, then the initiating trigger will be deleted.
Direct Facility Operator to trigger lesson step, EVENT 5 - 3A SIG BYPASS FEED VALVE CONTROLLER DRIFT. Unsert TVFV479 0.500000 delav=0 ramp=60 on=0 off=0)
Observes the following:
SROIBOP 3A S/G Feedwater flow increasing A slow rise in 3A SIG Level SROIBOP Observes Annunciator C 6/1 SRO Directs response using the ARP CAUSES:
- 1. Steam Generator Level Control Malfunction C6
- 2. Instrument Failure SROIBOP SGA LEVEL DEVIATION PROMPT ACTIONS IF malfunctioning SG level controls, THEN:
SROIBOP TAKE manual control of level.
RETURN SG levels to normal.
ALARM CONFIRMATION SROIBOP CHECK Ll-3-476 or Ll-3-478, A STM GEN LEVEL Controlling channel vs. P1-3-446 or P 1-3-447, FIRST STAGE PRESSURE level control program on VPA.
OPERATOR ACTIONS SROIBOP IF alarm is due to instrument failure, THEN REFER TO 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.
BOP Adjusts the 3A SIG Bypass Valve to lower the 3A SIG Feed flow to maintain a band from 45 to 55%.
16
Appendix 0 Required Operator Actions Form ES-D-2 Time Position Applicants Actions or Behavior 3-GOP-301 4.41 The Shift Manager may designate operating bands as necessary based on current plant mode and equipment conditions as needed to allow the operating crew more flexibility.
This guidance on operating bands does not allow the violation of Tech Specs or allow the operation near automatic trip setpoints. One example is Sf0 levels while not in Mode 1 or in unit startup.
The program level is 50 percent, so the operating band is set at 45 to 55 percent.
This allows the deviation alarm to remain clear, yet still alert the operator when a 5 percent deviation from program occurs, which is the system design.
Op-Test No.: 2011-302 Scenario No.: 3 Upcoming Potential Additional Tech Spec Call POWER DISTRIBUTION LIMITS 314.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the following limits:
a.
5 581.2°F SRO b.
Pressurizer Pressure 2200 psig, and c.
Reactor Coolant System Flow 264000 gpm APPLICABILITY:
MODE 1.
ACTION:
With any of the above parameters exceeding its limIt, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less then 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Op-Test No.: 2011-302 Scenario No.: 3 Event No.:
5 Page 2 of 2 Event
Description:
3A S/G Bypass Feed Valve Controller drifts causing the valve to open.
After noticing the SIG level change, the BOP establishes 3A S/G control band with the SIG Bypass Feed Valve per 3-GOP-301.
EXAMINER NOTE: After the 3A SIG Bypass Valve Controller is lowered, and then the FACILTY OPERATOR ensures this malfunction clears.
EXAMINER NOTE: When conditions stabile after the 3A SIG Bypass Valve Controller is lowered, then continue with Event 6
- PCV - 455A Spray Valve Controller Failure.
17
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.:
6 Page 1 of 4 Event
Description:
PCV 455A Spray Valve Controller causes valve to fail partially open.
The ATC mitigates this event by manually operating the valve per ARP, 3-ONOP-041.5, or 0-ADM-211.
Time Position Applicants Actions or Behavior Direct Facility Operator to trigger lesson step, EVENT 6
- PCV
- 455A SPRAY VALVE CONTROLLER PARTIAL FAILURE. (insert 1AH244G 2.5 delay=O ramp12O on=O off=O)
Observes the following:
RCS Pressure slowly lowers SROIATC PCV-3-455A partially fails which causes the spray to open further in automatic. Manual operation is successful with reclosing the valve.
A 9/2 PZR Control Hi/Lo Press SRO/ATC RCS Pressure is noticed lowering along with PCV-3-455A going further open.
PCV-3-455A is taken to manual and closed in accordance with SROIATC 0-ADM-21 1.
EXAMINER NOTE: If prompt action is taken, there may not be an annunciator response. In the case where action is delayed, then initial actions will be taken in accordance with these ARPs prior to entering 3-ONOP-041.5, Pressurizer Pressure Control Malfunction.
SRO Directs response using 3-ONOP-041.5, Pressurizer Pressure Control Malfunction.k SROIATC Foldout page is required to be monitored throughout this procedure.
CAUTION The Master Controller should be operated carefully (Norma! controller output for 2235 psig is 42.5 percent demand; 92 percent demand will open PCV-3-455C).
If the following conditions are met, an excessive increase in controller output could cause Power Operated Relief Valve PCV-3-455C to open:
1.
PCV-3-455C hand switch in AUTO.
2.
Pressurizer pressure is greater than or equal to 2OO psig, or OMS switch in LO Press Ops.
18
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.:
6 Page 2 of 4 Event
Description:
PCV 455A Spray Valve Controller causes valve to fail partially open.
The ATC mitigates this event by manually operating the valve per ARP, 3-ONOP-041.5, or 0-ADM-211.
Time Position Applicants Actions or Behavior FOLDOUT FOR PROCEDURE 3-ONOP-041.5 1.
FAILED INSTRUMENT ISOLATiON a.
IF any Pressurzer Pressjre control Instrument Loop fafls. THEN place app cable control swi:ches to a pcstion that iso ates the faIed natrument 2.
3-EOP-E-O TRANS1flO Ii CRITERIA a.
PZR cressure cannot be jvantained treater than 20C0 osig, THEN erform the following:
1.
Ccr.nue efforts to restore PZR pressure and 2.
Tho the reactor and turbine and ;o to 3-ECP-E-O, REACTOR TRIP CR SAFETY INJECTION.
3.
PORV ISOLATIONILEAKING PORV IDENTIFICATION a.
IF aiw PORV is OPEN OR Leakinc AND ressure is less than 2235 pc, THEN CLOSE the app cable PDRV and/ar Slcck valve.
b.
The fo lowing are ndicatons of eakage from a PZR PCRY and should be used :c identity and isa ate a leaking PORV:
PZR reief line zemoeranire. Tl-3-463, INCREASING.
2.i PZR reief tank level. Ll-3-470, INCREASING.
3)
FRreieftanktentperature. Tl-3-471, INCREASING.
4i PZR re:ief tank pressure P1-3472. INCREASING.
5)
PZR FOR//SAFETY ACOUSTIC MONITOR. LEDs LIT.
OPENiLEAKING PZR SAFETY VALVE IDENTIFICATION a.
The fo lowing are indications that a PZR safety a open or leaking:
I)
PZR Safety line temperature, T1-3-465, INCREASING orat saturaionten,perature associated th the PZR relief tank pressure cer ATTACHMENT 2.
2)
PZR Safety line temperature, T[-3-467. INCREASING or at saturation temperature associated with the PER rel:ef tank pressure per ATTACHMENT 2.
3)
PER Safety line temperature, TI-3-469. INCREASING or at saturation temperature associated with the PER relief tank pressure per ATTACHMENT 2.
4)
PER relief tank level, Lt-3-470, INCREASING.
5)
PER re ief tank temperature, Tl-3-471, INCREASING.
6)
PER relief tank pressure, PI-3-72. INCREASING.
7)
PER POR//Safety Acousc Monitor, LEDs LIT.
E.
SPURIOUS ACTUATION OF CV-3-31 I AUXILIARY SPRAY VALVE due to re in Containment ar 35 4KV Switchgear Room a.
IF pressurizer pressure is decreasing and Auxiliary Spray Va!ve, CV-3-31 1, is suspect. THEN reduce charging to one charging pump on slow speed AND close charging to RCS Confrol Vave HCV-3-121.
19
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.:
6 Page 3 of 4 Event
Description:
PCV 455A Spray Valve Controller causes valve to fail partially open.
