ML022260382
| ML022260382 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/03/2002 |
| From: | Otten M Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-237/02-301, 50-249/02-301, ES-301-4 NUREG-1021, Rev 8 | |
| Download: ML022260382 (95) | |
Text
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility D
[
L:/I Date of Exam Scenano Numbers t
, /
Operating Test No/Lrc, QUALITATIVE ATTRIBUTES Initials a
b" cO 1
The initial conditions are reaiistic. in that some equipment and/or instrumentation may be out of service. but it does not cue the operators into expected events IrI' 2
The scenanos consist mostly of related events M2 3
Each event lescnption consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
- 4.
No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenano without a credible preceding incident such as a seismic event.
5 The events are valid with regard to physics and thermodynamics.
,A C
- 6.
Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives..-H
- 7.
If time compression techniques are used, the scenario summary clearly so indicates. Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.,,A
- 8.
The simulator modeling is not altered.
,"0
- 9.
The scenarios have been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
t(40
- 10.
Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.4 of ES-301.
M'0.-
A
- 11.
All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
me -*)*
- 12.
Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
____ t-,4,
- 13.
The level of difficulty is appropriate to support licensing decisions for each crew position.
.10' TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION D.4.D)
Actual Attributes
- 1.
Total malfunctions (5-8) q/7,1 8 / 5/1 4e'
")
- 2.
Malfunctions after EOP entry (1-2)
I / //
z ! / /4.
o
- .4O,
- 3.
Abnormal events (2-4) q/1
/ -/
/
,4/
- 4.
Major transients (1-2) 1//
/
I /12/
e
- 5.
EOPs entered/requirng substantive actions (1-2)
/ /
z3 I 2_._/ 2_
j,
- 6.
EOP contingencies requirnng substantive actions (0-2) f//
/ / //
1
/
- -0
- 7.
Critical tasks (2-3) 3/3/
z, Z /q 41
,,,v/,
4 NUREG-1021, Revision 8, Supplement 1 24 of 26 Exa-- Subm i t ta I
Dresden Generating Station SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-1 Rev. 00 02102 DEVELOPED BY:
APPROVED BY.
Exam c
utR sa Date Facility Rez esent rtive Date SimScenario-ILT-N-1.do-Master Copy
Appendix ID Form LS-D-1 Facility: Dresden Scen_ :
No: ILT-N Examiners Op-Test No. ILT 01-1 O: ÷-ators Initial Conditions: -33% reactor power RM channel "-ý out of service; 2B EHC Pump OOS; Unit 3 is in Mode 4.
Turnover: Unit startup in progress; pt0--then trar-Ser FWLC to 3-element control.
Event Type*
R NSO SRO N
NSO ANSO SRO C
ANSO SRO ALL M
Event Description raise reactor pcver recirculation flow
-ansfer FWLC :: 3-element control szurious openir z of main turbine bypass valve
/-RPM channel fails downscale
/-RPM channel companion IRM 15 spike upscale c-ausing partial half-scram r-ain feed~breake 'r to Bus 23-1 trips with failure of emergency diesezi generator to start automatically falure of RPS tc Jieenergize and ARI to initiate ANSO H33, H44 SRO t-o or al reactor -eed pumps (N)ormal, (R)eactivity, (I)nstrument, 3)omponent.
V)ajor Page 2 : 23 A u t n ()
-or
'V
':JREG-1021, Revision 8, Supplement 1
., aL i on Event Malf.
N7o.
3 4
5 6
7 No.
N/A N/A EHD626 NIA5POT Ni115POT B15 K49 T12 B12 AW4 H31, H32,
-narno Owl
Dresden Generating Station NRC ILT EXAM Scenario ILT-N-1 Scenario Ob ÷ctive Evaluate th-e : :rators in using the Failure to Scram contingency procedure.
Scenario Summary Initial Condi" :-s
-33% pc,,,r-, unit startup in progress 0
IRM 16 C 3S 0
2B EHC Kmap OOS Unit 3 is - Mode 4 Events:
"* Raise Pc,, er with Recirculation Flow
"* Transfer N.VLC to 3-Element Control
"* Spurious Eipass Valve Opening
"* APRM Fa Downscale with Partial Half Scram
"* Bus 23-1 _css of Power "
"* ATWS (Fa ure of RPS and ARI) with Loss of RFPs Scenario Sequence
"* The crew -creases reactor power by increasing recirculation flow.
"* The crew :-ansfers the FWLC system to 3-Element control.
"* The main :urbine bypass valve #1 opens spuriously. The valve is closed when the ANSO takes manual ac:on at the EHC control panel
"* APRM channel 5 fails downscale followed by a companion IRM 15 spike upscale and a partial half scram occurs. The NSO inserts a complete half-scram.
"* The SRO addresses the technical specification requirements for the ARPM channel. The APRM channel is oypassed but the half-scram should not be reset by the NSO.
"* The main 'eed breaker to Bus 23-1 then trips and the 2/3 EDG fails to automatically start. The 2/3 EDG does run when manually started by the ANSO and power is restored to Bus 23-1.
"* A Spurious Channel A scram occurs. An ATWS condition exists due to a failure of RPS A to deenergize and ARI is unsuccessful. The crew should perform the ATWS DEOP. Pulling RPS fuse-venting the scram air header and driving control rods are successful. The event is complicated by a loss of RF-)s and the crew should control RPV level using the HPCI and / or CRD system.
"* The scena-o is terminated when all rods are inserted and the plant stabilized.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 3 of 23 Rev. 00 (02/C Au t n or-fot Val dation
Event One: Raise Power with Recirculation Flow The crew raises reactor powef Iy incfeasinr recircula':-*
Malfunctions required 0 Success Path 0
Increase recirculation flow per procedures.
Event Two - Transfer FWLC to 3-Element Control The crew transfers FWLC to 3-Element control per DOP D-06, Feedwater Regulating Valve (FRV)
Operation.
Malfunctions required: 0 Success Path:
Follows DOP 0600-06.
Event Three - Spurious Bypass Valve Opening The crew should recognize and respond to main turbine b, :ass valve #1 opening spuriously. The valve will close when the ANSO takes manual action at the EHC :antrol panel Malfunctions required: 1 (Bypass Jack drift)
Success Path:
Close the bypass valve with the bypass jack.
Event Four and Five-APRM Fail Downscale/Partial Haf Scram The crew should recognize and respond to failure of APR1,'
5 downscale and a channel B partial half scram.
Malfunctions required: 3 (APRM fail downscale)
(IRM spike upscale)
(partial half scram)
Success Path:
"* Bypass APRM channel 5
"* Manually scram RPS channel B ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 4 of Z Rev. 00 (02/02)
AU t no/0r f o r Va io n
Event Six - B-S 23-1 Loss of Power The crew rec-
--es and responds to a oss of norrcal power tF automatically Malfunctions
.ed:
2 (Bus 23-1 feed breaker trips)
(EDG 2/3 fails to auto start)
-1 arlO -
ofthe 2/2) EDGt Success Path Manually -z-ws the 2/3 EDG Event Seven a -d Eight - ATWS (Failure of RPS and ARI) with Loss of RFPs The crew shoL
-ecognize and respond to an ATWS condition witý a loss of RF:s Malfunctions reý :ired: 3 (RPS failure to deenergize)
(failure of ARI)
(Loss of RFPs)
Success Path
"* Inserts roezs.sing alternate methods.
"* Control RF. ievel with HPCI and / or CRD.
Scenario Recapitulation Total Malfunctic-s:
Abnormal Ever:s:
Major Transien:s:
EOPs Entered:
EOP Continger ties:
9 4 1 1
1 (ATWS)
(ATWS)
ILT 01-1 NRC E/AM, Scenario ILT-N-1 Au t n-or Page 5 of 23 for val I dat o,
Rev. 00 (02/02)
Appendix D Op-Test No: ILT 01-1 ILT-N-1 I veý-t No 1
Page 1 of 1
Event
Description:
Thn-
-ears raise Time Position
,ver using recircUlation flow Applicant's Actions or Behavior NSO Performs - - following actions per DGP 01 -01, Unit Startup, and DOP 0202 03, Rea::: Recirculation Flow Control System Operation:
r es recirculation pump speed using the master controller 7etiometer.
e -s expected power increase.
SRO Directs rE z -g reactor power per DGP 01-01, Unit Startup, and DOP 0202 03, Reac: Recirculation Flow Control System Operation, by raising recirculat: --ump speed.
ROLE PLAY:
QNE: reqLzest for a ramp rate, respond "limit ramp rate to,250 MWe/hr".
Monitors :.-=-els and assists as directed.
Event I Completion Criteria:
Signific-ant power increase.
o AND, a' the direction of the NRC chief examiner Ga A9054 i1'?A ILT 01-1 NRC EXAM, Scenario ILT-4,-"
/
_/1.
1//
- J LfIT~Cflu Wf Page 6 of 23 r
for Val idat on
/'
- _L1/
,oa o
Rev. 00 (02/02)
ANSO
ý0 --
j /V
-6 M b A-I I
E II L
Operator Ac~tion-,
I orn) fSD-
/
I
Operator i\\ct(oI Op-Test No ILT01-Scenario No ILT-N-1 Event No 2
Event Description The crew transfers Feedwater Level Control System to 3-Elerner: - -'trol Time Position Applicant s Actions or Behavior NSO Performs the following actions per DOP 0600-06, Feedwate-Regulating Valve (FRV) Operation:
Verifies the AUTO Control mode pushbutton is not D--er.
Verifies that annunciator 902-5 G-8, 1 -Element FA
-itrol Active at Hi Flow, is in alarm Verifies that FWLCS is in Master Auto.
P Depresses AUTO pushbutton and verifies that the -
-O and 3-ELEM white indicating lights are lit and the 1-ELE',' ght goes out.
SRO Directs transferring FWLC to 3-Element Control per DOP 0- - -06,:
Feedwater Regulating Valve (FRV) Operation.
Note: RPV level may take a couple of inch swing during the 7ansfer to
,3-Element Control, so the NSO may take Manual Control of t:ie FRy. If the crew requests Instrument Maintenance (IMD) assistance to c.n*"ck out FWVLC, tell the crew that you are time compressing and that IMD rep.: rts the FWLC system is functioning normally. The crew should then transfe-FVVWLback to AUTO Mode.
ANSO Monitors panels and assists as directed.
Event 2 Completion Criteria:
AND, at the direction of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 7 of 23 Rev. 00 (02/02)
A U
r)l0or for Va I i, a t i,rn roe 1 of 1
Appendix D Sfiorl F!S P-2
erator /\\ctnons Op-Test No ILT 01-1 Scenario v:
T N-1 Event No 3
Event Description The main turbine b, ANSO takes manuL alve #1 opens spuriously The valve is closed when
Applicant's Actions or Behavior SIMULATOR C= =RATOR:
At the discretic-the NRC chief examiner, activate trigger 1, which wor-s in conjunction wi:- :ger 2 to open the #1 turbine bypass valve until the pastial open light is lit If after 2 minute: -. e team has not noticed the bypass valve open, activate trigger 16, whic-,,,)rks in conjunction with trigger 17 to open the #1 turbire bypass valve u- :he full open light is lit and the bypass valve open alarm is received.
Note: when the ::-=-w depresses the bypass valve jack decrease pushbutton, triggers 18 and "-: will activate to delete the bypass jack increase pushbutton and light overrio-:e...
Performs the fo.:,,,ing actions per DAN 902-7 G-3, Turb Byp Vlv Open, and/or DOA 56,:'-.D3, Turbine Control Valve or Bypass Valve Failed Oper as directed:
1]
Verifies -actor pressure stable
[I Verifies :ass valve should be closed E] Closes :-e bypass valve with the bypass valve jack.
Acknowledges announces alarm 902-5 C-8, Main Stm-Turbine Stm 1%
Mismatch. He s- :,cld recognize it alarmed due to the bypass valve openir'-g.
Enters and direc:_* performance of DOA 5650-03, Turbine Control Valve o Bypass Valve F7 ;,e*'d Open.
1i Places s=rtup on hold.
E] Notifies Z-:ft Manager.
May refer to the z,:e technical requirements and determine:
E]
ITS 3.3 is not applicable.
E]
ITS 3.3 is not applicable.
F]
ITS 3.7 - s not applicable.
ROLE PLAY:
- Act_,
Qffe-mipte afte tie crewfvqiýý the bypass valve-ep~el, call the control room as the IM $eisranýI report "my. crew was h-66king tip a F-luke to take readings or te bypass valve control circuits in panel 93'1, in the AEER. The tech-3:ian thinks (e inadvertenfly-shorted btwe~p tq trminal points that may -;-ae caused t he bypass jack td oper*te. Then he disc6iered he was in the w-:-g panel. He was in the 902-31 panel instead-of the 903-31 panel. The Unit EHO Control system should operate normally now".
Respond as grc_:s notified.
Event 3 Comple:lon Criteria-Bypass va,-: closed AND, at the : ection of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 8 of 23 Rev. 00 (02 -2)
A U I, -
for Va i ýdat on Time Page 1
0 Appendix D Sormn LE- _-2
Operate-l I01orS D Dp-TestNo ILI1 -1 ScenarioNo ILTN-
-N 4&5 PIge 1
No 1
Event Description APRM channel 5 fails downscale RM 15 supscale and a partial half-scram occurs FieNSO inserts a comnlete half--
The SRO addresses the technical specification requirements for the ARPM c----e The APRM channel is bypassed but the half-scram should not be -eset by t- -
0SO Time Position Ap: icant's A- :-s or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief ex:-
ier, activate trigger 3, which fails APRM 5 downscale and 5 seconds I2oe-spikes IRM 15 upscale.
NOTE: trigger 4 activates on the half s.:.-am signal to remove IRM 15 upscale so it appears to be a spike.
NOTE: If the team attempts to reset th e half scram, trigger 5 will activate to fail the fuses for scram groups B2 ano 03.
NSO Performs the following actions per DC - 0500-02, Partial 1/2 or Full Scram Actuation:
LI Recognizes and announces -::-.ial half scram.
11 Manually scrams RPS chanre 3. (immediate action)
[I Determines all channel B scr;-- solenoid lights are off.
SRO Enters and directs performance of DC 0500-02, Partial 1/2 or Full Scram Actuation.
NSO Performs the following actions per DA', 902-5 C-6, APRM Downscale, as directed:
11 Notifies SRO L
ANSO Performs the following actions per DA', 902-5 C-6, APRM Downscale, as directed:
El Checks APRM parameters or 37 panel.
SRO References plant Technical documents I]
ITS Table 3.3.1.1.A-1, verifies sufficient RPS APRM trip channels (2 available /.2 required for B cha-nel)c
[i TRM Table T3.3.a-1, verifies s-ificient APRM rod block channels available (5 available / 4 requ -ed)
Directs bypassing'APRM 5.
Notifies the Shift Manager and IMD_
Events 4 & 5 Coripletion Criteria:
RPS channel B manually scramme.:
APRM 5 bypassed.
AND, at the direction of the NRC :ef examiner.
LT 01-1 NRC EXAM, Scenario ILT-N-1 Page 9 of 23 Rev. 00 (02/02)
Author for 1lda r) opendix D IForm L-S-D-2Z
Op fratoi i\\rtFons 1-1 ScenarioNo ILIN-1 Event No 6
Page 1 of 2
The main feed breaker to Bus 23-1 then trips and the 2/3 EDG fails to automatically start. The 2/3 EDG does run when manually started by the ANSO and power is restored to Bus 23-1 Time
" - zion ANSO NSO Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 6, which inserts failure of RPS to deenergize, pulls ARI fuses, and main feed breaker to MCC 23-1 trip with failure of 2/3 EDG to start automatically Diagnoses that Bus 23-1 has lost power and that the 2/3 EDG failed to auto start to pick up the bus Should perform the following actions of DGA 12, Partial or Complete Loss of AC Power, and DOA 6600-01, Diesel Generator Failure:
D Places the 2/3 EDG control switch to start.