The ATC mitigates this event by manually operating the valve per ARP, 3-ONOP-041.5, or 0-ADM-211.
Time Position Applicants Actions or Behavior I
Check PZR Pressure Contro Instrument Loop Not Failed a
Check PT-3-.44
- NOT AILED cy comparison with adjacent pressure char nels and known pant parameters 2
Take manual control of PC3a4dJ, PZR °RESS CONTROL.
3i IF nisnus control of PC-3-4.4J is NOT effec: ye. THEN perform the foilowing:
Take manual control of PZR scray valves.
Take manual control of PZR heaters IF PZR pressure is less than
- 2335, THEN manually cose POVs, IF any PZR PORV can NOT be c osed, THEN manually close its block valve.
a Perform the following:
1 Verify PCV-3-455C MOV-3-53f CLOSED.
b.
Check PT-3a45
- NOT FAILED by comparison with adjacent pressure channels and known plant parameters b,
Perform the following:
Il Verify PCV-3-456 Qj MOV-3-535 CLOSED Check PORVs Closed Perform the following:
PCV-3-455C
- CLOSED PCV-3-456
- CLOSED CAUTION A fire in containment or the 3 4KV Switchgear Room may cause spurious actuation of and give false valve position indication for Auxiliary Spray Valve, CV-3-31 1.
20
Q Cl)w E
L.0 LL z
Ui I
Ca E
0C C
.0 0)
.0 N
0 i a 0co 0
0 0)
C
-g g
a) 0_j a,i.i C.)
0Cc)
.20 0) a)
.2 C)
Ca a,
0z 0z
.2 a
a)
-J<
Zia,.2 c
2:
(3 3
ca
.2 0-._
OaG) ca 0<
0 Cl)
.2 0
zo 0
X.EUJ, o
N-0 N
D o-LtJ D-W
<W !.--
0>0 0>0 0
.9cc ciujU-.
CL
.20_i CaQ_i Ca_i QCa CLCLQ D.C.)
>0 NI.2U) 33 Co 0-.
o>ct
=9
- Eo l-4-
o-z or 0
ci)
---D_
- 3) 0 ci CU 11 CU
>0 (0
Øcl) o o>
Z
-G)
-I-jC ci) 20)
C w
C:
ow Cv)--d CU>
o
>D C
C CU 0CU (1)2 o
(I)
L0-.Q (Y) >
Cl) 0 4-,
C.)
0 4-.
a)0.0 a)
L..
a) 0)
C C
-Ua)
o
.2 0) 0 (3
0) a, Ca
(*
L I-.
o a-i ID 0
E 0
1) di (1) a-R 1
ID z
CD CD 0
0 0
C:i*
0 o
a--i
E E
a a
-C 0)
Q 3-il 1
- _c=
S) er
- ?? o
r-_
CLI CLI CLI N
r-
,j
[1 o
CL CLJ CL ID a
F 4-,C a)>w
-C 4-a) a)
C.)0 0.
C a).t 4-.
ci)
.0 4-C)
-o0 C.)a)
C.)
Co 0.
U) a)
a)-.
<cv) w I0z 0I D
S a
0 C
a)0.
0.
Cl)
Cl)
CO w
0 0
0 Q
0 W
W 03 0
0 0
U
-o Ii o
-h (D
rr Pd CD CO.o
<0
.c, CD COCD o Z 0
3 CD I
C)0z
-I
-1 0z H
3 CD
-u 0
CO 0
- 3
-o C)
U)
- 3 U)
C) 0
- 3 Cl) 0 QJ CD
- 3-U) 0 p
ui>
- j pw
-1
- t 000 r mzu0
-1 1w
w 9) o 3
o
-oLD c
3 H-cLI C)
H D
CD OCD CD D)
LI)
D CD (0
0 CD:5 C)
- 5 C)
0)
D C
CD o
CD
- 5
)
(I)
CD m
m CD Z
-D m
2 1
- 5 0
- 5
- 5-CD 2
0
- 5 CD C/)
U)
CO c)
H
-U0
-a C
3
- 0 C
(I)
- 3 (0 :3-CD Ci))
0z0 C
C 03 0
C 0
H CD U) z p
rJ0 CI)
C)
CD U) 0z p
(I) m CD
- 3 z
p
-.--J
-a U)
(0 CD 0
C) ii C)
H Ti C-)
CD 0)
(0 CD U)
ICC CD CD
.0C cC) 0 0
CD (I)
U)
- 3-cC)
- 5 H
(C)
(/)
(I)
H
-I,
0) ci, 2.
H c D mm CD.
II cC 0
- 5 D CD CD 0-
- 5 II CD CCCfl 00)
U)
CD m<mz
-I 1
-I
-U C-)
-U Cl) 1
-f 1
I cj)
C-)
C (I) 0)
U)
- 4. ) [3
E oC a a aC)
(0 ID ID ton 35 a C
=
OlD (0
C)
DC C-<
ID C
(0 In C
DC.
S C-)
- 1:
ICn L
cm CD CD(D D
U) C) 0.
0*
- 3-
-a 0
H 00
-0 I) U)
- U)
H 0
t3 CDU)
-0 U) a
- 3
(5)
-1
-a0 0C 3
N)
-0 n
0) cTDI w
0.
(DC
CD 0
a-CD 9
- -o 0
H CD 0
-o-o QID 3
Cl C
CD
-MCD 3
0)2
-p 8
CD
-fl
>c i
CC) tm CD
-Um ci
-Ti w
0
- 5 2.
CD CD 2
=
C) o CD (5a CD W
0 Lu w
- 5 C).nxm0 CD a.
x CD a.
0 CD 0) 0-C, 0
0) 1 0
m Cl)a I
-U--I-U m
COa CO.
(I)tJ2w0-C);0
.w0
-U
-H CD Cl):o0;
-I C-)
C) m F%)
0 0
CD x
0 (0
0
- 3 0
-U CD (I-)
z p
0 (AZ0
-3 3
CA) p
- 5-CD C,
CD 03)
0 G)
CD()
35W 4,
0
-omz CT,
-4
- 5 CD I
.3; (I) u TJ C
CD CD C))
CD CD3 CD CD (4
Di CD
- 5-CD CD CD H
3
- 5 C0 CD CD(1 F
p5 5D.
(DC 3<.
- 5 332 OCD
-4, CDC 0
ø CutS IC),
fflo OCD tD 1t3 CD 0
oflCD 0
12.
0-CD Di CD CD C)
CD 0
CD 4,
CI)
CD (I)
CD CD 3
C),
C
- 0 (C,
0
.3; 0
0 CD xi CD CD C,
0 H
.3; z
CD C
0 D
sth C
5<
cim0 0m>
(I)z0 13 00.
00.0 CO 0
0Z 00 0
CD 0
D 0
0 CD 0
£0 H
Nm 0
OW tJCD rn Z
CD
- 50.
3-3)0 (0
0 CD CD CD (0
U)
- 3C U)
CT:
C-)
0 Cl)
CD (0
C,)
C,, CD 0) 0
-D 0
0)
I U)
>a 0
- 3 Cl) 0
-S CD
- 3-0) 0
-S a) 0 CD
- 3 U)
-S 0z p
C,)
o o.
i2.
02.
<0 I
II IICo CI C0 m
oz oo 3)
I z
CD
- 1.
Cl)
-c--I 0) 2r CDZ 0
CD II C
-S CD0 Cr)
-S CD Cl)
-D0
- 3 U)
CD C
U)
- 3 CD CA) m0
-u m
cb U)
U)
- 3 CD 0) a)
CD o
U)
CD IU)00:3 I
C 0 ;:D
- 0<
CD I
r-(1) H, c a)
CA)
T jCD CD 000 a-U D
U)
U)
- 3 U)
(A) c Ci)
CD 0
- 3 j; 0
U)
() c 2m U) 0 d-ri i
0
-.-CD
..:3 CDHD Cl) 0 CD u
U)
U)
U-1 0
- 3 4,
CD 0
T 0
Cl)
°CC
- 3
-5 1
1
!CD <
o C,) £ CD I
i U)-CD C)
U) c -D 0 DU)0:3 Q
CD D
U)
CD CD
- 3:3 D 0 (0 I
Ci)
(4
-O (4
C 0:5-CD C) 0 As CD
-Q p5 1
Zi 0-i m
CD.