Nl Dispatches an operator to the 2/3 EDG with Attachment A.
LN Verifies power restored to Bus 23-1 and Bus 28.
N1 Resets annunciators and verifies the ones remaining are expected.
D Dispatches an operator to check the U2 EDG trouble alarm May perform the following actions of DOA 6500-10, 4KV Circuit Breaker Trip if time permits:
D Dispatches NLO to check for signs of fault or overload.
N Verifies no other reason for trip.
Monitors panels and assists as directed.
ROLE PLAY:
NLOeto check Bus 23-i feed breaker (wait 3 min):
RepoThere are no targets up at the breaker".
NLO to perform Attachment A of DOA 6600-01:
JcL{av Respond "I will get a copy of Attachment A of DOA 6600-01 and complete it for the 2/3 EDG".
SIMULATOR OPERATQRIROLE PLAY:,
NLO to check U2 EDG trouble alarm (wait 3 mi):
Activate trigger 12 then report "the alarms were circulating lube oil and turbo charger lube oil pumps trouble alarms. The pumps are operating normally and the alarms have reset".
ILT 01-1 NPC E/.iM, Scenario ILT-N-1 Page 10 of 23 Rev. 00 (02/02)
Author f-or Va i
idat ion Op-Tesý ',
Event D-42 Appendý\\
Form ES-D-2
Operator Actions Op-Test No ILT01 Event
Description:
11 Scenario No ILT-N-1 Event ý,
The main feed breaker to Bus 23-1 then trips and start The 2/3 EDG does run when manually starte restored to Bus 23-1.
Page 2 of 2 3 EDG fails to automatically
'he ANSO and power is Time Position Applicant's Actions c- -* avior SRO Enters and directs actions for the following
--e permits:
DGA 12, Partial or Complete Loss c -
Power.
DOA 6600-01, Diesel Generator Fa DOA 0500-05, Loss of Reactor Prot-: :n System Bus.
DOA 6500-01, 4KV Bus Failure.
i DOA 6500-10, 4KV Circuit Breaker -
The major actions to direct are:
L7 Starting the 2/3 EDG
]
Verifying major loads reenergize.
SRO Notifies Shift Manager and EMD.
Role Play:
Acknowle.ge requests for actions not alread, -ddressed earlier. If the crew request status of previous requests, report "I =-- working on it as fast as I can".
NOTE: The intent here is to proceed to the n=e:- event soon after the 2/3 EDG is started and the crew has begun to ac :-ess recovery of equipmpent.
Equipment recovery is not necessary for the --mainder of the scenario.
Event 6 Completion Criteria:
2/3 EDG supplying Bus 23-1.
AND, at the direction of the NRC chief exE-*iner.
IcE
, S c V ILT 01-1 NRC EXAM, Scenario ILT4ý1-1 Page 11 of 23 Rev. 00 (02/02)
AU u
i-ror for-V aI 1t da ft i o,*
Appendix 1)
F-orm F2S-D-2
Appendix D Op TestNo ILT01-1 nano No 11 1 N-I Event No Event Description. A spurioný RPS Channel A sciam begins an ATWS condo:
perform'-- ATWS DEOP and insert the control rods The should uSc -- PCI for RPV level control Time Position
.e 1 of 4
-nm should 3nd the crew Applicant's Actions or Behaý I
I NSO NSO /
ANSO SIMULATOR OPERATOR:
At -_ discretion of the NRC chief examiner, activate trs -7z which causes a s: _ious RPS channel A half scam. --fý
,*F er6 Pe :-ms the following actions per DGP 02-03, Reactc-S-Presses scram pushbuttons Places mode switch in shutdown Check rods inserted; discovers rods not inserted.
Initiates ARI, checks rods, announces ATWS :onc :,:.
Pe'---ms the following actions per DGP 02-03, Reactc. S---
Verifies turbine and generator tripped (only if Gro: " nas occurred or reactor power has dropped low enough that this :-Duld occur)
Inserts SRM/IRMs Per:frms DEOP 400-5, Failure to Scram, actions as directe:
Places ADS to inhibit Places both CS pumps in PTL Pov, e r Leg Inserts IRMs & SRMs 4 Performs Alternate Rod Inserti May Inject SBLC.
Level Leg Rx Power >6%
- Terminates and Prevents injection except boron and CRD until RPV/L is _< -35 in.
4Maintains RPV/L between -164 in. and the level lowered to.
)n. (see specif5: actions below)
Rx Powe-- <6%
C Maintains -el between -164 and 48 in.
Pressure Leg Verifies turbine/bypass Valves maintaining RPV/P - :60 psig.
If MSIVs isolate, maintains <106Q p~ig using IC AE !/s and / or HPCI.
SIMULATOR OPERATOR I ROLE PLAY:
Operator to jumper the MSIV Group1 -59 in. and offgas hi ý -adiation isol:-,ions (wait 5 min):
Act',,ate trigger 8 (jumpers the MSIV Group1 -59 in. and off:.ss hi hi radiation isolations) and report "the MSIV Groupi -59 in. and offgas -: hi radiation isoýa:ions are jumpered".
ILT 01-1 NRC EXAM, Scenar: ILT-N-1 Page 12 of 23 Rev. 00 (02/02)
Au-tror for Va I dat ton C
Form [--S D-2
ppp'r\\atof,
mctEon s
OplTest No ILT01-1 Scen...
L :N-.1 Event No n
&8 Page 2
of 4 Event Description A spuriousPP
--- el A scram begins an ATWS condition The team should perform the AT,','-- --3P and insert the control rods The RFPs trip and the crew should use HPC :--'V level control.
Time Position Applicant's Actions or Behavior SRO Enters art,:
- -- s performance of DGP 02-03, Reactor Scram, and DEOP 100, RP,
-D.
Due to re-,:.
ATWS condition, exits DEOP 100 and enters and directs performa-,
-: DEOP 400-05, Failure to Scram.
E P;--c -
ADS to inhibit
-P.o-coth CS pumps in PTL Power Le:
S-\\ Directs any of the following control rod insertion methods (f-stz -,,, D most preferred) per DEOP 500-05, Alternate Insertion of C:,-7: Rods:
p-ng scram channel A solenoid power su ply fuses.
v e-ting the scram air header.
Z_.-
us -ig the scram test switches.
Ma-nually driving of withdrawn control rods. jA't") 2,' '>vI/1 C' a 0
M' May direct Injecting SBLC e.
Level Leq Od, ID Ve&1icEtion water level instruments are accurate
[I Ve-fiý=ion any required automatic actions have occurred ID Drect.-g jumpers installed for MSIV low level and Off Gas high Rad isclatic s Rx Dower >6%
Rx Power *6%
ý Terminating and El Maintaining level between Preventing injection
-164 and 48 in.
except boron and CRD until RP//L s* -35 in.
'1 Maintaining RPV/L between -164 in. and the level lowered to.
Pressure Le=q 0
Manta iing <1060 psig using turbine/bypass valves.
ID If I,1Slr's.isolate, maintaining <1060 psig using IC, ADSVs or HPCI.
ILT 01-1 NRC EXAM, Scenario ILT-N-"
Page 13 of 23 Rev. 00 (02/02)
-,r t\\) <D 0Am (Ls~
for Va I dat Ion A\\ppemlix D)
Form ESJ[)*-,,ý
Operator AciotFr iestNo I LT01-1 Scenaro No Il -N-1 Event No 7 &_8 Page 3
c ent Description A spunous RPS Channel A scram begins an ATWS condition The team shoulc perform the ATWS DEOP and insert the control rods The RFPs trip and the crý should use HPCI for RPV level control.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR / ROLE PLAY:
Note: For the first two requested actions below, wait about 10 minutes ar or at the discretion of the NRC chief examiner
- 1. Operator to pull scram channel A solenoid power supply fuses:
Activate trigger 10 (pulls Channel A RPS fuses and trips reactor feed purr:
and then after the fuses are all pulled report 'the scram channel A soleno!:
power supply fuses are pulled".
- 2. Operator to vent the scram air header:
Activate trigger 11 (vents the scram air header) and report 1 have vented -_
- 3. Operator to use tlh-eindividual scram test switches (wait?2 min):
Go to Instructor Station screen'ROD5 and begin simulati g flipping the scr-- 7 test switches. Follow the guidance in DEOP 500-05 for selecting rods.
If directed, attempts to drive withdrawn control rods in per DEOP 500-05, Alternate Insertion of Control Rods:
Z El May close CRD 25 charging water valve.
[I Throttles open the CRD FCV.
E) May start a second CRD pump.
El May maximize drive water pressure using the CRD 8 valve "E) Bypasses the RWM.
El Applies an insert signal tot insert rods/ K4)
ýSIMULATOR OPERATOR I ROLE PLAY:
NLO to close CR0 25 valve (wait 3 mmn):
Activate trigger 9 (closes the CR0D 25 valve) and report "the CR0D 25 valve closed".
Li Reports that all rods are inserted.
LI Li Restores RPV level to +8 to +48 inches as directed.
Begins cooldown as directed.
When receives report that all rods are inserted, exits DEOP 400-05, Failu-e to Scram and enters DEOP 100 and directs:
11 Controlling RPV water level between +8 to +48 inches.
1i May direct depressurizing the RPV at <100 OF/hr.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 14 of 23 Rev. 00 (02 -
A U t h O r-f-o Va I i d a t i on
, 5frt4l
NSO 4-O NSO ANSO SRO
-.,Icjlx [
Form E
A0) e0)iix [)
Foini S D-D!
Op-est No [LT01-1 Event
Description:
A s pe sh, Scenaro No ILT-N-'
SpLirious RPS Channel A scra--"
rform the ATV-S DEOP andc ould use HPCI for RPV level c Event No K&8 Page 4
of 4
ns an ATWS condition The team should
-e control rods The RFPs trip and the crew AppJ ---. s Actions or Behavior Critical Tasks: (identified b, in guide)
With a reactor scrar- _-quired and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to preve - exceeding the primary containment design limits 11 During an ATWS wit-Dnditions met to perform power/level control TERMINATE AND P;=-VENT INJECTION, with exception of boron and CRD, into the RF until conditions are met to re-establish injection. (May not a: :, if power becomes <6% before the step requiring this action is -eached) 11 When conditions are -et to establish injection use available injection systems to MAINTAIN' RPV water level above -164".
Scenario Completion Criteria:
Control rods inserted.
Plant stabilized.
AND, at the direction of tlhe=
NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 15 c23 Rev. 00 (02/02)
AU t i9r f Or i d a t I orn Time Position Opefatc- -
"S
REFERENCES PROCEDURE DAN 902-5 C-3 DAN 902-5 C-6 DAN 902-5 C-15 DAN 902-5 D-15 DAN 902-5 G-8 DAN 902-7 G-3 DOP 0202-03 TITLE Out Block
-'M Downscale
-.Inel B IRM Hi Hi/Inop
- 'tor Recirculation Flow Control System Op-_--:
REVISION 09 07 07 10 09 01 20 DOA 0500- 02
-.al 1/2 or Full Scram Actuation 02 DOA 0500-05 s of Reactor Protection System Bus 04 DOA 5650-03
-_-ine Control Valve or Bypass Valve Failed
--er 09 DOA 6500-10
-'Circuit Breaker Trip 03 DOA 6600-01
- -sel Generator Failure 12 DGP 01-01
-=-tial or Complete Loss of AC Power 47
)EOP 0100-00
- -:V Control 10 DEOP 0200-01
- - nary Containment Control 10 DEOP 0400-02 E-:ergency Depressurization 04 DEOP 0400-05
!ure to Scram 12 DEOP 0500-02
-assing Interlocks and Isolations 10 DEOP 0500-05
.-.:ernate Insertion of Control Rods 12 ILT 01-1 NRC EXAM. z:enario ILT-N-1 Page 16 of 23 AU th -r)r for Va I Rev. 00 (02/02)
PRE-SCENARIO ACTIVITIES If applicable, condu :Dre-s o activities rn accordance with TO-AA-106 0107 SIMULATOR EXAMINATION BR E-ING a
Provide the cre,,, vith of Control Room 'work request list b
Provide the tea-- with
_--y of DOGP 01-01, Unit Startup, which is marked up to the point of transferring FWLC to 3-Ele'-ent C.---
c If the crew inqu -es abe startup plan, inform then the Shift Manager is maintaining it.
- d.
Provide the crev, 'with a
-- '/ of the REMA
- e.
Inform the crew :nat (see:: an individual) is the ONE present in the Control Room.
- f.
Direct the crew : perfo-
- neir briefs prior to entering the simulator
- 2.
Simulator Setup (the 'ollowi-- _'eps can be done in any logical order)
- a.
Initialize simulatc-in IC ' -cnd perform the following prior to proceeding below:
I) Transfer Aux-iary Pc,,to the normal full power lineup.
i,
, at-,,--
.,)LC_
fvh~4~i~v C-d*
- 2) Use the Rodmove p,:..-cam to pull rods through step 72.
I
(
F, F-VdC.O5
- 3) After the roo move is :omplete, verify with the Rodworth Minimizer that rod moves are completed through steps Mae-corrections if necessary.
S74e--
//
- J--5-,
- 4) Run CAEP fle lit-n-1 cut in heaters.cae to cut in the heaters. (this will take over 5 minutes)
- 5)
After lit-n-I cut in heaters.cae has completed running, verify the heaters are latched. (no alarms)
- 6) Run the Summary p':gram and clear ALL remotes and overrides.
- 7) Verify 2A EHC and 2A Stator Cooling Water pumps running.
"*-/',V I
2s-
- 8) Verify FWLC is in I-E ement control.
c
-t
- 3
- 9) Verify backpanel lights are reset.
" /'3 f,*)-f-_hj-,
- b.
Run the initial setup caep zle: ilt-n-l.cae
- c.
Verify the following simula:or conditions:
- 1) Master Recirc Flow ccntroller at.
T.-ý.
- 2) MWe at -245.
- 3) Condensate Demin 1:1 between 20 and 45 psid.
- 4) Condensate pump ar-ms between 160 and 255 amps
- d.
Secure the following equ :ment and tag out ofservice:
- 1) Place IRM 16 902-5 ranel joystick in bypass and place an Equipment Status Tag on it.
- e. Advance the cha-t recorce-s.
- f.
Mark up rod sequence asee o,-&*.*,.tgvs.ep/
- h.
Complete the Simulator Seip Checklist.