C 0.
0 CD I-..
0
-I C,
0z CO p
CD m03) 0.g s-Di.
0 9g CD (0
Di CD CD CD C 00.
0.
p.
.z5 CDOCD 9as CD
- s CD 3
C c5-ZC 0.
CD OCDCD
- 5CD=
CD O<
A) o0.
- 53:5.
g CD0_CD CDmCD (012.3)
.Z(J) crQ.
CDI1
<ohi CD3C 5.CD CD PS
- 5 CD_
m CD
- 3 4-z p
D
>ZG)
Hco C),m O)>
DJ 0
1J12 0_1 u
0-roW zm mC 130
>0 HZ 0
PS OmO 0 D.
Ei C)) 0 5-)
1W 11 CC)
(fl>
T (C,[1l.
HO P
C0
- 3 (0
CD 5-3 z
CD CD
- 5
- 5. D O
CD CD 0_C) m.30 CD CD O
(I)
-0 CD U)
CD CD 0
-4
-3 a) 0 m
C;)
ci
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 2 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Applicants Actions or Behavior Time Position Applicants Actions or Behavior 3
Verify Power To Emergency 4 KV auses a
Check the 3A and 384 KV buses a
Perform the following:
MAINTAIN AT LEAST ONE ENERGIZED 1)
Attempt to emergency start any Unit 3 available diesel generator.
2)
IF neither 3A nor 3B 4 KV bus is energized, Ij) go to 3-EOP-ECA-OO, LOSS ALL AC POWER Step I b
Check the 3A and 3B 4 KV buses b
Attempt to emergency start the MAINTAIN BOTH ENERGIZED de-energized Unit 3 bus diesel generator c
Maintain the 3D 4 KV bus energized c
Perform the following:
ALIGNED TO AN ENERGIZED 4 Ky BUS 1)
IFlockoutof3D4 KVhus NOT present, THEN perform the following:
a)
Verify 3C CCW pump BREAKER OPEN b)
Verify 3C ICW pump
BREAKER OPEN SROIBOP c)
Operate bus supply breakers to restore power 24
rAppendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 3 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior 4
Check If SI Is AcLuated Perfom the followin9:
- ANY ON a.
Check if SI to required:
OR Low pressurizer pressure 1730 psig Safeguards equipment AUTO STARTED High containment pressure 4 psig OR High steam line differential pressure 100 paid a
SROIATC Hiah steam flow with low SiG pressure - 14 psig OR low Tavg (543 F) ti.
jSI is required, LU.{ manually actuate SI and containment isolation phase A AND go to Step 5.
c.
SIisrequired, perform the following:
I)
Monitor Critical Safety Functions using 3-EOP-F-0, CRiTICAL SAFETY FUNCTION STATUS TREES.
2)
Go 1 3-EOP-ES-0.1 REACTOR TRIP RESPONSE, Step 1.
NOTh 1
CREW L -
FQLDOUTPago shall be monitored fortlie remathder of bus procedure. - -
RO Manually actuates Train B SI and Phase A depressing SI and Phase A pushbuttons.
5 Continue With Attachment 3 To Complete SROIBOP The Prompt Action Verifications While Performing This Procedure Examiner Note: 3-EOP-E-O, Attachment 3 commences at Page 21 of 26.
Examiner Note: The SRO and ATC will complete the remaining steps in 3-EOP-E-O, while the BOP performs 3-EOP-E-O Prompt Action Verifications using.
25
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 4 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior FOLDOUT FOR PROCEDURE E-0 1.
ADVERSE CONTAINMENT CONDITIONS IF either of the conditions listed below occur, THEN use adverse containment setpoints:
Containment atmosphere temperature 180° F OR Containment radiation levels 1.3x10 5 R/hr WHEN containment parameters drop below the above values, THEN normal setpoints can again be used IF the TSC determines that containment integrated dose rate has not exceeded 106 Rads.
2.
RCP TRIP CRITERIA a.
IF both conditions listed below occur, THEN trip all RCPs:
- 1) High-head SI pumps
- AT LEAST ONE RUNNING SI FLOWPATH VERIFIED.
- 2) RCS subcooling
- LESS THAN 25°F[65°F]
b.
IF phase B actuated, THEN trip all RCPs.
3.
FAULTED SIG ISOLATION CRITERIA IF any S/G pressure decreasing in an uncontrolled manner OR any S/G completely depressurized, THEN the following may be performed:
a.
Maintain total feedwater flow greater than 345 gpm until narrow range level in at least one S/G is greater than 6%[32%].
b.
Isolate AFW flow to faulted SIG(s).
c.
Stabilize RCS hot leg temperature using steam dumps when faulted S/G has blown down to less than 10% wide range.
4.
RUPTURED SIG ISOLATION CRITERIA IF any S/G level increases in an uncontrolled manner fi any S/G has abnormal radiation, AND narrow range level in affected S/G(s) is greater than 6%[32%], THEN feed flow may be stopped to affected SIG(s).
5.
AFW SYSTEM OPERATION CRITERIA a.
E two AFW pumps are operating on a single train, THEN one of the pumps shall be shut down within one hour of the initial start signal b.
IF two AFW trains are operating and one of the AFW pumps has been operating at low flow of 60 gprn or less for one hour, THEN that AFW pump shall be shut down 6.
CST MAKEUP WATER CRITERIA j CST level decreases to less than 10%,
THEN add makeup to CST using 3-NOP-018.01, CONDENSATE STORAGE TANK (CST).
7.
RHR SYSTEM OPERATION CRITERIA IF RHR flow is less than 1000 gpm, THEN the RHR pumps shall be shut down within 44 minutes of the initial start signal.
26
ci) 0
-I C,
H 3
CD ci) 0
-I C)
CD a
-i:i 0
Cl) 0D 0
-D H
CDci,Iz 0
N)
D
-k N) m 0>
rn-n r
0>
rnz 0
-U rn
- 33
- 33c) z.
01
-D C,0 4*
Cl)
C,I 0
C,)
0 CD
- 3-0 0
-I Cl)
C, CD
- 30 0z p
()
Cl, 0
5;;
C)
OH
-I, -
0(l)
°CD CD C,.)
- 3 3
DCD CD
-I, Ci) 00C 0-0
.:3 0
00 w
Cl)0 0
0
- 3 j.
C) o CDO 2.
CD C3 OCn C)
-Ut In 0
a 0
Cl)
CD w
C,)0 0
0 m
Q_00 9o C
oE ç T1 u-.- 0<
CD I
D*
cj mCD HCD C,
CD
- 3.
WCD CD kSg g 3
3.
T 0
3
,-.-:3 C,)
C CD
$W:3 $-
C) c 003 CD
? m 0
CDH o
- 3-C,
-i CD CD 0 CD0 03 0
- 3
-4, Cl)
CD C, :
OCD
- 3 C_I)
(flCD wWCI)
J7CD m_.
0 I
Ci)-CD CD c2co C) 0 0 D 0 CflO:3 O
CD
- 3
O-0-.
C,).
(0:3 Cl)
D.
CD CD
- 3:3 CD CD C
-I CDa.
0 CD I-,0
-I C,
0 U) m CD
- 3 z
p CD =
CD (CD CD CD
-C CD VI CD 113 CD CD C.