ILT 01-1 NRC EXAM, Scenario IL--N-1 Page 17 of 23 Rev. 00 (02/02)
Autfl r-f-or Val i dat on
Comp.1ter,Vded F[xerc-se Progir n, ILT 01-1 NRC EXAM SCENARIO ILT-N-X Initial Setup CAEP:
- ilt-n 1 cue
- Setup for It-n-1
- Written by JAS
- Rev 00
- Date 02/02
- INITIAL CONDITIONS
- Inserts a partial RPS CH B scram failure and overrides the bypass jack increase light off imf b15 ior eh1626 off
- overrides isolation condenser vent monitor downscale.
imf ser0004 off imf serOO19 off
- SETUP EVENT TRIGGERS
- Event Trigger 1 in conjunction with trigger 2 causes turbine bypass valve #1 to ramp open ur: :he partial open light is lit.
trgset 1 "0" ior ehd626 (1) depressed
- Event Trigger 2 turns off the bypass jack increase override when the partial open light is lit.
trgset 2 "ehlbpvi(1)"12 trg 2 "ior ehd626 off"12
- Event Trigger 3 ARPM channel 5 fails downscale and 5 sec later spikes IRM 15 upscale trgset 3 "0"12 imf nia5pot (3) 0.012 imf nii15pot (3 5) 12512
- Event Trigger 4 removes IRM 15 spike when half scram received.
trgset 4 ".not. rpxgpllb"14 trg 4 "dmf niil 5pot"14
- Event Trigger 5 when scram reset switch is placed in GP 2&3 position, causes blown fuse RP S B2 and B3.
trgset 5 "rpd30323"14 irf rpfuseb2 (5) pulledj4 irf rpfuseb3 (5) pulled14
- Event Trigger 6 inserts failure of RPS to deenergize, pulls ARI fuses, and main feed breaker MCC 23-1 trip with failure of 2/3 EDG to start automatically trgset 6 "0"14 imf b12 (6)14 irf aw4 (6) pulledJ4 irf k45 (6) open14 imf t13 (6)14
- Event Trigger 7 pulls scram fuse for group A4. tr-.i "J~i
- r "eL
/
trgset 7 "016 irf rpfusea4 (7) pulledl6 R-- Q
trgset 8 "0"16 ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 18 of 23
-ev 00 (02/02)
Autktlor for Val dat i (r
, ý ¢151ý9jp ý8) In6 irf ogcgjp (8) inJ6
- Event Trigger 9 closes CRD -5 vaKve trgset 9 "0"!6 irf rd25pos (9) 0 016
- Event Trigger tG4f4 P
piLIs RP trgset 10 "0"18 irnf h31 (10) 8 imfh32(10)18 k*v'c>
imf h33 (10)18 imf h34 (10)18 irf rpfuseal (10) pulledI8 irf rpfusea2 (10 20) pulledI8 irf rpfusea3 (10 40) pulledl8 7annel A fuses
- Event Trigger 11 vents the scram air heade trgset 11 "0"110 irf rdscrair (11 ) open110
- Event Trigger 12 locally acknowledges U2 E- - trouble alarm.
trgset 12 "0"110 irf t20 (12) acknowledgel 10
- Event Trigger 16 in conjunction with trigger
-auses turbine bypass valve #1 to ramp open until the oa-:.al open light is lit.
trgset 16 "0"110 trg 16 "ior ehd626 depressed"I 10
- Event Trigger 17 turns off the bypass jack ir: :ease override when the full open light is lit.
trgset 17 "ehlbpvo(1)"112 trg 17 "ior ehd626 offI12
- Event Triggers 18 and 19 delete the bypass pushbutton is depressed.
trgset 18 "ehd627"112 trg 18 "dor ehd626"I12 trgset 19 "ehd627"112 trg 19 "dor ehl626"I 12
, increase pushbutton and light overrides when the :ecrease
- END ILT 01 -1 NRC EXAM, Scenario ILT-N-1 Page 19 of 23 Rev C, 02 D2)
AL,,,
for Va I I da
- i.
1 on
Da*:*
-ODAY Unit 2 Turnover ECCS Status:
All Online Information Shutdown Information 245,We M
1 I Time to Boil: N/A Online Risk:
Green CDF:
1.00 Shutdown Risk: N/A Risk Equipment:
Protected Path: N/A Unit 2 Priorities Station Priorities Con: -ue startup LCORAs LCORA #
Start Title Clock Ends Shift I Activities (X = Completed)
Shift 2 Activities Shift 3 Activities
[]
nl Continue Pove-Ascension El El El El I Common U-it Activities Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities Fl El Fl El El El Common Unit Procedures / Surveillances in Progress Unit 2 Conditions, Status, Abnormalities 2 hr ago 0500 IRM 16 OOS due to power sup:,.i failure. IMD waiting for replacement power supply to arrive from Quad Cities Stator :laced in DEL for tracking.
6 hr ago 5650 2B EHC pump OOS due to a p:olem with its pressure compensator. Expected BIS next shift.
Compensatory Actions, Extra Checks ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 2' -- 23 Rev. 00 (02/02)
Au tl L h O d a t I Onl
Equipment 0>
2 hrago 99L ---
6hrago 99.
54
- 52 RM 16 "AB FHC pumn Service Unit Status 9 days ago 7 clays ago 1 clays ago 2 days ago 11 days ago 6 days ago 2 days ago 376 days ago 240 days ago 20 days ago 76 days ago 2A Cond Den in 21 Cond Detain 2C Cond Dei r 2D Cond Demin 2E Cond Demir 2F Cond Detan 2G Cond Dernin 2A RWCU 2B RWCU 2C RWCU U2 FPC Demin Unit 2 Abnormal Component Position U2 Open Operability Determinations with Compensatory Actions Events and Misc. Information DGP 01-01 in :-egress. Continue the startup.
DW samples:
Iodirne 231 Beta Gamma 2.5 X 10-13 1.5 X 10-11 ji ILT 01-1 NRC _/AM, Scenario ILT-N-1 Page 21 of 23 Rev. 00 (02/02)
Au I hlor-for Va I
dat ton ctit In Cut In C(,tt In Cut Out Cut Out Cut Out Cut Out Cut In Cut Out Cut Out Cut In
Date TODAY Unit 3 Turnover ECCS Status:
All available Online Information Shu
- ,vn Information N/A MWe MODE 4 T
T oBoil: 24hrs.
Online Risk:
N/A S- _sown Risk: Green Risk Equipment: N/A P.r: ÷ted Path: None Unit 3 Priorities Stat
- Priorities Complete startup checklists LCORAs LCORA # None Start Title Clock Ends Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities Q
Ii D]
El ED Common Unit Activities Shift 1 Activities (x = Completed)
Shift 2 Activities Shift 3 Activities LI D]
El EI lI Common Unit Procedures / Surveillances in Progress None Unit 3 Conditions, Status, Abnormalities DGP 01-S1, Start-up Checklist, in progress.
IMD taking voltage readings in the EHC Control Panel 903-31.
Compensatory Actions, Extra Checks None ILT 01-1 NRC EXAM, Scenario ILT-N-1 Page 22 of 23 Rev. 00 (02/02)
Au t hor for
/,/a I i doa
Equipment OOS None Service Unit Status days ago days ago days ago
- days ago 3 days ago 15 days ago 3 days ago 750 days ago 390 days ago 60 days ago 444 days ago L
Unit 3 Abnormal Component :-Dsition None U3 Open Operability Determir -tions with Compensatory Actions None Events and Misc. Information DGP 01-S1, Start-up Checklist - progress ILT 01-1 NRC EXAM, Scenani _T-N-1 Page 23 of 23 Rev. 00 (02/02)
Au t r)or i cr Va I dat on "Denrr[
Dentin
- Deiiin Detain Detain Detain
- Detnin
_ U 2U
_U Demin Cut In COLt In C ut In Cut Out (BUt Out CLt OLt Cut Out CuLt In Cut Out Cut Out Cut In
Dresden Generating Station SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-2 Rev. 00 02/02 DEVELOPED BY:
Exam \\u 0-,"
Date APPROVED BY:
Date SimScenario-ILT-N-2.doc Master Copy
AL penhix D Sccnario Ojtline Formn Facility Dresden Examiners Scenario No I[T-N-2 Operators:
Op-Test No ILT01 Initial Conditions: Unit in Mode 2 at approximately 2% reactor power; IRM channel 16 out service; 2B EHC Pump OOS; Unit 3 is in Mode 4.
Turnover: Unit startup in progress, return TBCCW pump 2B to service following maintenar :
then continue power ascension Event Malf.
Event Event No.
No.
Type*
Description ANSO 1
N/A N
SRO swap TBCCW pumps NSO 2
N/A R
SRO raise reactor power by withdrawing control rods NSRO 3
RODC13DO C
NSO control rod double notches during withdrawal NSO 4
NII12POT I
SRO IRM channel fails upscale ASRO 5
PCPDWTOR I
ANSO drywell to torus differential pressure controller failure SRO 6
HP8 C
ANSO circulating water pump trip SRO ANSO 7
CSBRKSEV M
SRO lowering torus level from ECCS suction line break ANSO 8
J33 C
- ~~~~~~~~~~
kLo....-.
I
+/-.....
n kiJ~~~~ormai,~~/
4 "ec intu etk~
moet
~Iao W,1(0~-
- ,k b(7 r Page 2 of 21 NUREG-1021, Revision 8, S -:lement 1 Au t hor f or va I i(jat on A-ppendix D)
Scenario Outline Form
Dresden Get,,'ating Station NRC IL-EXAM Scenaric ILT-N-2 Scenario Objective Evaluate the operators in using the Emergency Depress- -ation DEOP contingency procedure Scenario Summary Initial Conditions:
Mode 2 at approximately 2% reactor power.
IRM channel 16 out of service.
2B EHC Pump OOS Unit 3 is in Mode 4.
Events:
Swap TBCCW Pumps Power Change with Rods Control Rod Double Notch IRM Channel Fails Upscale Drywell to Torus Differential Pressure Controller Failu-e Circulating Water Pump Trip
_ A.,
j S -
(
'---i S
Lowering Torus Water Level Scenario Sequence
"* Maintenance has been completed on TBCCW pump 2B and the SRO directs the ANSO to switch running pumps and place the TBCCW pump 2B in service.
"* The NSO, as directed by the SRO, then continues the Dower ascension for unit startup by control rod withdrawal.
"* During the control rod withdrawal, a control rod double notches beyond the withdraw limit and must be repositioned.
"* IRM channel 12 then fails upscale and a half-scram occ:urs on the RPS "A" channel. The NSO bypasses the failed IRM channel and the SRO addresses the techn cal specification requirements for the failure.
"* Drywell to torus differential pressure then begins to decrease and pressure control is regained when the ANSO takes manual control of the drywell to torus differential pressure controller.
"* Circulating water pump 2C then trips on overload and *he ANSO manually starts circulating water pump 2B to maintain condenser vacuum.
An ECCS suction line break occurs resulting in a lowe-ing torus water level. HPCI spuriously initiates 5 minutes later. The HPCI System should be secured, t-e reactor scrammed and an emergency depressurization performed as directed by the DEOP 'or primary containment control. The EHC system -s lost when the reactor is scrammed.
The scenario terminates when an Emergency Depress irization has been performed.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page of 21 Rev. 00 (02 02)
Auk. t. r) O r-fOQ)-
i I I a-t o on
Event One - 7,vap TBCCW Pumps The crew s..
T BCCVV pumps by staitirg 2B FBCCW pV m pping thie 'A TBCCW pL mp Malfunctions
_.ýjred 0
Success Paý 2B TBC__
Dump started and the 2A TBCCW pump stopp-Event Two - = cwer Change with Rods The crew inc-eses reactor power by withdrawing control rods DP 0400-01, and DGP 03-04, Malfunctions
- --uired: 0 Success Pat Control r: ::s pulled per applicable procedures.
Event Three - Control Rod Double Notch The crew rec:.:mizes and responds to control rod that double nc:ch--s. The crew should insert the control rod to its target positic Malfunctions "equired: 1 (control rod double notch)
Success Patr The cont-: rod moved to its target position.
Event Four - IRM Channel Fails Upscale The crew recc.:nizes and responds to an IRM failing upscale result - g in a half scram.
Malfunctions,equired: 1 (IRM Fails Upscale)
Success Path Bypasses :i*e IRM and resets the half scram.
Event Five - Drywell to Torus Differential Pressure Controller Failure The crew rec: :2*izes and responds to a failure of the automatic "',:- of the drywell pressure controller.
Malfunctions
- luired: 1 (Controller input fails high)
Success Pat Place the :-ywell to torus differential pressure controller in r'-a_ 7l mode and controls differential pressure manually ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 4 of 21 Rev. 00 (02/02)
AU/
uthor-for Vf-o I
o n
/
<NC{
/
IT- "s q Event Six - CirculatinqV,ater Pump Trip The crew should Fecognir:
ý-d respond to Circulating water pump 2C tripping on overload The ANSO should manually start circ ating,,*er pump 2B to maintain condenser vacuum Malfunctions requ -d:
1
___ulating Water Pump trip)
Success Path:
0 Start 2B Circu 3nng V', 3ý.er Pump Events Seven and Eight - Torus Leak The crew should recognize.and respond to a lowering torus water level.
Malfunctions requred: 3 (--:us Leak) r2§,
EHC pump trip)
-f.CI spurious initiation)
Success Path:
Prevent HPCI operatio Emergency Depressur:ze Stabilizes the plant Scenario Recapitulation Total Malfunctions:
Abnormal Events:
Major Transients:
EOPs Entered:
EOP Contingencies:
0 4
1 3
1 (emergency depressurization)
(emergency depressurization)
ILT 01-1 NRC EXAM Scerýi--o ILT-N-2 Page 5 of 21 Au l-nor for-Vai idat on Rev. 00 (02/02)
Operator Actions Op-Test No ILT01-1 Scenario No ILT-N-2 Event No 1
nage 1 of 1
Event Description Maintenance has been completed on TBCCW pump 2B and t'- -_-O directs the ANSO to switch running pumps and place the TBCCW pump service.
Time Position Applicant's Actions or Behavior ANSO Performs the following actions per DOP 3800-01, Turbirt'
ý-ilding Closed Cooling Water System(TBCCW):
Directs NLO to verify 2B TBCCW pump suction s_: discharge valves open.
I Directs NLO to verify 2B TBCCW pump oil levels I
Starts 2B TBCCW pump and verifies proper ope--= 3n.
LI Stops 2A TBCCW pump.
11 Verifies system parameters normal.
- ROLE PLAY:
NLO to verify 2B TBCCW pump suction and discharge v: -es open (wait 1 min):
Report "2B TBCCW pump suction and discharge valves -=-e open".
NLO to verify 2B TBCCW pump oil levels (wait I min):
Report.2B TBCCW pump oil levels are normal".
NLO tb report on operation of 2B TBCCW pump:
Report "2B TBCCW pump is operating normally".
SRO Directs swapping from 2A TBCCW pump to 2B TBCCW :..rmp per DOP 3800-01, Turbine Building Closed Cooling Water System BCCW).
NSO Monitors panels and assists as directed.
Event I Completion Criteria:
2B TBCCW pump running and 2A TBCC.W pump sto::ed.
AND, at the direction of the NRC chief examiner*
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 6 of 21 Rev. 00 (02/02)
A u Th r)
Or "r/a I I j a t i o n Appendix D Form ES-D--
Operator Actions S[ )
Op-TestNo ILT01-1 Sce-No ILT-N-2 Event No 2
Paa of Event Description The NSO, as
- ed by the SRO. then continues the power Fý-,.nsior.
. ýit startup by co -
-od withdrawal.
Time Position Applicant's Actions or Behavior NSO Perforr--
e following actions per DOP 0400-01, React:.- 'anua
- -ntrol Systen- - eration, and DGP 03-04, Control Rod Movem*-:s. as
-ected Verifies -
following prior to moving any control rod:
-ntrol rod selected on the select matrix is corre:- -od.
S:ond Verification requirements satisfied.
J i Out Permit light is illuminated.
e water pressure at nominal 260 psid.
- Withdra,
-ods as follows:
E Y,':yes Rod Out Notch Override (RONOR) Switc, :o NOT2-i
.'ERRIDE position (use of RONOR switch is op-onal) a2: the Rod
':vement Control switch to ROD OUT.
Li e-ifies ON light illuminated and proper Control R:d Time- :peration.
i
- =-'eases switches before target position is reached.
Li
,-:rifies rod settles to target position and proper response - nuclear
-_:rumentation.
ANSO I or Performs _second verification checks.
Surrogate For first -: in a step:
El e-ifies correct control rod pattern Li erifies correct step and array.
Li e'ifies RWM rod blocks enabled For all rc::s moved:
i
=',ifies correct control rod selected.
i erifies planned control rod motion is correct.
Li
-mnediately notify the NSO of errors during rod rrction.
EL '. e-ifies control rod at target position.
SRO Directs p - ing control rods.
EL Feviews REMA.
Li
[esignates second verifier.
EL i
-ects.NSO to pulls rods.
Event 2 Completion Criteria:
Suffi: *nt power increase.,
AN-at the direction of the.NRC chief ekaminer.
ILT 01-1 NRC EXAM, Scenario ILT-',-2 Page 7 of 21 Rev 00 (02/02)
" ro0r f-or Val Idat on Appendix D
Appendix D Op-Test No ILT01-1 Scenario Nc
-N-2 FEvent No 3
Page 1 of 1
Event Description During the control roc,
withdraw limit and mLSc
-rawal, a control rod double notches beyond the repositioned Applicant's Actions or Behavior Two possible p&.
Either: Observe position 14 (1 n:-
1 902-5 B-.
[1 902-5 C-
-an occur:
I-J announces that control rod N-13 has moved to
- 3eyond its target position) and responds to alarms:
Rod Worth Min Block Rod Out Block NSO SRO ANSO Rod returned:: target position AND, at the d -Ection of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-2
- age 8 of 21 Rev. 00 (02/02)
A u t ý
-or Val Idal on Time Position Should perform -- ollowing actions per DOA 0300-12, Mispositioned Control Rod:
11 Discont!-_es rod movement and notifies SRO.
0 Moves t-s mispositioned rod to its target position.
0 Records - DOS-0300-06, Control Rod Abnormality Record.
Or: When obser,-_ rod N-13 moving past its target position of 12, then:
0 Uses the :-ierg Rod In position of the Rod Out Notch Override switch tc -. ve the rod back to its target position prior to it latching in to positic- '4.
El Notifies-SRO.
0 Records - DOS-0300-06, Control Rod Abnormality Record.
May enter and d!-e:: performance of DOA 0300-12, Mispositioned Control Rod.
[]
Notifies t-e Shift Manager.
D May refer - ITS 3.1.3 and determine that no actions are required.
May enter DOA 03 JD-05, Inoperable or Failed Control Rod Drives.
ROLEPLAY:
Respond as the S- :ft Manager.
QNE: If crew requests guida nce from the QNE, respond "I recommend inserting rod N-13 t position*12.
Monitors panels a-.: assists as directed.
Event 3 Completion Criteria:'
÷raýtor !ACtInr] A Form !-%
pe':
D Operator Actions Form ES Op-Test No ILT 01-1
- e. nnafno No ILT-N-2 Event No 4
Page 1 of I
Event Description IRM chann el 12 then fails upscale and a half-scram occurs on the RPS "A" channel The NSO bypasses the failed IRM channel and the SRO addresses the technical specification requirements for the failure.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 1, fails IRM 12 channel upscale NSO Should perform the following actions per DAN 902-5 C-15:
If not in the RUN Mode, verifies the following occurred:
"* Channel A half scram
"* Rod Block.
Verifies IRM 12 readings against other IRMs on 902-5 panel.
Verifies IRM range switch in correct position Bypasses IRM 12 after T. S. compliance verified by SRO.
Resets RPS channel A per DOP 0500-07, Insertion/Reset of Manual Half Scram, as follows:
"* Verifies half scram no longer required
"* Turns the Scram Reset switch in each direction and verifies all eight white group solenoid lights are lit.
Verifies alarm 902-5 A-10, Channel A Manual Trip, resets.
ANSO Should perform the following actions per DAN 902-5 C-10:
F Verifies IRM 12 readings against other IRMs on 902-36 panel.
E Verifies IRM 12 function switch in operate.
Eu Verifies power supplies operating properly.
SRO F., Should references plant technical documents:
"* ITS Table 3.3.1.1.A-1, verifies sufficient RPS IRM trip channels (3 available / 3 required for A channel) for Mode 2.
"* TRM Table T3.3.a-1, verifies sufficient APRM rod block channels available (7 available / 6 required) for Mode 2.
E Should direct IRM 12 bypassed and the half scram reset per DOP 0500-07, Insertion/Reset of Manual Half Scram.
E Notifies the Shift Manager and [MD..
Role Play:
Respond as persons notified.".
Event 4 Completion Criteria:,
IRM 12 bypassed.
Half scram reset.
AND, at the direction of the NRC chief examiner.
iLT 01-1 NRC EXAM, Scenario ILT-N-2 Page 9 of 21 Rev. 00 (02 1,2)
Author for Va idation
Operator Acti Op-Test No LT 01-1 Scenario No,: ILT-N-2 Event
Description:
Drywell to Torus differential pressure t!
is regained when the ANSO takes mar pressure controller.
Time Position Applicant ANSO SRO NSO SIMULATOR OPERATOR-At the discretion of the NRC chie: e drywell to torus differential press' demand to fail to 0%.
Acknowledges and announces a _:
and performs the following:
.-ent No 5
Page 1 of 1
gins to decrease and pressure control uDntrol of the Drywell to Torus differential
.ons or Behavior sminer, activate trigger 2, which causes
- r.iner, activate trigger 2, which causes
- ontroller input to fail high causing the
- 902-4 B-15, DWto Torus DP Hi/Lo, F) Should diagnose failure c' -_ drywell to torus differential pressure controller AUTO mode of :-:eration.
Performs any of the following as c ÷.cted:
LI Places the drywell to torus - iferential pressure controller to MAN and controls the drywell t: :-us differential pressure manually; LI AND / OR, vents the torus - Reactor Building Ventilation per DOP 1600-01, Normal Pressure _" ntrol of the Drywell or Torus:
"* Verifies atmospheric s- -,ple results allow venting.
Verifies U2 Reactor B_ :ing Ventilation operating.
"* VerifiesAO 2-1601-9' ::)en.
"* Opens AO 2-1601-24
- oses when desired to stop venting)
"* Opens AO 2-1601-61
- oses when desired to stop venting)
DOP 1600-05, Primary Containment Inerting and Atmosphere C : -itrol.
To maintain Primary Containment : -essures to those specified in DOP 1600 05, Primary Containment Inerting F-: Atmosphere Control, should direct performance of any of the followin:
El Placing the drywell torus c erential pressure controller to MAN and controlling Drywell to ToruL
- ifferential pressure manually; El AND / OR, venting the tor- :o Reactor Building Ventilation per DOP 1600-01, Normal Pressure Dontrol of the Drywell or Torus, to maintain the required diffe-e,-tial pressure.
LI May direct closing AO 2 1-58 per DOP 1600-05, Primary Containment Inerting :and -'- mosphere Control.
El May notify IMD.
Monitors panels and assists as dire_:ed.
ROLE PLAY:
IMD to investigate.drywell pressure :ontrQller:
Respond "I wil Isend a technician "-: vestigate".
Event 5 Completion Criteria:
Drywell to Torus differential pre:-;ure control in progress.
AND, at the direction of the NF - chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 10 of 21 Rev. 00 (02/02 Author-for Val T
T_ 1 o rn I
Appendix [)
Appendix D
[orto I-S-D-2 Op-Test No. IL Event Descrip:
"1 Scenario No I[T-N-2 F
C.ircullating water pump 2C then trips on over : _
circulating water pump 2A to maintain conde.'-*
- <>.1 of I
,e ANSO manual[y starts J m, Applicant's Act. -
-- -aavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examirer. -=:,:vate trigger 3, which trips 2C Circulating Water pump.
Performs the following actions per DAN L_-2-- -'-15, Circ Wtr PP Trip, DOA 4400-01, Circulating Water System FailL,=. F- - DOA 6500-10, 4KV Circuit Breaker Trip, as directed:
N1 Starts 2B Circulating Water pumr: (i- -ediate action)
Nl Verifies condenser vacuum retur-inc 2:
-ormal.
N1 Verifies 2C Circulating Water pu-p c:-,:narge valve closes.
N1 Sends NLO to check 2C Circulat -,g V\\' er pump breaker and operation of 2B Circulating Wate-our'-:
N Places 2C Circulating Water purro cc-raol switch in PTL.
N1 Verifies Circulating Water Flow re.iers., valves lined up normally.
[N May send NLO to check cribhouse be. -acks and traveling screens.
ROLE PLAY:
NLO to 2C Circulating Water pump breaker ("-it 3 min)
Report "2C Circula!ting Water pump breaker has an vPercurrent target up",.
NLO to check 2B CirculatingWater pump operetion (wait 2 min)
Report21 Circulating Water pump is operatin: normafly".
NLO to check cribhouse bar racks and travelin: screens (wait 3 min)
Report "th6ý cribhouse bar racks and traveling z.;-reens are clear".
Enters and directs performance of DOA 4A00--* Circulating Water System Failure, and DOA 6500-10, 4KV Circuit Breake' Trip.
Notifies the Shift Manager and EMD.
RAkI P6iv
Respond as persons, notified, NSO Monitors panels and assists as directed.
Event 6 Completioti Criteria:i 2B Circulating Water pump started.
AND, at the direction of the NRC chief exa-,ner.
ILT 01-1 NRC EX/'.' Scenario ILT-N-2 Page 11 of 21 Rev 00 (02/02)
Author
-For Va ida-SRO Oper-ator Action.
Appef mx DOpo*r 3tot F
"uk fl Op-Test No JIT
-ario No. ILT-N-2 Event No: 7 & 8 Page 1 of 3 Event Descriptio'-
n ECCS
',ion line break occurs resulting in a lowering torus water level HPCI
ýouriousl,, -
iates. HPCI should be secured, the reactor should be scrammed and
.n emerae-:y depressurization should be performed as directed by the DEOP for Drimary c.
7ainment control.
Time Pos -n Applicant's Actions or Behavior SIMULATOR OPERATOR:
At tihe discretion of the NRC chief examiner, activate trigger 4, which starts an ECCS suction line break in the torus basement and spuriously initiates HPC: after 5 minutes.
Whe-the unit is manually scrammed, verify trigger 5 automatically activates to tric 2A EHC Pump.
Note: It takes about 30 minutes for torus level to reach 12 feet. At the discretion of the lead NRC examiner, use the cues later in this event to jump ahead in time to expedite the level drop if desired.
ANSO I
Reports the following alarms:
902-4 C-23 Torus Narrow Range Wtr Lvl Lo 923-4 A-3 U2 E RBFD Sump Lvl Hi Hi 923-4 B-2 U2 W RBFD Sump Lvl Hi Hi Checks the torus narrow range level indicator. Reports level dropping.
Directs NLO to perform DOS 1600-02,Torus Level Verification Using Local Sight Glass.
Directs NLO to investigate leakage to torus basement.
Verifies proper operation of the RBFD Sump pumps. (will require resetting the Group 2 isolation at both the 902-5 panel and the 923-4 panel for the sump pumps to operate if a Group 2 Isolation occurs)
ROLE PLAY:
NLO to perform DOS 1600-02,Torus Level VerificatioU sBing Local Sight" Glass: (wait 5 min)
Report "Local Torus level is (use value from variable ppc232, unless it is
<20", then~resort it is nbelow ethe sightglass)".
NLO to investegat i
leakage (wait 2 min):
.Report "There is',ý large ruptufte from a pipe' attached between the torus shell and the torus suidtion ring header near the East LPCI Corner room. The torus basement floor ii!covered with water". There is no valve on,,the line".
NLO to report LPbI corner status (wait 2 min):
Report " there is no water in either LPCI corner room".
Maintenance to determine if the leak can be stopped (wait 3 min);
Report "Maintenance cannot stop the leak".
ILT 01-1 NRC EXAT, Scenario LT-N-2 Page 12 of 21 Rev. 00 (02/02)
Author for Va idat ion Appendix D Formi ES D-2
Operator Action
[-S-D 2 Op Test No. ILl 01 1 Scenario No ILT N-2 Event No 7&8 F1 -
2 of 3
Event Description An ECCS suction line break occurs resulting in a lowering torus wate spuriously initiates HPCI should be secured, the reactor should be an emergency depressurization should be performed as directed by primary containment control HPCI meed and "EOP for Time Position Applicants Actions or Behavior Aplcat 1-t~onsor ANSO ANSO SRO ANSO NSO Performs the following actions per DEOP 200-01, Primary Cor:
Control, as directed:
IJ May attempt to add water to the torus by opening the -
LI Monitors/Reports DEOP 200-01 entry parameters.
[]
q Prevents HPCI operation by placing the HPCI 4 va ment 14 valve.
SPTL.
Performs the following actions per DOA 0040-02, Localized FI:.: -g in Plant, as directed:
0 Makes PA announcement.
LI Directs NLO to investigate leakage to torus basement 11 Notifies Radiation Protection and Security as time pert Cue: (if desired for time compression)
A,/,/4
/
, 1 When torus level is < 14.5 feet and/or at the discretion of the lea: NRC examiner cue the crew that we are taking a time jump and that ::th torus wide range level meters indicate 12.5 feet and are dropping at -:c
-t 0.1 ft per minute.'
Enters and directs performance of DEOP 0200-01, Primary Cor- : ment Control:
El May attempt to add water to the torus by opening the H:-
14 valve.
DI May decide to anticipate RPV Blowdown:
directs a manual scram per DGP 02-03, Reactor Sc:-Em enters DEOP 100, RPV Control.
a directs opening turbine bypass valves.
E]
Enters DEOP 0300-01, Secondary Containment Control, and di-::s:
LI If Reactor Building Ventilation Isolates when unit is scra--7ed, directs restarting Reactor Building Ventilation.
Performs DEOP 300-01, Secondary Control, as directed:
El Time permitting, restarts Reactor Building Ventilation (if :' solates when the reactor is scrammed).
SPerforms DGP:02-03, Reactor Scram, as directed:
11 Presses scram pushbuttons rJ Places mode switch in shutdown I I Checks rods inserted I
Maintain RPV/L between +25 and +35 inches or as dire :
by DEOPs ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 13 of 21 Rev. 00 (02/02)
AU t oror fof Val daat on Appendix [)
Appendix D
-rm ES D Op-TestNo. ILT-01-1 Scenario No 3/4-'ý2
[-vent No 7&8 Pac÷ 3 of 3 Event Description An ECCS suction line L7,-,
Dccurs resulting in a lowering torus water
.,el. HPCI spuriously initiates. HPC
-uld be secured. the reactor should be scr :-med and an emergency depress; on should be performed as directed by the DEOP for primary containment cot-'
Time Position Applicant's Actions or Behavior ANSO When at-e--::s to open bypass valves (if directed), repc-s that the 2B EHC p--: tripped.
Cue: (if time comp-ession was used above) 10 minutes after the -itial time compression cue and/or at the discretion of the lead NRC exarr -er, cue the crew that both torus wide range revel meters indicate 11.5 feet a-.: are dropping at about 0.1 ft per minute.
SRO When informed thaý ::rus level is approaching 11 feet:
P 1 Directs a manual scram (if not already directed above, per DGP 02-03, Rea::cr Scram.
Enters DEOP 0400--2. Emergency Depressurization, and directs:
0 Initiation o: zo Condenser to maximum flow 0 - Verificatior ::-at SP/L >6 feet.
EP 4!Opening all ADS valves P Verificatior 2 ' relief valves are open.
ANSO Performs DEOP 04-,:-02, Emergency Depressurization, actions as directed:
EP Initiates Isc ýondenser to maximum flow P1 Verifies tha: SP/L >6 feet.
P 4 Opens all ADS valves P Verifies all -aeief valves are open.
Critical Tasks: (identified by.in guide)
.With reacto-at power and.suppression pool water level cannot be maintained the safe region of the heat capacity temperature limit, MANUALLYSCRAM the reactor.
nWhen it is be'ermined that suppression pool.water level cannot be held above '2 feet wide ange (level of HPCI exhaust), TRIPAND PREVENT HPCI operation irrespective of adequate core cooling.