CD d
-U CD
-1, L)
)
3 Et C CD CD (51 CD CD 3 1(13 CM >
0 U
flQ 2
CD.
CD CD CD CDI (CD I
CD CD C-.)
-U CD H
rT,C 1-..)
CDVI 13)
(VC.
13.)
(CD CD
-I, CD C
CD 13)n (C
C.
CD
-o CD
>I >I 113 m
flCD 11 CD CD
- 2 CC.
2C1>
C CDD CD
.)C
=
CC_CM CD CDt)
C CC)
O-CC
CCC EU 2CD
(
3U CM 13 D
E.
s
CCD CD t>
s_p-H I t 0
CD CD 0
-h N) 0)
-n 0
3 m
Cl)a
H 3
CD Ci) 0 Cl) 0 U
U) 0 0
0 5
(
I I
- 3 C)
C)
C) r%)
03 DO 0
0(
D I0.9 C!)
CD.
-I, Cj) 5 CD U)
-h 00
-q.
0 Cn U)
--0 CDQ 0
CDCD
-U)
U) 0..
CDCDj
.C0 00
.3 0a U)
U) g
-D 0
U) a-U)
C) 0D U) 0 CD
- 3-U) 0 0
II CD U)az p
0 C) 0 CD
- 3 U) 1 0z 0
m CD
- 3 zp 03
-:i U)
(0 CD 0) 0
-h 0) mm 0(i)
()20U)
CD I
C
0 tJ 0<
Cl)
I
- 3.
U) mCD H 0
C/)
- s
_.WCD CD,-
000 B.U)U)
- 3
- .
- 3 5* C C)
CD:3
(/)C/)U) 0 U)
B 2m
.0B 0
CD
? m 5 JC CD 0
J 0 a- -
CD OCD w-U) 3 U)
- 3
-4, CD 0 D 0
CD CC
- 3 C.)
U)
CD jj ri <
0.
._, v) 91
- 3 tJ7CD r!ri_* 5..
(1)-CD CD a_U)
C)
U) 0 -0 0
- 3U)Q:3 QCl)
HC 3 U)
CD CD
- 3:3 (0
0 0
G) 0 0
>0 20D ho
0 0) 0 CD 0
CD CD 0
I CD CD
-I CDa-0 CD I
0
-S C,
-4.
0 Cn
-I 0
-S 3
m06 (I) (!) 2 0 rnn1o 20Y 0
i02 H U).
U) U) 20 51 CI H
U) C 2 > l. 0 rn ru U) H r11c)
T1Q c-U I ID C.!)
o2 cr (I) 1.3
-g U)fl,):a ID
.,CD In 00>
0 ID 0
Ca)
CD Ca>
j Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 7 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIC. After 3B SIC isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SL Time Position
]
Applicants Actions or Behavior 9
Check RCP Seal Cooling Check all RCP thernial barrier alarms
a.
IE CCW to an RCP thermal barrier is losi, OFF A 111, RCP THERMAL BARR 1)
Trip the affected RCP(s)
COOLING WATER HI FLOW 2)
Go to Step 9c.
A 112, RCP THERMAL BARR COOLING WATER Hi TEMP A 1)3, RCP THERMAL BARR COOLING WATER LO FLOW b
GotoSteplO c.
Check all RCP seat return temperatures c.
Go to Step Ia.
are less than 235 F d
Verify SI
- RESET d.
Reset SI.
e IF ctfsite power is NOT available, THEN check diesel capacity adequate to run one charging purnp adequate diesel capacity is NOT available, THEN shed nonessential loads.
SROIATC Refer to ATTACHMENT 2 for component KW load rating f
Start one charging pump at minimum f.
Go to Step 10.
speed for seal injectton g
Adjust Charging Flow To Regen Heat Exchanger, HCV 121, to maintain proper seal injection flow 29
Cl)u0 5;
-I C*)
-:i 0
CO 0:3 Cl);v0 5;
C)
H 3
CD CD C/)
00 5;-I C) 0 H
CD CO z 0
0 C?)
C I
m zm z0-lm
-I CD C,
.1 CO C,
t-,.
0 V
CD 0
0 CD Cl, 1
CD-
-.4 I1 C/)
C)
CD Cl) mIm 1mp m
zm z0-Im mc ow
.P Cl)
-I.
CD CO 3
C,,
0 CO 4-4.
0 C,)
CD 3
C,)
CD C)I0 Ci)m C,)
C, 3
CDz1 C) 0-,
C)
-U CO C,
CD Cl)
C?)
CO
- 5
- 0) CD B
00
- 0) 0
- 3 CO CD 0 C)I0 C) 0
-a C,
CO
- 3 CO C,
4-0
- 3 CO 0
CD
- 3-CO 0
C)
C, CD
- 3 CO
-3 0z C?)
CD0 C,
CD Cl) 0 CO
-n C)
CM C)
C Cb CT LJ U,
I 0
Orn 1>
G)ni E3 0
-10 UT 4,.
C
-n
-n
- s m m 00 CO rn-C -
o
.- 0<
CD I
D.
CO mCD HCD C/) C?)
CD CD 3
- 3 CO 1
COCO
- 5 CO C?)
C (I)
CD0 CO G)0 B
CO 03 CD r1 CT 0
CD
? m CO CDH C,
CD J-3 CO CO
- 5
-h Cl)
CD 0 C,
z!-. 0 C,
CD
- 5 -
C?)
C CD 4CD <
C,_.
L/ V)
- 3 DCD CO r!n_. E CD S1CO C)
CO 0 -D 0 Q
CD CO CO:3 Hc 3 Cl)
?.
CD CD
- 3:3 C, Q CD C
0 V
CD 0
C,
-I.
0 U) m CD
- 3 z 0
03 C
tC CT 0
cu z:,a k) c.
5;-cC 2,CT CTE I
9 Ic,
-1 5
29 iIft :iiHhi1 0
D(T 5,
T U,
0 a,
-C
-_-aI CC T
9 C
E.
0
=
-o CO Co CD 03 0
-h M
0) 1 0-3 m
Cl) 6 3
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 9 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to3-EOP-ES 1.1 to terminate SI.
Time Position
[
Applicants Actions or Behavior 11 Check PRZ PORVs, Spray Valves And Excess Letdown Isolated a.
PORVs CLOSED a.
IF PRZ pressure less than 2335 psig, THEN manually close PORVs. IF any PRZ PORV can NOT be closed THEN manLially close its block valve. IF block valve can NOT be closed, THEN perform the following:
1)
Monitor Critical Safety Functions using 3-EOP-F-0, CRITICAL SAFETY FUNCTION STATUS TREES.
2)
Go to 3-FORE-I LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
b.
Normal PRZ spray valves CLOSED
- b. j PRZ pressure less than 22130 psig, THEN manually close valves. Evolve(s) can2I be closed, stop RCP(s)
SROIATC as necessary to stop spray flow c.
Auxiliary Spray Valve, CV-3-31 1
c.
Manually close auxiliary spray valve.
CLOSED auxiliary spray valve can NOT be closed, THEN close Charging Flow to Regen Heat Exchanger, HCV-3-121 d
Excess letdown isolation valves
d.
Manually close valve(s).
CLOSED CV-3-387, Excess Letdown Isolation Valve From Cold Leg To Excess Letdown Heat Exchanger HCV-3-l 37, Excess Letdown Flow Controller 31
I Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 10 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
r Time Position Applicants Actions or Behavior 1 2 Check If RCPs Should Be Stopped a
Check RCPs
- ANY RUNNING a
Go to Step 13 b.
Check RCS subcooling LESS THAN b
Go to Step 13.
25F[65fl c
High-Head St Pump AT LEAST ONE c
Go to Step 13.
RUNNING AND FLOWPATH VERIFIED d.