0 When it is d-termined that suppression pool water.level cannot be' held above 11 feet wide range (level of the downcomers), INITIATE emergency iepressurization.
Scenario Corhpletion Criteria:
HPCI secu--,-d.
AND, at the --irection of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-2
- 1/2ge 14 of 21 Rev. 00 2/02)
Author Dr-al idat ion
REFERENCES PR. -- EDURE DAN.
-2 DAN 3- -15 DAN
-' H-17 DAN 9---- A-15
-1TLE Area Temp High DW to Torus DP Hi/Lo Vlv Leak Det Sys Temp Hi Channel B Manual Trip REVISION 06 06 10 04 DAN 6-3 Rod Worth Min Block 06 DAN 9-C-3 Rod Out Block 09 DAN 9-C-15 Channel B IRM Hi Hi/Inop 07 DOP 0Q- -- D1 Reactor Manual Control Syste-Ope-*:,on 16 DOP 05 : --07 Insertion/Reset of Manual HaL' Scrar-02 DOP 1i-: :-01 Normal Pressure Control of the Dryv-or Torus 18 DOP 16 : :-05 Primary Containment Inerting -,d Atr'-,sphere Control 37 DOP 3E- -01 Turbine Building Closed Coolir: Wate-System (TBCCVV) 06 DOS 1E*--02 Torus Level Verification Using _acal S ght Glass.
12 DOA 0 :-05 Inoperable or Failed Control R:d Drr es 20 DOA 6E: :-10 4KV Circuit Breaker Trip 03 DGP 02-: 3 Reactor Scram 54 DGP 03--4 Control Rod Movements 41 DEOP C 00 RPV Control 10 DEOP C>990-01 Primary Containment Control 10 DEOP C.::0-01 Secondary Containment Contro 07 DEOP C- 02 Emergency Depressurization 04 ILT 0"-
NRC EXAM, Scenario ILT-N-2 Page 1; :f 2' Autror Rev. 00 (02/02) da V i on I
i
PRE-SCENARI-ACTIVITIES I
Ifapr: ab÷ :' dLictpre-scnarioactivties in accordance with TO AA-106 0107, SIMULATOR EXAMINATION BRIE-:NG a
Provide-crew with a copy of Control Room work request list.
- b. Povido team with a copy of DGP 01-01, Unit Startup, which is marked Lip to the point of "verifying main turbine
- ass valves open and maintaining pressure at 920 psig"
- c.
Provide team with a copy of DOP 3800-01. Turbine Building Closed Cooling Water System (TBCCW).
- d.
If the cr,-
renquires about a startup plan, inform them the Shift Manager is maintaining it.
- e.
Provide
- crew with a copy of the REMA.
- f.
Inform
- - rew that (select an individual) is the QNE present in the Control Room.
- g.
Inform
- rew that an IM technician is on site to adjust gains.
- h.
Direct t-
_rew to perform their briefs prior to entering the simulator.
- 2.
Simulator So:_
(the following steps can be done in any logical order)\\
- a.
Initialize s -iulator in IC 7 and perform the following before moving continuing below:,/
- 1) Use -e Rodmove program to pull rods through step 34. <
- 15) 5 jý -
t CoI "t__*r4, L
-Yt Vert-2A Stator Cooling Water and 2A EHC Pumps running.
FCY 20*
- J),,
) Ado -e following variables to a Monitor program screen and change the fifst-twa as necessary to obtain a DW :-essure of -1.1 psig and torus pressure of -0.0 psig:
a) :,cmndw(1) b)
- ,cmnww(1)
- b. Run the tial setup caep file: ilt-n-2.cae.
Verify the Drimary Containment controllers are in AUTO and controlling in the normal at power pressures.
- d.
Verify the :ollowing simulator conditions:
- 2) Con:ensate Demin dP between 20 and 45 psid.
- 3)
Con:e=nsate pump amps between 160 and 255 amps.
- 4) Ope-AO 2-1601-58.
- 5) Veri.-, 2A TBCCW pump running and 2B off.
- 6) Veri6. backpanel lights reset.
- d.
Secure :-e following equipment and tag out of service:
- 1) Place RM 16 902-5 panel joystick in bypass and place -an Equipment Status Tag on it.
- e.
Add var,.*:§e ppc232 to a Monitor program screen.
- f.
Advance -. e chart recorders.
- g.
Mark up -:d sequence as completed through step 34.
-. Po h.._TM
~i th ppor i*te book.
- i.
Comple-e *ne Simulator Setup Checklist.
ILT 01-1 NRC E,.- M, Scenario ILT-N-2 Page 16 of 21 Rev. 00 (02/02)
AutO0r f&)r Va I
dat i on
Computer Aided Exercise Progr-ams ILT 01-1 NRC EXAM SCENARIO ILT-N-2 Initial Setup CAEP:
- itt-n 2cae
- Setup for lt-n-2
- Written by JAS
- Rev 00
- Date 02/02
- INITIAL CONDITIONS
- overrides IC rad mon downscale alarm off imf ser0004 off imf serOO19 off
- opens the N2 makeup inlet isolation.
irf p33 true
- lowers the isolation condenser temperatures.
set ich2la = 50.0 set ich2lb = 50.0 set ichshell = 50.0
- SETUP EVENT TRIGGERS
- Event Trigger 1 IRM 12 channel fails upscale trgset 1 "0"12 imf niil2pot (1) 125.012
- Event Trigger 2 drywell to torus DP controller input fails upscale.
trgset 2 "0"12 ior pcpdwtor (2) 3.012
- Event Trigger 3 inserts a 2C circulating water pump trip trgset 3 "0"14 imf hp8 (3)14
- Event Trigger 4 inserts an ECCS suction line break and spuriously initiates HPCI 5 minutes later. HPCI injection is prevented.
trgset 4 "0"12 imf csbrksev (4) 100.014 irf hp8vbkr (4) trippedl4 imf hpinit (4 05:00)14
- Event Trigger 5 trips 2A EHC pump when the reactor is scrammed.
A 0
trgset 5 "rpdmode4.or. rpdmode3"16 PC,
_x4 j
"(-,IJlL I
imf j33 (5)16
~~~~)
- Event Trigger 16 insert rod N-13 drift out malfunction when it is out past position 1 trgset 16 "rdzactls(163) >31.0"16 imf rodnl3do (16)16
- Event Trigger 17 deletes rod N-1 3 drift out malfunction when it is out past positior trgset 17 "rdzactls(163) > 38.0 -or. (rds303em and. rdiselw(163))"16 trg 17 "dmf rodn13do"16
- END ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 17 of 21 Rev. 00 (02/02)
Aut or f(or Va I dat ion I
Date: TODAY Unit 2 Turnover ECCS Status:
All Online Information Shutdowr Information N/AMWe MODE 1 Time to Boil: N/A Online Risk:
Green CDF:
1.00 ShutdovTi Risk: N/A Risk Equipment:
Protected Path: N'A Unit 2 Priorities Station Prorities Continue startup LCORAs LCORA # None Start Title Clock Ends Shift I Activities (X = Completed)
Shift 2 Activities Shift 3 Activities L]
-] Start 2B TBCCW pump El
-Continue startup El Common Unit Activities Shift I Activities (x = Completed)
Shift 2 Activities Shift 3 Activities El
- 1 1:1 Common Unit Procedures / Surveill*-ces in Progress None Unit 2 Conditions, Status, Abnormal-:es 2 hr ago 0500 IRM 16 OC C
due to power supply failure. IMD waitir, for replacement power supply to arrive frorr Ljad Cities Station.
6 hr ago 5650 2B EHC p_-
OOS due to a problem with its pressL-e compeisator. Expected BIS next shift.
Compensatory Actions, Extra Chec-s ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 18 of 21 Rev. 00 (02/02)
- t lotr r-va I j d a t i (on
Equipment OOS 2 hr ago 990045654 6 hr ago 990045652 IRM 16 2B EHC
_.p Service Unit Status 9 days ago 7 days ago 16 days ago 2 days ago 11 days ago 6 days ago 2 days ago 376 days ago 240 days ago 20 days ago 76 days ago 2A Cond Demin 2B Cond Demrin 2C Cond Demio 2D Cond Dernin 2E Cond Dernin 2F Cond Demin 2G Cond Demin 2A RWCU 2B RWCU 2C RWCU U2 FPC Demin Unit 2 Abnormal Component Position U2 Open Operability Determinations with Ccmpensatory Actions Events and Misc. Information DGP 01-01 in progress. Rods pulled jp throuc-step 34. Continue the startup.
Ql'*I
ý a-%-
y.*o(
r 2B TBCCW maintenance complete; swap TBC : N pumps. (start 2B, stop 2A)
DW samples:
Iodine 131 Beta/Gamma ILT 01-1 NRC EXAM, Scenario ILT-N-2
- ge 19 of 21 Rev. 00 (02/02)
- .'C utI for Va I dat Ion Out In Cut In Cut In Cut Out Cut Out Cut Out Cut Out Cut In Cut Out Cut Out Cut In 2.5 X 10'"
1.5 X 10"
Date -ODAY Unit 3 Turnover ECCS Status: All available Online Information Shutdown Information N/A NWe MODE 4 Time to Boil: 24 hrs.
Online Risk:
N/A Shutdown Risk: Green Risk Equipment: N/A Protected Path: None Unit 3 Priorities Station Priorities Corn: ete startup checklists LCORAs LCORA # None Start Title Clock Ends Shift I Activities (X = Completed)
Shift 2 Activities Shift 3 Activities n
n R
Dl ED ED Common Unit Activities Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities M
nIJ ED ED ED Common Unit Procedures / Surveillances in Progress None Unit 3 Conditions, Status, Abnormalities DGP 01-S1, Start-up Checklist, in progress Compensatory Actions, Extra Checks None ILT 0'-1 NRC EXAM, Scenario ILT-N-2 Page 20 of 21 Rev. 00 (02/ 2)
AUtthr-for Va l I dat ron
Equipment OOS None Service Unit Status 5 da a, o
8 da\\,
jo 10 de.
go 5 da,, ý ýJo 3 da\\.
J]o 15 du. -ýigo 3 days -:-o 750 dz.. 5 ago 390 0ý.-z ago 60 da, ago 444 ds. _ ago 3A Cond Detnin 3E3 Cond Den ir 3C Cond Deiin 3D Cond Detain 3E Cond Dentin 3F Cond Detnin 3G Cond Demin 3A RWCU 3B RWCU 3C RWCU U3 FPC Demin Unit 3 Abnormal Component Position None U3 Open Operability Determinations with Compensatory Actions None Events and Misc. Information DGP 01-SI, Start-up Checklist, in progress ILT 01-1 NRC EXAM, Scenario ILT-N-2 Page 21 of 21 Rev. 00 (02 92)
A ut Li a foar V a I i o )n Cit In CuIt In Cut In Cut O)L,:
Cut OLu Cut OLu Cut Out Cut In Cut Out Cut Out Cut In Ii "I
"**'lcýl.\\ for 1)2(
I, >I:irtttp" Iii I) I)
It tilL I I
.I'IIKU'V' \\I lnisiructions/Stcps to Accomplish the EN olution (use FORIls () 111(
), it nece*
Pull rods to criticality, hcatup to iAted pressure. 10(d to I-
-250/o C P.
Limiting Parameters ('X' the applicable limits, if any):
DIFLCPR(OD-20) D*APRAT(,-20)
N))
FDLI, X(OD-20) D[3`1) 1'1 I()-201
- 20)
DCTIP(OD-3 or -9) D-FCL (0[)-76) D]P-I)CS (OD-20) ZOther ir aio-d helooý Comments (indicate range of values and monitoring frequency, if any):
I.
Monitor moderator temperature once per hour during approach Ic critical. Per be less than 240 F when the reactor reaches criticality. Moderato-temperatur new Estimated Critical Position (ECP) calculated by a QNE.
- 2.
Reactor period should not be less than 30 seconds prior to, or upon criticalit\\
- 3.
During the approach to criticality, calculate the reactor period be:ore pullin" SRM count rates.
IP1(0)-20) DM1MFII)I/FRP(0D
\\A-233, inoderator temperature must Uld not fall below 140 F without a
-xt notch upon continuously increasing Other Information:
Upon achieving criticality, calculate the reactor period before pulling :he next notc rates.
Remain within the analyzed rod position sequence by following sequence.0 un Criticality is predicted in the group 3 rods 12-48. Several rods in group 3 are pred-:
24-48, and these rods are noted in the sequence. The QNE will provide a recomm notching each rod between 24-48.
- :th continuously increasing SRM count
.wer> 10%.
Ito have high notch worths between
- ttion on the necessity of single The ECP using sequence.2,.0 with a moderator temperature of 190 F is Step 11, K-
'ýiD
- 36.
ECP with approximately -1% delta Keff: Step 3, J-14 @26.
ECP with approximately +1% delta Keff: Step 11, H-13 @ 32.
Atf The ECP using sequence-2X.0 with a moderator temperature of 140 is step 11, F-I
- 22.
The ECP using sequence 2'X.0 with a moderator temperature of 240 is step I1, H : 16.
The analyzed rod position sequence must be followed until achieving :0% of Ratec 7'termal Power for RDA concerns. The analyzed rod position sequence allows up to 8 rods OOS. Rods are on!v considerec OS for the purposes of the analyzed rod position sequence if they are unmovable AND they are not at the target position.
will provide assistance in ensuring compliance with the analyzed rod position sequence.
ce above 100 CTP, the adherence to analyzed rod position sequence is not reqi -:
10% CTP is -2.1 IBP above 10% CTP, out e-e Instructions to rapidly proceed through start up and scr nd occur. The react 'r must be b ht to mode I prior,to scram time test~n prevent themode2 APRM rod blocks and scram fo in e-AU thi)or fOr Va j
t S
( t\\ CI c I S Prepared by.
4W.5 4upReviewed by:
-/oved b P)AR I II I
-RI ' A(.'I1IV I -IN M A Nt I x
Dresden Generating Station SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-3 0
Rev. 00 02/02 DEVELOPED BY APPROVED BY Exar-Authe*
Fac' i*epresentative SimScer ý-,io-ILT-N-3.doc Date Date Master Copy
ScA- -
- Outhne Facility Dresden
- cenar Examiners:
ILT-N-3 Op-Test No ILT 01-1 Operators:
Initial Conditions: Approximately 78% reac::- oower, IRM channel 16 out of service, 2B EHC Pump out of service; Unit 3 is in Mode 4.
Turnover:
Unit shutdown in progress for f :ed outage; shutdown reactor condensate pump 2B, then continue power reduction for unit S-tdown Event Malf.
Event Event No.
No.
Type*
Description 1
N/A N
ANSO sh'-.:wn condensate pump for unit shutdown SRO 2
N/A R
NSO lovw-reactor power by reducing recirculation flow SRO 3
SER1375 NSO reeeB FWDOP2 SRO r feed pump 2B failure FWDOP5 4 AD3ESDANSO ADS3ESD SRO spy" ous ADS valve opening K11 C
ANSO sta::- cooling water pump trips on overload and MGDSCBTR SRO sta- :by pump fails to start automatically 6
RLLMLS I
NSO fee--vater level control system setpoint drifts high SRO 7
F44 ALL sm.= recirculation loop break M
8 ACDTP21 ANSO TR 22 feed to Bus 21 fails to close ACDCL21 SRO HP8VBKR ANSO HP.
injection valve failure HPLCL8 SRO
- ~~~~
INoml IReciiy lntuet (C, mponent, (M)ajor NUREG-1021, Revision 8, Supplement 1 Auteior
ý I vaiidation Page 2 oi -
Appendix D Form ES-D-!
- (N)ormal, (R)eactivity, (I)nstrument,
Dresden Generating Station NRC ILT EXAM Scenario ILT-N-3 Scenario Objective Evaluate th- :.erators in using the Emergency Depressurization DEOP contingency procedure.
Scenario Summary Initial Condit -- s
-80% pc,',er.
IRM 16 C3S.
2B EHC P-mp OOS Ready to secure a Condensate Pump.
Unit 3 is i-Mode 4 Events:
"* Shutdowr 2B Condensate Pump
"* Power recJction with recirculation flow
"* 2B RFP Failure
"* E ADSV setpoint drifts low
"* 2A stator water cooling pump trips 9
Failure of FWLC auto mode Recirculat:on loop leak with loss of high pressure feed.
Scenario Sequence
"* The team continues the shut down by securing 2B condensate pump.
"* Next the team reduces power using recirculation flow.
"* A 2B RFP low lube oil condition will require the team to start 2C RFP and secure 2B RFP.
"* The E ADSV setpoint will drift low causing it to open. The team should close it by placing its contro _wvitch in OFF. The SRO will address Technical Specification requirements.
"* The 2A stator cooling water pump trips on overload and the standby pump fails to start automatical., The team should manually start the 2B stator cooling water pump.
"* The FWLC system setpoint will begin drifting up. The team should take manual control of the FWLC z!stem.
"* A small recirculation loop break occurs causing a reactor scram and high drywell pressure. During generator trip, Bus 21 will fail to transfer to TR 22 and the 2C RFP Bus 22 breaker will rot close res_ :ng in a total loss of high pressure feedwater. The HPCI injection valve fails to open. The team should perfco-the RPV Control and Primary Containment Control DEOPs.Due to the loss of high pressure injection a-,: RPV level dropsing to TAF, the team should Emergency Depressurize and restore RPV leve with low pres sure injection s/stems.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 3 of 24 Rev
,2/02)
AUt CO0 for Va Idation
Event Two - Power Reduction With Recir ulation Fio,,.
The crew reduces power with recirculation -:v per pro÷- es.
Malfunctions required: 0 Success Path 0
Reduces power with recirculation flow pe-procedur-e Event Three - 2B RFP Failure The crew recognizes and responds to failure Df the 2B RF: ube oil system.
Malfunctions required: 2 (Low Lube Oil Pressure)
(Failure of aux oil :,_rap to start Success Path:
Starts 2C RFP and secures 2B RFP Event Four - E ADSV Setpoint Drifts Low The crew recognizes and responds to E ADS/ setpoint dc fing low causing the valve to open.
Malfunctions required: 1 (E ADSV setpoint o-ft)
Success Path:
Places the E ADSV control switch to OFF Event Five - 2A Stator Water Cooling Pump Trips The crew recognizes and responds to trip of ZA stator wate cooling pump and failure of 2B stator water cooling pump to automatically start.
Malfunctions required: 1 (loss of stator water cooling)
Success Path:
Manually start 2B stator water cooling pump.
C-Vedb-C--~~rd
-3 i4 ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 4 24 Au I f
r
-1 idation Rev 00 (02/02)
Event Six - FailL-÷ of FWLC Auto Mode The crew recogv-and responds to failure of the automatic mode of the FV, Malfunctions req-1 (FWLC setpoint drift)
Success Path 0
Takes manua
-itrol of the FWLC system.
stem Event Seven and Eight-Recirculation Loop Leak With Loss Of High Press_-e Feed The crew recognio z and responds to a recirculation loop leak with a loss of hic- *-essure injection systems.
Malfunctions reqct -e: 3 (recirculation loop leak)
(loss of RFPs)
(HPCI injection valve failure)
Success Path:
Emergency De:-essurize Use low press-e injection systems to restore RPV level.
Scenario Recapitulation Total Malfunctions Abnormal Events:
Major Transients:
EOPs Entered:
EOP Contingencies 8
4 1
2 1
(emergency depressurization)
(emergency depressurization)
ILT 01-1 NRC EX!-' Scenario ILT.N-3 Page 5 of 24 Autnhor for Va I idat on Rev. 00 (02/02)
Append ix D Forn1
[ S-D Op Test No iLT 01-1 Event Descript on: The tean-rino No ILT-N 3 Event No 1
- nues the shut down by securing 2B Condensate Pu Page 1 of 1 mnp Time Event I Completion Criteria:
H
.Cond.ensate Pmp secured.
AND, at the direction of the NRC chief examiner, ILT 01-1 NRC EXAM, Scenario 1_--N-3 Page 6 of 24 Rev. 00 (02/02)
-.u nror for Va I I dat on Position SRO ANSO NSO Applicant's Actions or Behavior Dire:- ANSO to secure 2B Condensate Pump per DOP 3300-03, Con:- sate System Shutdown.
Per': -'s the following actions per DOP 3300-03, Condensate System Shu:- :.vn, to shutdown 2B Condensate Pump as directed:
Verifies Reactor Feed Pump Suction Pressure >230 psig.
Verifies closed the hydrogen isolation valves. (on turnover)
Stops 2B Condensate Pump Selects 2B Condensate Pump for standby.
Directs NLO to verify Condensate Pre-filter operating parameters.
Mon ::-s panels and assists as directed.
ROLE PLAY:
NLO:: verify 2B Condensate Pump hydrogen isolation valves closed:
Repor hydrogen isolation valves are closed".
NLO *: verify 2B Condensate Pump stopped rotating:
Repo-: '2B Condensate Pump has stopped rotating".
NLO t: verify Condensate Pre-filter operating parameters (wait 2 mini):
Reporý Condensate Pre-filter operating parameters are normal."
Operator Actions Z-- b, R, V f,,
Appendix D Form ES D 2 Op-Test No ILT 1 1 Scenario No: ILT-N-3 E. --t No Page 1 of I
Event Description The team reduces power using recirculatior -.
Time Position Applicant's Ac*.:,-s or Behav NSO Performs the following actions per DC-D2-01 Unit
-- down, and DOP 0202-03, Reactor Recirculation Flow C.: trol Systen-- ieration LI Lowers recirculation pump spý_.J using the r-*
er controller potentiometer.
LU Verifies expected power reduc-,n.
SRO Directs reducing reactor power per DG: 02-01, Unit
- Jtdown, and DOP 0202-03, Reactor Recirculation Flow C:rtrol System _- zeration, by lowering recirculation pump speed.
ANSO Monitors panels and assists as directe:
Event 2 Completion Criteria:
Significant power reduction AND, at the direction of the NRC chef examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 7 of 24 Rev. 00 (02/02)
Aitnor for Val Ida-
_n Operator f cto
Operato Actio )s Op Test No ILT 01-Scu -
',3 ILT-N-3 Event No 3
Page I
Event Description A 23 RFP Iow
-I condition will require the team to start 2C RFP and sec.
RFP.
Time Positior Applicant's Actions or Behavior SIMULATR OPERATOR:
At the dis:-::on of the NRC chief examiner, activate trigger 1, which ins_-
2B RFP I,.
Dil pressure and causes failure of its auxiliary oil pump to st:
NSO Per-forms -
following actions per DAN 902-6 H-8, 2B RFP Brg Oil Pres
--pts to start 2B RFP Auxiliary Oil Pump.
E -:,s NLO to report 2B RFP oil pressure, oil reservoir level an:
c-z: < for oil leaks.
1 -'--ms SRO 2B RFP is running with low oil pressure and the a-: ary oil pump will not start.
ROLE PLAY:
NLO to cherk 2B RFP (wait 2 min):
Report "2E RFP oil pressure is 16 psig. Oil reservoir level is low. There is large amo,.-,t of oil on the pump base-plate The oil had not reached the b=ze plate drair yet. I plugged the base plate drain".
NLO to che:k 2B RFP Aux Oil pump breaker: (wait 2 mir))
Report "I sEe no problems with 2B RFP Aux Oil pump breaker".
SRO Directs st:--::7g 2C RFP and securing 2B RFP.
Contacts t-- Shift Manager, and appropriate maintenance departments.
ANSO Monitors p._-els and assists as directed.
NSO Starts 2C - 7P per DOP 3200-03, Startup of second Reactor Feed Pump Shifting to -.:ernate Reactor Feed Pump, as directed:
SM_>, direct NLO to perform pre-startup checks.
l Pe:es RFPs Standby selector switch in OFF.
C Ci:.es the discharge valve.
C O:e.ý-sthe recirculation valve.
C Ve-es, RPV level stable.
C S::--s discharge valve opening.
SS:-:-s the RFP. (should start it on Bus 22 per procedure)
- es RPV level stable.
C C : -es. the recirculation valve.
I D --_*s NLO to perform post-startup checks.
E Vev - es auxiliary oil pump stops.
ILT 01-1 NRC EXAM, Scenario iLT-l`,-!
Page 8 of 24 Rev. 00 (C 2) or for Val idat ion Appendix D)
Ar,nornAl n
uperator-Form LS [- *2 Op-Test No ILT 01 1 Scenario No ILT-N-3 Event No.
3 Page 2
of 3 Event Description A 2B RFP low lube oil condition w*,
"e the team to start another RFP and secure 2B RFP Time Position Applic*o- -
Actions or Behavior ROLE PLAY:
NLO to perform RFP pre-startL: :hecks (wait 5 min):
Respond "I have completed the --quested RFP startup pre-checks per step G.1 through G.11 of DOP 320:1-- 3".
NLO to perform post-startup cI-.:<s: (wait 5 min)
Respond "The RFP post-startu: :hecks are completed per G.31 of DOP 3200-03".
NSO Performs the following actions :,
DOP 3200-05, Reactor Feed Pump Shutdown, to shutdown 2B RF,- :s directed:
U Verifies zinc injection it -:)t lined up to 2B RFP (may not wait on this).
[]
Places RFPs standby s-e ector switch to OFF.
0
-Opens the recirculatior,alve.
U Verifies RPV level stab e I
Closes the discharge v
- e.
0 Verifies RPV level stab LI Stops the RFP.
LI Verifies the running RF-amps below 1115 amps.
O Closes the recirculatior,alve.
,I Has NLO verify the RFE -as come to rest.
0I Has NLO adjust zinc in.'ection to -20 gpm.
0 Has NLO verify 2-5772-3B closed.
ROLE PLAY; NLO to verify lineup of zinc i.-je-on (wait 1 mi):
Resppnd "Zinc injection is lined _p to 2A RFP".
NLO to verify 2B RFP has come to rest (wait 1 min):
Respond "21 RFP has stopped -stating".
NLO to verify 28 RFP is not rotd_:lg in reverse direction:
Respond "28 RFP isthot rotatin: n reverse direction'.
NLO to adjust zinc injection to -_2] gpm (wait 2 min):,
Respond "I adjusted zinc inject a-to -20 gpm".
NLO to verify 2-5772-48B close: (wait 1 min):
Respond "5772-48B is closed".
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 9 -, 24 Rev. 00 (02/02)
Author for
\\8 IJa a T i or)
Operator Actions
- S [)
1 -1 Scenario No IL]-N-3 Lvent No 3
Page I)f 3
Event Descr secure 2B R-A 2B RFP low lube oil condition will require the team to start another RFP -- -
Applicant's Actions or Behavior Event 3 Completion Criteria:
2C RFP started 2B RFP shutdown AND, at the direction of the NRC chief examiner 0
ILT 01-1 NRC E,.AM, Scenario ILT-N-3 Page 10of 24 Rev. r,: 02/02)
A(thor for-Va I idat o r Op-Test N(
-i~ppendix D
Operate -.
otiom-Op-Test No ILT01-1 Scenario No ILT-N---
.ent No 4
Page 1 of 1
Event Description The E ADSV setpoint will driftlc,,, causir -
Dopen. The team should close it by placing its control switch in OFF Time Position Ap: icant's - - ons or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief e: _="niner, activate trigger 2, which sets the E ADS valve's setpoint to 890 psig.ising it to open.
ANSO Performs the following actrns per -N 902-3 E-12, 2E Electromatic Relief Vlv Open:
0 Verifies valve act-elly ope-checking any of the following:
"* Valve positior ndicatic
"* Generator outcut decrý_ _=e.
0 Acoustic monw:.r trippe:
"* Increasing tailcipe tem-:.-:-ature.
"* Torus temperature ince.E sing l
Notifies SRO the \\alve is c:.*
SRO Enters and directs performance of - --A 0250-01, Relief Valve Failure.
ANSO Performs DOA 0250-01, Relief Val\\ - -ailure, as directed:
0 Places the 2E Electromatic - lief valve control switch to OFF.
(immediate action; 0
Verifies RPV level stable. (,-mediate action) 0 Verifies and reports the val, e closed.
0 Resets the acoustc monito SRO References Technical Specifications and determines:
0 ITS 3.6.2.1, Suppression P:,: Average Temperature, is not applicable.
0 ITS 3.5.1.G, ECCS. if decioe:_= the failure does affect its ADS function, then restcre the A, B valve to OPERABLE status within 14 days, otherwise, th's is not a:olicable.
E ITS 3.4.3.A, Safety and Rele Valves, restore the relief valve to OPERABLE status within 1lz :ays.
0 ITS SR:3.6.1.8.2, Suppress.:.- Chamber to Dry~vell Vacuum Breakers,: perform a functio-test.of each required vacuum breaker within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Event 4 Completion Criteria:
2E Electronatic Relief valve clos.ed.
Referenced Technical Specifica:-:ns.
AND, at thedfrection of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Pace 11 of 2' Rev. 00 (02/02)
Author for on Appendix D Form L*S-D-2
Operatot,Actiofs Form ES-D-2 Op-T-- No ILT --
Scenario No ILT-N-3 Event No 5
Page 1 of 1 Evenr
-escriptio'* -- e 2A stator cooling water pump trips on overload and the s.:_ oby pump fails to startl _omatica, -- e team should manually start the 2B stator cooling water.
TiTm Posý:
Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate tr:: -r 3, which causes 2A stator cooling water pump to trip on overload and 2E fails to auto start.
ANSO Announces the following alarms:
DAN 902-7 B-10, Stator CIg PP Trip DAN 902-7 C-3, Turb Stator Coolant Runback Performs appropriate actions per DOA 7400-01, Failure :' the Stator Coolant System:
0 Starts 2B Stator Cooling Water Pump (lmmedia-e Action)
J Verifies Runback condition clears.
]
Sends NLO to verify 2B Stator Cooling Water P_--p operating normally.
Performs appropriate actions per DOA 6700-06, 480V C -:uit Breaker Trip:
LI Sends NLO to check breaker and 2A Stator Coc
'g Water Pump for cause of trip.
LI Places 2A Stator Cooling Water Pump control s, :ch in PTL.
SIMULAT~OR OPERATOR / ROLE PLAY:
NLO t acknowledge stator cooling water trouble alarm: iw.vait 2 mi)*
Activate
,trigger 9 anreport "I have ackno&l.ed ed stator cooling water trouble allarm. The alarms were Inlet Pressufre Low and Trbine'Run back".
NLO,o check operation of 2B Stator Cooling Water Pums: (wait,2min)
Report `2B Stator CooIlig Water Pump is operating norma-Rlly NLO to check cause of 2A Stator Cooling Water Pump t,,": (wait 2 min)
Report "~2A StatorCooling Water Pump trip on overload".
SRO Enters and directs performance of DOA 7400-01, Failure If the Stator Coolant System.
Enters and directs performance of DOA 6700-06, 480V C.-uit Breaker Trip.
Notifies Work Week Manager, IMD and/or EMD NSO Monitors panels and assists as directed.
ROLE PLAY:
Respond to calls for assistance.
Event 5 Completion Criteria:
2B Stator Cooling Water Pump started AND, at the direction of the NRC chief examiner.