Stop all RCPs SROIATC SROIATC Stops RCPs if subcooling is less than 25°F (65°F) with HHSI flowpath verified with HHSI pumps running.
EXAMINER NOTE: RCPs will be tripped if not previously tripped on 3-EOP-E-O Foldout Page.
CREW CRITICAL TASK : Ensures RCPs are tripped due to a loss of subcooling during a LOCA prior to completing Step I of 3-EOP-E-2.
32
H 3
CD m
zm z0
-Im in0 m
C, 0
C CD 0
CDx CD CD Ci)
Cl)
Cl)
Ci)
Cl)
Cl) 0 i
u U) 0 0
0 0
0 0
E 0
5>
5
-I
-f
-1
-I C)
C)
C)
C)
C)
C)
-I
-5 U)
D U) 0 D
Cl) 0 C?)
m0
-pm r3 C?)
H
-I U)
D U) 0
- 3 Cl) 0 m0-p 0
(V O
C,)
0 0
(V
-30 0
CD U)
CD 0
- 3-U)
-t U)0 N
U) 0
- 3 C/)
6)
U)
Cl)C D
0)
I-0
-o
-o C-)
U)
- 3 U) 0 I-0
- 3 U) 0
-5 Ix CD
- 3-U) 0
-S
-.o-C/,
o U)
00 U)
N 0
CD cn
-4,0 0C/)
C
CD
-o U)
-sO)
CD E.
CD C1)
CD U)
CD3 CD U)
- 3
(03 CD 0
00 I -
CDCD CD U) p i y
>rn onlo 0
zO (J)C)
- j
(:)
0 CD H1 rl1 CC-)-.
1Dm U)3J IC rTl
-m rn>
-U)
(V 0
<C)
CDO
-4, -
0:3 U)C CD 0
- 3 CD 0
-53 U)
- 30 CD 0
-4, m0-a
[in D
I-U)0
- 3-3 CD
- 3
-t C?)
-a
-50 3
-D
-t 0
0
- 3 0
U)
-s(0 CD:3 C)
- 3CD CO U)
---t
- 3 Zr U)CD CCj)
- 306) 0
-SC 0 z
CD CDQ-D 3U)
U)CI)
CD
- 3CD0
-:3 Ix C/)
6)
CD CD U)
- 3
-a
-5 CD (I)
U)
C 0
0 CD (is z
p 0-Cl) 0 CD U)
-S 0zp C?)
m CD
- 3 z
0 OD
-a U)
(0 CD 0
-4, N) 0)
m m 00
?U) -aQ-:3 rn C
- - O<
CD D*
QU)
CD H Cl) C?)
-WCD CDT-,
000
-.c-D 0 P n
B 3.
,Ci)U):3
- 35c CD
-CD C/)o U) 6)0; 3 U) 03 CD F-0
-tCD m
E;rJ;oC CD 0
Zr 0
-S
_4-
-5 CD OCD w-3 U)
U)
U-5o
- 3
-4..
CD 00 0
0CD
°CC
- 3 C?)
0CD(aj C?)aJ:3-0 C/) £ CL) r!T,_.
CD Qcn C)
U) 0 -D 0 00:3 Q
CD D
OC1.
0:3 C HC 3 U)
CD CD
- 3:3 0 0 (0 tO CV Z)
I Z
(V U)
H I (V
U) rii C) mcI 1Dm mn 5V5 0
cC 0
U)
CV0
- D CD x
CD
.0 C
-I CD0.
0 CD
-I U) 0
- 1 C,
-I.
0 Cl)
-1, 0
m Cl)
Q Cl)w 0
U-U) 0 C) 0 4)0.0 ci)I ci)
C ci) 0 o
- Cb oc 0
C-)c L
C)
£ o
c I.
D C
o E
C C
0 CD Co o
C) 4-d
-I- ) C) 0 CC 1)
.U U) ci)
C (Q
C (N
Cu)
0 C0U)C o 0 0 (N
ci)
ci)-cj I
ci)0) 5-
>LJ co C)-C o
Z COC:tf 9-C C
0.9-Ow ci)OQ)ci)
-I--
L Ci C
c,)
Cl)0 (D
ci)
C)
Dçjj o
z oC CU0 ci)
E0O_
c CD ci)
C C t (U
C C E
- 4) 9-1 o
<U)
C)
<-4-a 9
I CO o
00 (N
0Z U)
- C ci) >C) ci)
4
-.LU F-C-
04) o WoLJJ.2 I
U I
C III I
I I I
I I
C I
C.
CC I
D C t UI I H I
I I U I
I I
H C>
C>
C U)0 C
C C
w zo C0,,,
i2Ø a) 0 CD U
I(a U
C C.
4)>.
2 C)
C)
-U C 0)0i UiC HLL zo C o*
DH b
0 2
D<DL)
C)CLLJ
= 00oZ WJJUJ C
uJ
-J U) 2:
0<
a)
U)
LI_
U)=
0 C,
cj)
C
=
00 o
C c1
-oa)
C)0 0
0 Cci CU
.4-,0C 4-0 0
0 It)0 Co 0
Cl)
U)
U)0 C.)
Cci C
(U Ui 0
LiT 0)
C 0
I L
ID0 L
Ca, 0)
C Cl) a)
U)C00 U)
U) 4-,ci ci)
I 0
C)
C 0.
U)
C CC C
C LO 2
U)
C uJH UJO 0:1 -
1 UJ 01
>-Q zw
<ID CC CCC U)
C C
0 CJLLJ I-ti-I cr:-
1 D0 ujZ U)
CC C)
C C
C 0
CC II)
C 0
U)
C C
L1
-0 C-)
a) c)
(U ci)
I.0 U)C0 4-,
C.)
U)
C (ci0 0.0 C0 Cl)00 ci)N I
U)
U) 0 ci)
O>
I:)
4-,a)0 E0 C) 0 ci) cr U)
U)
I ci)>
C, ci)
E F-C.)
()()
C)
C.)
00 F-F-I I
w w
Cl)
U)
Ck Q
0 0
0 C.)
Cl) 0 C1)
U)
U)
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 13 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B S/G. After 3B S/G isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time rPosition J Applicants Actions or Behavior CREW 4
Isolate Faulted SIG(s) a Isolate main feedline a.
Manually isolate main feedline.
Close feedwater isolation valve Close feeclwater bypass valve b
Isolate ARJ flow b.
Manually isolate.
c.
Verify SI-RESET d.
Verify steam supply aligned to both trains of d.
Reposition AFW steam supply cross AEW pumps from intact SJGS) connect valves to provide steam from intact S/G(s) to all AEW PUmPS.
Maintain steam flow to AFW pumps while repositioning cross-connect valves.
AFSS-3-006 CREW AFSS-3-007 e.
Dispatch operator to perform the following 1)
Open ARV pump steam supply MOV breaker on faulted S/G(s) 2)
Close AFW pump steam supply MOV on faulted SIG(S) 1.
Place steam dump to atmosphere controller in MANUAL AND close the f.
Verify Sb dump to atmosphere valve steam dump to atmosphere valve. IF CLOSED steam dump to atmosphere canQI be
- closed, locally isolate steam dump to atmosphere valve.
g Verify 510 blowdown isolafion valves CLOSED h.
Venfy S/C3 sample lines
- ISOLATED Isolates AFW to the 3B SIG. Maintains greater than 345 gpm total AFW BOP flow to the 3A and 3C SIGs until greater than 6% NR level [32%] in one SIG is attained. (May have already been completed in 3-EOP-E-0)
CREW Directs SNPO/TO/FS to de-energize by opening breaker 30833 &
closing 3B SG AFW steam supply isolation MOV-3-1 404.
35
C)
C)
C) m m
m 0
m zm z0
-1m In0 In C,
0
-I.