ILT 01 -1 'ARC EXAM, -:enario ILT-N-3 Page 12 of 24 Rev. 00 (02/02)
Author For Va I dat on Appe'- -
- D
Operator Actomn[
Op-Test No ILT 01-1 Scenai ILT-N-3 Event No 6
Page 1 of 1 Event Description. The FWLC syste control of the FWLC svstem ooint will begin drifting up The team should take manual Appolicant's Actions or Behavior SIMULATO-OPERATOR:
At the discra_
-n of the NRC chief examiner, activate trigger 7, which causes feedwater l. e control system setpoint to drift high (to 60") over 10 min.
Observes a-announces RPV level rising or responds to alarm 902-5 E-8, RPV Lvl Hi Performs th
-: lowing actions per DOA 0600-01 Transient Level Control:
ZTake-manual control of the Feedwater Regulating Valves.
g Res: -as level to within band specified by the SRO Enters and : -acts performance of DOA 0600-01 Transient Level Control.
Notifies Shit Yanager and IMD.
ROLE PLAY.
Respond to ca.!s for assistance.
Cue:
IfANSO goes to check OIS screen, prompt him that the OIS Monitor is blank.
Monitors pa-a s and assists as directed.
Event 6 Corr oletion Criteria:
Feedwa',- level control system under manual control.
AND, at 7e direction of the NRC chief examiner.
~tK~AV/c V.2
);U1 1 ILT 01-1 NRC EXAM, Scenario ILT-N-i Page 13of24 Rev. 00 (02/02)
A _--
_r for Val dat on Time Position NSO SRO ANSO Applicant's Actions or Behavior Appendix D Foim I-S.D-2
ý A __ýj
Appendix D
%ES
[l2 Op-TestNo ILT01 1 Scenario No ILT-N-3 Event No 7 8;,
of 3 Event Description A small recirculation loop break occurs with a loss of high p ssure irn ':
The team should perform the RPV Control and Primary Containment Control DEOPý Due to-
--ssof high pressure injection and RPV level dropping to TAF, the team should Emercency Dep- - -..rize and restore RPV level with low pressure injection systems Time Position Applicant's Actions or Behavic SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 8, c- - _es a 2%
recirc loop leak and failure of the HPCI 8 vlv to open.
NSO Announces Reactor Scram on high Drywell pressure.
Performs the following actions per DGP 02-03, Reactc-Scram, 2- : DEOP 100, RPV Control, as directed:
[3 Places Mode Switch to Shutdown and depresses the Sc-i-niv hhi ffnnc ANSO SRO O Checks rods inserted.
O Maintains RPV level as directed by SRO.
El Checks turbine and generator tripped.
1 Checks recirc pumps run back to minimum speed.
El Inserts SRMs and IRMs Should inform the SRO that High Pressure Feedwater and HPCI -
not available.
Enters DEOP 100, RPV Control, due to high PC/P and/or low RP',
and performs/directs:
El Entering DGP 2-3
[3 Verification of water level instrument accuracy E] Verification of all isolations, ECCS and EDGs s:arts
[3 Holding RPV/L +8 to +48 inches 13 Maintaining RPV/P <1060 psig When informed no high pressure feed is available other than CRE, :n.en directs:
El Inhibiting ADS before -59 inches.
0 Initiating thie isolation condenser
[I Directina use of hiah nressure Alftcrnnfrt Inin,-,fin, f
,,-)-,,-
El El El
- 'r-*sj I,~3/.*L~illI 3[-L.,
and CRD Crosstie)
Verifies at least two low pressure injection systems availa:-!
Waits until RPV level drops to TAF.
Verifies any low pressure system lined up with a pump ru- - -g SIMULATOR OPERATOR / ROLE PLAY:
NLO to lineup CRD crosstie (wait 5 min.):
Verify trigger 10 is activated then report "the CRD crosste is lined ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 14 of 24 Re,
-'0 (02/02)
Autnor For Va I idati on Operator Action!
Appendix D Op Test No ILT 01 1 Scenar - Ný Event Description A small recircul team should perform the RPV Connv high pressure injection and RPV leve restore RPV level with low pressure
'-3
-10C nd P jropr ect:o*
Event No 4
8&,
Page 2
of 3
--ak occurs with a loss of high pressure injection. The
--3ry Containment Control DEOPs. Due to the loss of to TAF,-the team should Emergency Depressurize and stems.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR I ROLE PLAY:
NLO to line-p make - to SBLC Boron tank (wait 5 min.):
Verify trigger 11 is E::ivated then report "makeup is lined up to SBLC Boron tank".
Before RP\\, evel re-- :hes -164 inches, enters DEOP 400-02, Emergency Depressunr-3tion, a-directs:
]
Ini-.=tion of s: Condenser to maximum flow L Ve-ýcatior :-at SP/L >6 feet.
O '1Opening all ADS valves I
Ve--9catior :: I relief valves are open Performs DEOP 40--02, Emergency Depressurization, as directed:
I Preients ir. ection from LPCI/CS pumps not needed for core cooling per Hard Ca -J, LPCl INJ/CC CONTROL/SHUTDOWN L]
Init~ates Isc.ondenser to maximum flow per Hard Card, ISOLATION CONDENSER E] Ver-ýes SP - >6 feet LI 4 Opens all ADS valves L]
Ver-tes all re ief valves are open q Directs NSO/ANSO to control RPV level above TAF using any of the preferred in.ection s. stems listed below:
Condersate Core Spray LPCI 4 Restores RPV level to that'directed by the SRO (above TAF) using the systems spec-ified..b, the SRO..
ILT 01-1 NRC EXAM, Scenario ILT-N-!
Page 15 of 24 Rev. 00 (02/02)
Aý,-
" 2
'r VaI idatior SRO ANSO SRO NSO/
ANSO 2trActions Form [-S-D 2
tForm ES-D-2 Op--
z:No: ILT.01-1 Scenario No.
ILT-N-3
'tNo 7 8&39 Page 3 of.3 Eve
==
Description:==
A small recirculation loop break occurs v. "
5ss of high pressure injection The tearz-
-uld perform the RPV Control and Primary Contain,
-- ontrol DEOPs Due to the loss of higi-
--ssure injection and RPV level dropping to TAF, the should Emergency Depressurize and rest-- -
PV level with low pressure injection systems
-- J Position Applicant's "- ::-s or Behavior SRO Enters DEOP 200-1, Primary Con,_--.nt Control, when PC/P reaches 2 psig and performs/directs:
U Monitoring of PC/P U
Initiation of torus sprays be:-: PC/P of 9 psig I]
When PC/P is above 9 psi-: - efore DW/T reaches 281 'F
"* Verification of DSIL
"* Tripping of recirc pump.
"* Tripping of DW coolers
"* Initiation of DW sprays U
Monitoring of DW/T (drywe
-ays may be initiated for temperature control)
U Monitoring of SP/T and init: : 7 of torus cooling 0
Monitors SP/L U Verifies initiation of drywell
-- torus H2/O2 monitors ANSO Performs DEOP 200-1, Primary Co--: iment Control, actions as directed:
U Monitors PC/P and initiates
-.-s sprays and drywell sprays per Hard Card LPCI/CCSW OPERAT
, as directed U Monitors DW/T U Monitors SP/T and initiates -.
- -s cooling per Hard Card LPCI/CCSW OPERATION as directed U Monitors SPIL U Verifies initiation of drywell 2-.: torus H2/0 2 monitors ROLE PLAY:
NLO to check EDG operation (wait'
-7in)
Report "Both EDGs are operating nc-ally" Critical Tasks: (identified by '
in.q de)
[U With Reactor pressure grea*-e-Than shutoff head of the low pressure systems and when RPV wa:-- evel reaches TAF, INITIATE emergency depressurizatior- :efore level reaches Minimum Zero Injection RPV Water Level.
1J Action is taken to restore RF.,vater level above TAF by OPERATING available low '-÷ssure systems, when RPV pressure decreases below the shutoff -- ad of low pressure systems.
Scenario Completion Criteria:
Performed Emergency Depress_-:ation Restored RPV level above TAF AND, at the direction of the NRC :-ief examiner.
ILT 01-N RC EXAM, Scenario ILT-N-3 Page 16 of 2-,
Rev. 00 (02/02)
Autnor
+Or-Val on Ooerator,A\\h(
REFERENCES PROCEDURE DAN 902-5 E-8 RPV Lvl Hi DAN 902-6 H-8 2B RFP Brg Oil Press Lo DAN 902-7 B-10 Stator CIg PP Trip DAN 902-7 C-3 TITLE urb Stator Coolant Runback DOP 3200-03 Startup of second Reactor Feed Pump or Shifting to Alternate Reactor Feed Pump DOP 0202-03 Reactor Recirculation Flow Control System Operation 20 DOP 3200-05 Reactor Feed Pump Shutdown 20 DOP 3300-03 Sondensate System Shutdown 20 DOA 0250-01 Relief Valve Failure 21 DOA 6700-06 480V Circuit Breaker Trip 08 DOA 7400-01 Failure of the Stator Coolant System 14 DGP 02-01 Unit Shutdown 65 DGP 02-03 Reactor Scram 54 DGP 03-01 Routine Power Changes 40 DEOP 0100 Reactor Control 10 DEOP 0200-01 Primary Containment Control 10 DEOP 0400-02 Emergency Depressurization 04 DEOP 0500-02 Bypassing Interlocks and Isolations 10 DEOP 0500-03 Alternate Water Injection Systems 12 ILT 01-1 NRC EXAM Scenario ILT-N-3 Page 17 of 24 At*t0or for Va I I dat I on Rev. 00 (02/02) 32 REVISION 00 02 04 09
PRE-SCENARIO ACTIVITIES 1
If applicable, conduct pre-scenario activities in accordance with TI "A-1 107, SIMULATOR EXAMINATION BRIEFING a
Provide the crew with a copy of Control Room work request
- b.
Provide the team with a copy of DGP 02-01 Unit Shutdown,
- h ns i
-<ed up to the point of taking off the fourth condensate pump
- c.
Provide the team with a copy of DOP 3300-03, Condensate S, -em S-.-Jown.
- d.
Inform the crew that an IM technician is on site to adjust gains
- e.
Direct the crew to perform their briefs prior to entering the sim-._-or
- 2.
Simulator Setup (the following steps can be done in any logical or
- a.
Initialize simulator in IC 12 and perform the following before com: -. !ng be :,v 11 Reduce recirculation pump speed to just below the exclusio- -3nge. _4 6'
- 2) Verify feed water flow <9.0 Mlbm/hr; if not, reduce recirculat,:- pump _*til it is.
- 3) Shutdown 2C RFP and place it in standby on Bus 22.
ve'ýij' Y
p 5
/
- b.
Run the initial setup caep file: ilt-n-3.cae.
PC-V vL "4
/
- c.
Verify the following simulator conditions:
- 1) Master Recirc Flow controller at/65%
reCPC
-5pee4 C
- 2) MWe at-.1 -;-7Žý
- 3)
Condensate Demin dP between 20 and 45 psid [EPU]
- 4) Condensate pump amps between 160 and 255 amps [EPL'
- d.
Secure the following equipment and tag out of service:
- 1) Place IRM 16 902-5 panel joystick in bypass and place an Equipme-: Status Tag on it.
- e.
Advance the chart recorders.
- f.
Mark up rod sequence as completed through step 130.
- h. Complete the Simulator Setup Checklist.
ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 18 of 24 Rev. 00 (02/02)
Au t nor-For Vai i dat
omp terAided Exeicise "
grai ILT 01-1 NRC EXAM SCENARIO ILT-',-3 Initial Setup CAEP:
- ilt-n-3 cae
- Setup for It-n-3
- Written by JAS
- Rev 00
- Date 02/02
- INITIAL CONDITIONS
- Prevents TR 22 feed to E -
21 fror- :sing in ior acdtp2l trip ior acdcl2l off
- overrides 2B stator cooliri water p:-: auto trip light off.
ior mglscbat off
- SETUP EVENT TRIGGERS
- Event Trigger 1 Insert 2B RFP low c :ressure and failure of its aux oil pump to start trgset 1 "0" ior fwdop2 (1) off ior fwdop5 (1) trip imf ser1375 (1) on
- Event Trigger 2 Sets the 3E ADS va es setpoint to 890 psig.
trgset 2 "0"11 imf ads3esd (2) 890.012
- Event Trigger 3 2A stator cooling wa:er pump trips on overload and 2B fails to start trgset 3 "0"12 ior mgdscbtr (3) tripi2 imf k1 1 (3 2)12
- Event Trigger 4 when 2B stator cool
- water pump control switch is placed to close, removes
- .*p override.
trgset 4 "mgdscbcl"14 trg 4 "dor mgdscbtr"j4
- Event Trigger 5 when the 2B stator c:oling water pump control switch trip override is deleted =-d the 2A stator cooling water pump is off, sets the 2B s:ator cooling water pump breaker to closed.
trgset 5 ".not. (mgdscbtr.or. mgzsccl('
"14 trg 5 "set mgzsccl(2) = true&4
- Event Trigger 6 when 2B stator cool -] water pump is running, deletes the auto trip light ove- :e.
trgset 6 "mgzsccl(2)"16 trg 6 "dor mglscbat"16
- Event Trigger 7 causes feedwater le =i control system setpoint to drift high (60") over 10 mir trgset 7 "0"16 irf rilmls (7) 60 10:0016
- Event Trigger 8 trips 2C R7P Bus 22 :,eaker, inserts a 0.5% recirc loop leak and failure of tý
-PCI 8 vlv to open.
trgset 8 "0"16 ior fwdrfp8 (8) trip16 ior fwdrfp4 (8) offI6 imf f44 (8) 0.516 ior hplcI8 (8) onf6 ILT 01-1 NRC EXAM, Scenario ILT-N-Page 19 of 24 Rev
- (02/02)
.thor for Val idat ion
irf hpdvbkr (8) )
Event Trigger 9 acknowledges stator cooling.
ouble alarm trgset 9 "0' irf t22 (9) acknowledge Event Trigger 10 lineup CRD crosstie trgset 10 "0" irf rdxtieu3 (10) true Event Trigger 11 lineup makeup to SBLC Boror trgset 11 "0" irf scmumntk (11) true Event Trigger 12 lineup makeup to SBLC Boror -a trgset 12 "0" irf s45 (12) false
- END ILT 01-1 NRC EXAM, Scenario ILT-N-3 Au t
Page 20 of 24
-or V a II Rev. 00 (02/02) da t I or,
Date ---,Y Unit 2 Turnover ECCS S:atus:
All Online -ormation Shutdown Information 715 MV,e [EPU]
MODE 1 Time to Boil: N/A Online = sk: Green CDF:
1.00 Shutdown Risk: N/A Risk Eq_ pment:
Protected Path: N/A Unit 2 P-:orities Station Priorities ContinL-Shutdown LCORAs LCORA # None Start TitLe Clock Ends Shift I A :tivities (X = Completed)
Shift 2 Activities Shift 3 Activities Li DIContinue Unit Shutdown D]
El D]
ED Common Unit Activities Shift 1 Activities (X = Completed)
Shift 2 Activities Shift 3 Activities F
D]
LI El EL El Common Unit Procedures / Surveillances in Progress None Unit 2 Conditions, Status, Abnormalities 2 hr agc 0500 IRM 16 OOS due to power supply failure. IMD waiting for replacement pover supc / to arrive from Quad Cities Station.
6 hr agc 5650 2B EHC pump OOS due to a problem with its pressure compensator. Expec.ted BIS next shift.