C CD 0
CD C
Co C
CD c) 0)
0, H
Co D
Cl) 0:3 Cl) 0 m0
-Pm H
3 CD 0
CO 0
0 0
CoD (I) 0 0
Co 0
CD
- 5-Co 0
U)G) mo 00 0*
>mn 30
-<-P on 0.-
0*
-IC,)
C)-l0 xl 0
xl I
1 p
z-0 ZU)
D D
D C)
QC))
0:
2 H
D-ID
]:
z z m
cj m
D-p-
i i
-2 z
u
=.
CJ Li
i)
(j ZZ O
0
<0
.c r
(fl(V c
- r
-j mzm 0
JD 0
-S3H CD Ci) zp N)0 i
C/)
0 CD
- 3 Co 1
0zp c) m CD
- 3 zp 0,
-U Co (0
CD 0
-4, N) 0)
w0
-D Co C
Co 0
0 Cl)
CD (I)
()
-o N) 0)0 0-I w
C/)
0 (I) 4,
=50 Co Co0.
C) 0 (0
CDa m(D m 0
o Q3 1Co00.:3 rn Q<
CD I
- 3-a-U) mCD HCD £ Cl)
- 3- <
CD (Dr-,
- Q-3
- pCO>
3 ):5 3
- U)
Co
- 3 D
Co ()
- C C/)
CD 0
z Co-Cl)o Co G)o 3
CiA)
Co Q3 CD-0 CD
? m
- Co CD 0
CD0CD W
Co
-0I3 Co
- 3
-4, CD
°CC
- 3
(.4)
CoCDW
°WH
()W-C/)
4CD <
0 cr. c
- CD U) rr1_.
CCD C)
Co 0 D 0 CflO:3 a-CD
- 3
Q-Q-.
co Ci)
C H U)
- 3- !.
CD CD
- 3:3 D
C) CO
V V
CD C
- tj CD C
CDa.
0 V
CD r+
0
- 1 C,
rq 0z Ci)
-n 0
-43 m
Cl)
Ui C) 3.
p C)
C)
(I)
-1I ID p
0 xl m
-I ni 3:
z 0>
Do
>Cb 1
CJ)° O
ci-)
m 0
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 15 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The, crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior SRO Directs response using 3-EOP-E-1.
SRO Conducts crew brief for using 3-EOP-E-1.
= a
=
=
=
=!iJb
=
CREW Foldout page is requireci to be monitored throughout this procedure CREW Monitors 3-EOP-E-1 Foldout page (see next page) j Monitor Conditions To Determine If RCPS ShouLd Be Stopped a
- ANY RUNNING a
Go to Step 2.
b.
High-head SI pumps
- AT LEAST ONE b.
Go to Step 2.
SROIATC RUNNING c.
RCS Subcooling
- LESS THAN 25P[65F]
c.
Go to Step 2.
H.
Controlled plant cooldown NOT IN d.
Go to Step 2.
PROGRESS a.
Stop all RCPs 2
Check If SIGs Are NOT Faulted a
Check pressures in all S/Os
a IF any S/G is faulted AND that S/G has NOT previously been isolated, THEN go SROIBOP NO S!G PRESSIJRE DECREASING iN to 3-EOP-E-2, FAULTED STEAM AN UNCONTROLLED MANNER GENERATOR ISOLATION, Step I a
NO S!G COMPLETELY DEPRESSURIZED 3
Maintain Intact S!G Levels a
Narrow range level
- GREATER THAN a.
Maintain total feed flow greeter than 6%[32%]
345 gprn until narrow range level greater than 6%[32%J in at least one 5/G.
b Control feed flow to maintain narrow range SROIBOP level between 15%[32%] and 50%
c.
Narrow range level
- LESS THAN 50%
c.
Stop feed flow to any S/G with narrow range level greater than 50% j narrow range level in any S!G continues to increase in an uncontrolled manner, go to 3-EOP-E-3, STEAM GENERATOR TUDE RUPTURE, Step 1.
37
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 16 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
FOLDOUT FOR PROCEDURE E-1 1..
ADVERSE CONTAINMENT CON D[TIONS either of the conditions listed below occurs, THEN use adverse coi -ainntent setpotnts:
Containment atmosphere temperature 18DF OR Containment radiation leels 1.3x10 Rihr WHEN containment parameters drop below the above vaues, THEN normal setpoints can aga;n be ised IF conta[nnient integrated dose rate has not exceeded 10 Rads.
2.
RCP TRIP CRITERIA a.
IFal conditons listed below occur THEN trip all RCPs:
- 1) High.head SI pumps
- AT LEAST ONE RUNNING AND SI FLOWPATH VERIFIED
- 2) RCS subcooting
- LESS TI-IAN 2E.F[65F]
- 3) Confrolled RCS cooldown is NOT in progress b.
phase actuated, THEN trip all RCPs 3.
SI TERMINATION CRITERIA IF all conditions listed below occur, TI-lEN go to 3-EOP-E5-1.1, SI TERMINATION, Step 1:
a.
RCS subcooling based on core exit TCs GREATER THAN 30F(See below Tablel SI TERMINATION ADVERSE SLJBCOOLING VALUE RCS PRESSURE (PSIGI ADVERSE SUSCOOLING VALUE 2485 AND 2000
- 55 F 2000 AND 1000 85 F
<1000 210F b.
Total feed flow to intact SOs
- GREATER THAN 345 GPM narrow range IeeI in at least one intact SO
- GREATER THAN 6%32%)
c.
RCS pressure
- GREATER THAN 1600 PSIG[2000 psig]
STABLE OR INCREASING th PRZ level
- GREATER Ti-IAN 17%ESD%]
4.
SECONDARY INTEGRITY CRITERIA IF any SIC pressure is decreasing in an uncontrol ed manner OR has completely depressurized AND that S!G has NOT been isolated. THEN go to 3-EOP-E-2, FAULTED STEAt GENERATOR ISOLATION, Step 1.
5.
E-3 TRANSITION CRITERIA IF any Sf0 level increases iii an uncontrolled manner OR any SIC has abnormal rachation. THEN manually start SI pumps as neces.sarJ and go to 3-EOP-E-3, STEAM GEIERATOR TUBE RUPTURE, Scep L 6.
COLD LEG RECIRCULATION SWITCHOVER CRITERIA IFRWST level decreases to less than 155,000 gal ons, THEN go to 3-EOP-ES-t3 TRANSFER TO COLD LEG RECIRCULATION, Step 1 7.
RECIRCULATION SUMP BLOCKAGE RHR pump flow amps become erratic abnormally low after recirculation has been established.
THEN transition to 3-EOP-ECA-1.i, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
8, CST MAKEuP WATER CRITERIA C5TIevI decreasesto less than 10%, THEN add makeup to CST using 3-NOP-D1&01. Condensate Storage Tank (CST).
9 LOSS OF OFFSITE POWER OR SI ON OTHER UNIT jSl has been reset either affsite power is lostSI actuates on the other unit, THEN restore sareguarda equipment ro required onfigrnatAon. Referlo ATTACHMENT3 for essential loads.
RHR SYSTEM OPERATIOM tRITER IA RHft Iow i1ei4ha 1000 gpu THE!{4h8 Ri-fl puJapft shall )e suf dmfrn withiii $4 rninute pfth iniftal start signet CREW CRITICAL TASKflfRH shutdown within 44 minutes of the start signal.
38
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-302 Scenario No.: 3 Event No.: 8 Page 17 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior 4
Monitor Secondary Radiation Direct Nuclear Chemistry to take periodic activity samples of all S/Gs b
Direct Nuclear Chemistry to check DAM I SROIBOP monitor reading c.
Direct Health Physics to take radiation readings on main steamlines d.
Secondary radiation
- NORMAL NEAR d.
Go to 3-EOP-E-3. STEAM GENERATOR ROUTINE OPERATION VALUE TUBE RUPTURE, Step I.
CAUTION CREW If any PRZ PORV opens because of high PRZ pressure, it is required to be verified closed or isolated after pressure decre2ses to less than the PORV setpoint.
5 Check PRZ PORVs AND Block Valves a
Power to block valves
- AVAILABLE a.
Restoie power to block valves b
- CLOSED b.
IF PRZ pressure less than 2335 psig SROIATC THEN manually close PORVs. many valve can NOT be closed THEN manually close its block valve.
c.
Block valves
- AT LEAST ONE OPEN c.
Open one block valve unless it was closed to isolate an open PORV.
6 Verify SI
- RESET SROIATC 7
Reset Containment Isolation Phase A SROIATC Phase B 8
Verify Instrument Air To Containment a
Verify Instrument Air Containment Isolation, CV-3-2803
- OPEN S RO/ATC b
Verify instrument air pressure, P1-3-1444 b.
Restore instrument air pressure using GREATER THAN 95 PSIG O-ONOP-OI 3, LOSS OF INSTRUMENT AIR, while continuing with this procedure.
39
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 18 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B S/G isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior 9
Check Power Supply To All Charging Check diesel capacity adequate to wn three Pumps - ALIGNED TO OFFSITE POWER charging pumps. I.E adequate diesel capacity is NOT available THEN shed nonessential SROIATC loads Refet to ATTACHMENTS for component KW load ratincj 1 0 Check Charging Flow Established SRO/ATC a.
Charging pumps
- AT LEAST CItE a.
Perform ATTACHMENT 4 to estabksh RUNNING charging.
I)
Adiust speed controllers as necessary to esiabish desired charging flow to estabish SI Termination cond,tians c.
Adjust Charging Flow To Regen I-teat Exchanger. HCV-3-121. to maintmn proper seal injecdon flow 40
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 19 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior SRO/RO A1TACHMENT 4 (Page 1 of 1)
ESTABLISH CHARGING FLOW Verify ccw Flow Alarms To All RCP IF CCW flow to RCPs thermal barrier is lost, Thermal Barriers
- OFF pertorn the following:
A i/i, RCP THERMAL BARR COOLING EL Verify seal return temperature for each WATER HI FLOW RP to be less than 235 E AND
- b. j seal return temperature for each RCP
is less than 235 F, go to Step 2 A 1/2 RCP THERMAL BARR COOLING WATER HI TEMP C. j seal return temperature is 235 F, locally isolate seal injection to affected RCP(s) before starting charging A 1/3, RCP THERMAL BARR COOLING pui1p5.
WATER LO FLOW 3-297A for RCP A 3-297B for RCP B 3-297C for RCP C d.
WHEN seal injection is isolated to each affected RCP, to Step 2.
2.
Check Offsite Power Available IF offsite power is NOT available, THEN check diesel capacity adequate to run one charging pump. Ediesel capacity is NOT adequate. flj shed non-essential loads.
Refer to ATTACHMENT 3 for component KW load rating.
3.
Start One Charging Pump 4.
Place RCS Makeup Control Switch in STOP 5.
Establish Desired Charging Flow a.
Start additional charging pumps if needed a.
jf offsite power is NQI available, IH.Eti and offsite power available check diesel capacity adequate to run additional charging pumps.
c.
Adjust Charging Flow To Regen Heat Exchanger, HCV-3-121, to maintain proper seal injection flow d.
Verify charging pump suction auto transfers to RWST 6.
Notify The Unit Supervisor That The ESTABLISH CHARGING FLOW Attachment Is Complete 41
H B
CD
-3 (1)
U) 0 C) co u
o o
m o
D 0
0 H
CoD Co 0D Co 0
CA) m0 m
Cf)
DX C.>
(D CDO Cl, CD 0(i)
CD CDCo
- 0..
. 0 CD.
CD 0
0
-4.) )
r+
.CD CDO.
CD0 CD
- 0. z
,CI)
CD 0
0.
CD C,
(I, 0
Cl, CD CD CD (DC) l]10 n-I 1)1)
U)
H CI CD C
0 C)
Co
- 3 Co C)I 0
- 5 Co 0
CD Co 0
CD Q 3CD:5 CD
-t, H
CD
- 3C)
- D cx-.
o.
0 CD Co zp N)0 Cr)
C)
CD Co 0z p
CA) m CD
- 5 z
p 03
-3 Co (0
CD N)0 0
-4, N) 0)
mCO m Q0 Co 3Q rn C
0 c 0
-o
- 0<
CD I
- 3.
CI)
CD H £ C/)
- s-CD-.
g s-p n>
3 D 3
- Co CA) a c
(/)
CD:5 CI)o Co G)o 3
Co 03 CD ri I
o CD
?
CD CD-0
Co Co C)
- 3-C)
-+
_.)
__.)
CD UA 0 CD 3J Co Co
- 3 I,
Co CD C)
D_
c 1
C)CD Co CD Co (33 CA)33-C/)
(-
C).
_, J)
- 5 07CD Co CoCD CD Sico C)
Co
- 0 D
CD Co (15:5 Co CD CD
- 5:3 0
C) CQ
CD<
CD 0.
x CD
.0
-I CD0.
0 CD
-I 0
C, 0
Cl,
-n 0
m Cl)
C.
p z
c.D ocno r)
CrC CC)
N OU C)H Q.
n1.
2 rn9 c,,
C H
C) 0 ru CD H
CD 0
CD C.
rn U)
<)IC H
C)crC
(,
0ZC7 H
1D 0
mG)
Z0CD9 I
m H
H 0
H z
=
-?
>0 CD f
m 2
C DC UJZ1 C)
N CD (C
._(,
U)
U) 3o CD CD z =..
C
C)
NC
.;o CC.,
9 (CU, CDO
-(,
NC L
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-302 Scenario No.: 3 Event No.: 8 Page 21 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B S/G. After 3B S/G isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior 1.
Check The Load Centers Associated With Close the Load Center supply breakers.
The Energized 4 KV Buses ENERGIZED 3ALC BOP 3BLC 3CLC 3DLC 3HLC 2.
Check If Main Steamlines Should Be Isolated a
Check main steamline isolation and a.
Go to Step 3 bypass valves
- ANY OPEN b
Check if either main steam isolation b.
Go to Step 3 signal has actuated BOP High steam flow with either low S/G pressure 614 psig low Thvg 543 F OR Hi-Hi containment pressure 20 PSIG c.
Verify main steam isolation and bypass c
Push manual Steamline Isolation push valves
- CLOSED buttons on \\PB OR manually close valves BOP Places 3B Main Steam Isolation Valve to CLOSE.
CREW CRITICAL TASK : Places 3B Main Steam Isolation Valve to CLOSE is part of isolating the Faulted 3B SIG prior to exiting 3-EOP-E-2.
3.
verify Feedwater Isolation a.
Place main feedwater pump switches in STOP b.
Feedwater control valves CLOSED b.
Manually close valves.
c.
Feedwater bypass valves CLOSED c.
Manually close valves.
d.
Close feedwater isolation rvlovs d.
Locally close valves.
e.
Verify standby feedwater pumps OFF e.
IF standby feedwater is aligned to Unit 3, IHEt.{ stop standby feedwater pump(s).
- BOP Places Main Feedwater Pump switches in STOP.
43
Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 22 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B S/G isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior 4.
Verify Proper ICW System Operation a
Verify ICW pumps
- AT LEAST TWO a.
Start ICW pump(s) to establish at least RUNNING two running.
b.
Verify ICW to TPCW Heat Exchanger
b.
Manually close valve(s). JE valve(s) can ISOLATED I be closed, IE locally close the BOP following valves:
POV-3-4882 CLOSED 3-50-319 for POV-3-4882 POV-3-4883 CLOSED 3-50-339 for POV-3-4883 c.
Check ICW headers
- TIED TOGETHER c.
both ICW headers are intact, THEN direct operator to tie headers together.
5.
verify Proper CCW System Operation a
CCW Heat Exchangers THREE IN a
Perform the following:
SERVICE 1)
Start or stop CCW pumps as necessary to establish ONLY ONE RUNNING CCW PUMP.
2)
Verify Emergency Containment Coolers
- ONLY TWO RUNNING 3)
Go to Step Sc.
b CCW PU WS
- ONLY TWO RUNNING b.
Start or stop CCW pumps as necessary BOP to establish ONLY TWO RUNNING CCW PUMPS.
- TIED TOGETHER c.
both CCW headers are intact, direct a field operator to tie the headers together.
d RCP Thermal Barrier CCW Outlet, d.
IF containment isolation phase B NOT MOV-3-626 OPEN actuated AND CCW radiation levels are
- nonnal, RCP number one seal leak-off temperature is less than 235F.
IUE. manually open MOV-3-626.
MOV-3-626 can.QI be manually opened. IE direct operator to open MOV-3-626 locally.
6.
verify Containment Cooling a.
Check emergency containment coolers -
a.
Manually start or stop emergency ONLY TWO RUNNING containment coolers to establish
- ONLY BOP TWO RUNNING.
b.
Verify emergency containment filter fans b.
Manually start emergency containment AT LEAST TWO RUNNING filter fans.
44
[ Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 23 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B SIG. After 3B S/G isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position Applicants Actions or Behavior 7.
Verify Pump Operation a.
At least two high head SI pumps running a.
Manually start high-head pump(s).
BOP b.
Both RHR pumps running b.
Manually start RHR pump(s).
8.
Verify SI Flow a.
RCS pressure
- LESS THAN 1600 PSIG a.
Go to Step 9.
[2000 PSIG]
b.
High-head SI pump flow indicator
b.
Manually start pumps AND align valves to CHECK FOR FLOW establish an injection flowpath.
c.
RCS pressure
- LESS THAN 250 PSIG c.
Go to Step 9.
[650 PSIG]
d.
RHR pump flow indicator d.
Manually start pumpsQ align valves to CHECK FOR FLOW establish an injection flowpath.
9.
Realign SI System a.
Verity Unit 3 high-head SI pumps
- WiO a.
Perform the following:
RUNNING I)
Operate Unit 3 and Unit 4 high-head SI pumps to establish injection to Unit 3 from two high-head SI pumps.
2)
Direct Unit 4 Reactor Operator to align Unit 4 high-head SI pump suction to Unit 3 RWST using BOP ATTACHMENT 1 of this procedure.
3)
Goto Step 10.
I).
Stop both Unit 4 high-head SI pumps AND place in standby BOP Places the handswitches for the 4A and 4B HHSI pumps to STOP.
45
w0
-U CD a
x 0
CD (1)Iz p
Q 0
cx 0
()
CD CD DC CD C)
-U C-)
00 p
Cp
- 30.
C,,
CD
- 30 3
D)
C)0 CD D
D CD
- 3 C) u0 CD Z,C zD
-IIm>
(I)
I 0zm
<0
<CD C)0 0
0 3
DC C)0
- 3 0)
- 3 3
CD
- 3 C)00 (IC p
z.
CD<
1C) r CO r 0
-i>
ICC (p
0)
C)
CD
- 3 U)
-S 0
z p
C) p (n
00 0) 0-o C,,
m Cj()U) JQ:3 m--
c o
O<
CD 3
U)
C/)
_wCD (D
-.-D U) 3 U) c OJ:3 c
CD
-.-I, f
o
.-CD
?
rn
- U) 4-r.
T1 T.
C CD I -
T U)
C) 3 C)
_5
_5 CD L 0 CD w-U)
U)
- 3
-4, CD o
C)
T 0CD 0
- 3-,-
U)
CD U)
ED rCD <
C)_.
C.,
U)
I U)CD CD c2.U) C)
U) o -o o
- 3U)0:3 0(p D
o-Q-.
U)
CD CD
- 3:3 (0
C!)
00 0)
C)0 U)
G) 0 0
Ci)
CD
-U cn CD
-C CDa 0
CD 0
-I C,
0 Co F-m CD
- 3 z
p co
- 3 CD
-I
-0 0
- 3
- 3
- 3-
- 3 0
CD CD (0
C-)
0 (I) 3 CD:3 C)0 CD
- 3
-ci U)
(0 CD 0
-4, N) a)
1 0
m C,,o
)
Appendix D Required Operator Actions Form ES-D-2 j Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 25 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B S/G. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to3-EOP-ES 1.1 to terminate SI.
Time
[
Position Applicants Actions or Behavior 15.
Monitor Containment Pressure To Verify Containment Spray NOT Required a.
Containment pressure - HAS REMAINED a.
Perform the following:
LESS THAN 20 PSIG 1)
IL containment spray jjQI initiated, PR-3-6306A
]J:i manually initiate containment spray.
AND 2)
Verify Containment Isolation Phase B BOP PR-3-6306B
-ACTUATED.
3)
Verify Containment Isolation Phase B valve white lights on VPB
ALL BRIGHT.
4)
I.E any Containment Isolation Phase B valve did NOT close, THEN manually or locally isolate affected containment penetration.
5)
Stop all RCPs.
16.
Verify Containment and Control Room Ventilation Isolation a.
Unit 3 containment purge exhaust and a.
Manually stop fans.
BOP supply fans OFF b.
Verify Control Room ventilation status h.
Manually align eqinpment for Control panel
- PROPER EMERGENCY Room emergency recirculation.
RECIRCULATION ALIGNMENT I
NOTE BOP Hydrogen Monitors should be in se,vice within 30 minutes of a valid Si signal. They should j
be available in a timely manner to support decision-making related to hydrogen generation in containment.
S
a a a a
- 17.
Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST BOP ACCIDENT MONITORING SYSTEM 18.
Verify All Four EDGs RUNNING EMERGENCY START any available EDG NOT running.
BOP 47
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-302 Scenario No.: 3 Event No.: 8 Page 26 of 26 Event
Description:
A Main Steam Line Leak upstream of the 3B MSIV inside Containment gradually develops. A manual or automatic Reactor Trip occurs. The crew responds using 3-EOP-E-0. The crew transitions to 3-EOP-E-2. The BOP ensures 3B MSIV is closed. The crew isolates the 3B S/G. After 3B SIG isolation, the crew transitions to 3-EOP-E-1 and, subsequently, to 3-EOP-ES 1.1 to terminate SI.
Time Position
[
Applicants Actions or Behavior 19.
Verify Power To Emergency 4 KV Buses and Load Centers a.
Check the 3A, 3B and 3D 4 KV buses -
a.
Perform the following:
ALL ENERGIZED 1)
Inform the Unit Supervisor that ATTACHMENT 3 is complete v/ith the exception of the de-energized bus or buses.
2)
IF the Unit Supervisor decides not to energize the de-energized bus or buses, THEN go to Step 20.
- 3) f the Unit Supervisor decides to energize 3A, 3B, or 3D bus, THEN perform the following:
a)
IF 3A 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.2, LOSS OF 3A 4KV BUS.
b) j 3B 4 KV bus dc-energized, THEN restore power to bus using 3-ONOP-004.3, LOSS OF 36 4KV BUS.
c)
IF 3D 4 KV bus dc-energized, THEN restore power to bus using 3-ONOP-004.5, LOSS OF 3D 4KV BUS.
20.
Notify The Unit Supervisor That The PROMPT ACTION VERIFICATIONS Attachment Is Complete And Discuss Any BOP Safeguards Equipment That Is Not In The Required Condition 48