Compensatory Actions, Extra Checks ILT 01-
'4RC EXAM, Scenario ILT-N-3 Page 21 of 24 Authlqor
-for-Va I iOat ion Rev. 00 (02 -2)
Equipment 0OS 2 hr ago 990045654 6 hr ago 990045652 IRM 16 2B EHC Pump
_ rvice Unit Status
-iys ago A Cond Demin
-Ays ago 2 R Cond Demin jays ago
- A' Cond Demin
_ :ys ago 2?) Cond Demin jays ago 2E Cond Demin
-3ys ago 2F Cond Demin
-.ays ago 2G Cond Demin days ago 2A RWCU days ago 2B RVVCU Jays ago 2C RVVCU Jays ago U2 FPC Demin Unit 2 Abnormal Component Position U2 Open Operability Determinations with Compensatory -:tions Events and Misc. Information Plant shut down in progress per DGP 02-01. Ready tc take c- -B Condensate/Booster Pump. Hydrogen addition already isolated to 2B Condensate/Booster Pump. QNE dire:c-.: shutting down per station procedures using reverse sequence. No REMA is required.
DW samples:
Iodine 131 Beta/Gamma 2.5 X 10-13 1.5 X 10-11 ILT 01-1 NRC EXAM, Scenario ILT-N-3 Pace 22 Rev. 00 (02/02)
AUt-Or-fc I
\\/,
lat i on Cut In Cut In Cut In Cut In Cut In Cut In Cut Out Cut In Cut Out Cut Out Cut In
IDate TOt-'
Unit 3 Turnover ECCS Status: All available Online Information Shutd-,,,n Information N/A MWe [EPU]
MODEi4 Tim ý Boil: 24 hrs.
Online Risk: N/A Shu:zDwn Risk: Green Risk Equipment: N/A Prote:ted Path: None Unit 3 Priorities Statior Driorities Maintain operation per EDO LCORAs LCORA # None Start Title Clock Ends Shift 1 Activities (X = C-npleted)
Shift 2 Activities Shift 3 Activities D]
D]
D]
]
D DE I Common Unit Activities Shift 1 Activities (X = C-mpleted)
Shift 2 Activities Shift 3 Activities D
D]
ED I]
Common Unit Procedures I Surveillances in Progress None Unit 3 Conditions, Status, Abnormalities DGP 01-S1. Start-up Checklist, in progress Compensatory Actions, Extra Checks None ILT 01-1 NRC EXAM, Scenario ILT-N-3 Page 23 of 24 Rev. 00 (02/02)
AUtl[
or f-or Val Idatior
Equipment OOS None Service Unit Status 5 days igo 8 days ago 10 days ago 5 days ago 3 days ago 15 days ago 3 days ago 750 days ago 390 days ago 60 days ago 444 days ago 3A Cond Demin 3B Cond Demin 3C Cond Demin 3D Cond Demin 3E Cond Demin 3F Cond Demin 3G Cond Demin 3A IRWCU 3B RWCU 3C RWCU U3 FPC Demin Unit 3 Abnormal Componen: :')sition None U3 Open Operability Determ - 3tions with Compensatory Actions None Events and Misc. Informatio DGP 01-S1, Start-up Checklis: - progress ILT 01-1 NRC EXAM, Scenar,: _T-N-3 Page 24 of 24 Rev. 00 (02/02)
Au lnSor-for Val ida ion Cut In Cut In Cut In Cut Out Cut Out Cut Out Cut Out Cut In Cut Out Cut Out Cut In
Dresden Generating Statiol/
SIMULATOR EXERCISE GUIDE ILT 01-1 NRC EXAM SCENARIO ILT-N-5 Rev. 00 02/02 DEVELOPED BY:
Exam Author Date APPROVED BY:
Date SimSce - a rio-ILT-N-5.doc Master Copy
See- _ - o Outline Facility Dresden Scena - ',- ILT-N-5 Examiners Op-Test No ILT 0 Operators Initial Conditions: Approxj-,a:ely 78% reac:
power, IRM channel 16 out of service, 2B EHC Pump OOS; Unit 3 is in M:,:e 4.
Turnover: Power reductio-n progress for :--well entry.
Event Malf.
Event Event No.
No.
Type*
Description 1
N/A N
ANSO rot:- :.g idle SDC pumps SRO N/A R.NSO 2
N/A F
SRO Iov,e-reactor power by reducing recirculation flow MGGH2CON ANSO ma - generator hydrogen temperature controller outpu:
SRO fails ow ICTUBLK O
iso -:ion condenser tube leak iSRO N/A NSO 5
C CRP pump failure SRO RRMAFDBK NSO 6
Arec
-:ulation pump controller speed signal failure SRO 7
CIGP1l ALL spu-ous group 1 actuation and reactor scram 8
RDHLVFPA M
RDHLVFPB RDHLDEGA ALL SD. partial hydraulic lock (ATWS)
RDHLDEGA RDHLDEGB 9
SCRLFVAD NSO SBC pump relief valves fail open SCRLFVBD SRO (N)ormal, (R)eactivity, (I -strument, (C- :nponent, (M)ajor NUREG-1021, Revision 8, Sup: ement 1
,Jt nhor Va I Idat c)n Page 2 of -5 Appendix D Form ES-
Dresden Gene--- -ig Station NRC IT
-7 AM Scenario --- N-5 Scenario Objective Evaluate the C:-eators in using the Failure to Scram DEOF
-:ngency procedure.
Scenario Summary Initial Conditic
~78% pov, e IRM chanre 16 out of service 2B EHC P-7p 0OS Load drop l-progress per DGP 03-01, Routine Power C.iges Unit 3 is in Mode 4.
Events:
Rotating ic e SDC pumps Load drop with recirculation flow Main geneator hydrogen temperature controller failure Isolation co-denser tube leak CRD pump failure Recirculation pump controller speed signal failure ATWS with Spurious Group 1 Isolation Scenario Sequence
"* The crew assumes the shift with reactor power at about - :/ and a power reduction in progress to conduct a drywell entry for leakage inspections.
The ANSO. as directed by the SRO, performs DOP 10K--6, Rotating Idle SDC Pumps.
"* The NSO then lowers reactor power by reducing recircu e::on flow following direction by the SRO.
"* Alarms are then received due to high main generator hy:-:gen temperature resulting from a failed controller.
Hydrogen temperature is restored after the controller is :.=.:ed in manual and adjusted by the ANSO.
"* Alarms are then received due to an isolation condenser :_:e leak. The isolation condenser is manually isolated by the ANSO. The SRO addresses the technical specifice::on requirements for the inoperable isolation condenser.
"* A field report is received that the 2B CRD pump is failinc : -e to rapid oil loss from a leak. The NSO shutdowns the 2B CRD pump and starts the 2A CRD pump.
During the power reduction, the speed control signal fail:z
- wN for recirculation pump 2A and the pump flow increase is stopped when the NSO locks out the scoop t During IMD ýiork on main steam line flow transmitterS, a i: irious group 1 isolation and a reabtor scram occurs.
A hydraulic lock of the scram discharge volume results t- :artial inward rod motion and an ATWS. When boron injection is rnitiated, the SBLC pumps do not inject boror --. the reactor due to the pump relief valves failing open. The crew then initiates actions for alternate SBLC - ection-. The scenario terminates after manual driving in of contro rods is in progress and a scram/reset has bee-successfully initiated.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 3 cý -
Rev. 00 (02/02)
Au t ror f or d datI ion
Event One - 1= :tating Idle SDC Pumps The crew per*: --s DOP 1000 06. Rotating Idle SDC Pumps Malfunctions red: 0 Success Path Performs 7 -
1000-06, Rotating Idle SDC Pumps.
Event Two - Lcad Drop with Recirculation Flow The crew lowe-z -eactor power by reducing recirculation flow.
Malfunctions re:-ired: 0 Success Path Load droppe: per procedures.
Event Three - Main Generator Hydrogen Temperature Controller Failure The crew recoc-zes and responds to a high main generator hydrogen temperature resulting from a failed ccntroller.
Malfunctions rec:ired: 1 (failure of auto mode of main generator hydrogen temperature controller)
Success Path:
Takes manLal control of main generator hydrogen temperature controller.
Event Four - Isolation Condenser Tube Leak The crew recogr zes and responds to isolation condenser high temperatures / radiation levels.
Malfunctions req. -red:
1 (isolation condenser tube leak)
Success Path:
Isolates the Isolation Condenser.
Event Five - CRD Pump Failure The crew recogr 7zes and responds to a field report that the 2B CRD pump is failing due to rapid oil loss from a leak.
Malfunctions rec.- -ed: 0 Success Path:
Swaps CRD :-rmps.
ILT 01-1 NRC EYf-M, Scenario ILT-N-5 Page 4 of 25 Rev 00 (02/C2)
Au tlhor forr Va idat ion
Event Six - Recirculation PumP ControllerSpeed Signal 7_.ilure The crew recognizes and responds to a recirculation purnp control srcT, Malfunctions required. 1 (Loss of recirculation pump speed
-oack signal)
Success Path ling low for recircWnatlon lci.mp 2A Locks out the scoop tube Events Seven, Eight and Nine - ATWS with Spurious GroL: 1 Isolation The crew recognizes and responds to a spurious Group 1 Iso _ý-on with an AT-', _7: ondition. The event is complicated by failure of the SBLC system.
Malfunctions required: 3 (Spurious Group 1)
(SDV hydraulic lock)
(SBLC relief valve failure)
Success Path:
"* Control rod insertion in progress.
"* Plant stabilized.
Scenario Recapitulation Total Malfunctions:
Abnormal Events:
Major Transients:
EOPs Entered:
EOP Contingencies:
6 4
1 2
1 ILT 01-1 NRC EXAM, Scenario ILT-Nl5 (ATWS)
(level and power contro Page 5 of 25 AU t r) or fo r Va ia t n
i or Rev. 00 (02/02)
Operatof Actions Form ES )D-2 Op-TestNo l--01-1 SC Event Descnýý in The ANSO Pumps
ýe-
- No IIT-N-5 Event No
-ted by the SRO, performs DOP 100(
Page 1 of 1
otating Idle SDC Time Pcsition SRO ANSO NSO Applic- - Actions or Behavior Directs -'SO0 to perform DOP 1000-06, Rotating I DC Pumps.
Perforr-
-e following actions per DOP 1000-06, R:_-F g Idle SDC Pumps.
r]
.rifies the following valves closed:
MO 2-1001-2A, B & C.
MO 2-1001-4A, B & C.
- *ces each SDC pump control switch to sti-
-:sd then within 3 sec
--es each pump control switch to stop.
-- quests operator to confirm rotation for ea: - :ump.
Monitors :3nels and assists as directed.
ROLE PLAY:
NLO to c::nfirm SDC pump rotation:
Report tv e (requested pump) rotated".
Event I Completion Criteria:
DOP '000-06 completed.
OR, r: the direction of the NRC chief examiier.
ILT 01-1 NRC EXAM, Scenario ILT-',-7 Page 6 of 25 Thor f or Va I ida t i on Rev. 00 (02/02)
Appendix D
Operator ActF Op-Test No ILT 01 1 Sce-
- No.
ILT-N-5 Event No 2
Page
_1 of 1
1, Event Description The NSO owy the SRO
-eactor power by reducing recirculation flow following direction by Time Position NSO SRO ANSO Applica-:_ Actions or Behavior Perforr-7ie following actions per DGP 03-01, Routine Power Changes, and DOP 0ox -03, Reactor Recirculation Flow Control System Operation:
Svers recirculation pump speed using the master controller
- entiometer.
- r. ifies expected power reduction.
Directs -:-cing reactor power per DGP 03-01, Routine Power Changes, and DO- :202-03, Reactor Recirculation Flow Control System Operation, by lowerinc --circulation pump speed.
Monitors :anels and assists as directed.
Event 2 Completion Criteria:
Suffi--ent power reduction.
OR, =-' the direction of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-',.-5 Page 7 of 25
. t1or for Va i dTa i on Rev. 00 (02/02)
Apperndix D Form t S D 2
Operatoe Action Op Test No ILT 01-!
Scenario No ILT-N-5 Event No 3
Appendix D Event Description Alarms are then received due to high main generator hydrolen
-r-erature resulting from a failed controller Hydrogen temperature is restor-: ý`ter the controller is placed in manual and adjusted by the ANSO.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger - which fails the main generator hydrogen temperature controller output.
Verify trigger 3 automatically activates when the main gener-ror hydrogen temperature controller is placed to MAN.
Performs the following actions per DAN 902-7 E-11, H2 Sea iM
& Alterrex Pnl Trouble and DAN 2252-7 A-8,.
L Directs NLO to local panel 2252-7 to determine alar- "eceived.
LDiagnosis that the main generator hydrogen cooler -emperature controller auto mode has failed and places in MAN -,:de and restores temperature to normal band.
SIMULATOR OPERATOR / ROLE PLAY:
NLO to panel 2252-7 (wait 2 min):
Activate trigger 4 then Report "the alarm is A-8, Machine Gas Temperature High, and I have acknowledged it".
NLO to check hydrogen cooler TCV operation: (wait 1 min)
Report "the hydrogen cooler TCV appears to be bperating ncrmally.:
Directs ANSO to take manual control of the main generator h.,drogen temperature controller.
Notifies Shift Manager and IMD of controller problem.
ROLE PLAY:
Respond as individual notified.
Monitors panels and assists as directed.
Event 3 Completion Criteria:.
-Takes Manual control of the main generator hydrogen tern-erature controller.
OR, at the direction of the NRC chief eXaminer.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 8 of 25 Rev 00 (02/02 Autnior For Val dation ANSO SRO NSO Form ES-D-2 e
1 of 1
Operator.
- iit, Op-Test No ILT 0-1 Scenario No ILT-N-5
-vent No 4
Page 1 of 1 Event Description Alarms are received due to an isolatio.
.enser tube leak The isolation condenser is manually isolated by the D. The SRO addresses the technical specification requirements for the ino
-e isolation condenser.
Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chie- - aminer, activate trigger 5 which inserts an Isolation Condenser tube lea" 5%).
ANSO Performs the following actions p -
-,N 902-3 C-4, Isol Condr Temp Hi, and /
or DOA 1300-01, Isolation Conda- _-r Tube Leak:
OMay try to reseat the MC -'301-3 valve:
"* Closes MO 2-1301- '
"* Opens MO 2-1301-c
"* Closes MO 2-1301-:
"* Opens MO 2-1301-z
"* Opens AO 2-1301-1 20
"* Checks indication th=- -ak has stopped O Isolates the Isolation Co'-: --ser by closing:
"* MO 2-1301-1
"* MO 2-1301-2 MO 2-1301-3
"* MO 2-1301-4
"* AO 2-1301-17 & 20
"* MO 2-1301-10
"* MO 2-4399-74 SRO Enters DOA 1300-01, Isolation C:,-.:enser Tube Leak, and directs:
0i May try reseating the MC >-1301-3 El Isolating the Isolation Co-,enser.
El Radiation Protection to s--, ey below the IC vent.
El Security to limit access be.,:
IC vent.
O Chemistry Department tc -armple IC shell side for activity.
El Declares IC inoperable.
References Technical Specificati:- z and determines:
E ITS 3.5.3.A.1; verifies HFK system operable immediately.
L ITS 3.5.3.A.2; restore IC S. item to OPERABLE within 14 days.
Notifies Shift Manager and MMD C tube leak.
/I NSO Monitors panels and assists as d ÷.ed>,. <..C, 1 de
/
ROLE PLAY:
/
,'¶ t
'o,/
£3/4///,e 4v-/I Respond as departments contacte:f Event 4 Completion Criteria:
Isolation Condenser isolated.
Technical Specifications refe_--ed.
OR, at the direction of the NF-chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 9 c' :
Rev. 00 (02-2)
Au t rn flor
/a
. - - i on Appendix D)
` orm ES-[D 2-
o-
)pendix D I-orm ES-D 2 Dp-Test No ILT
-vent Descriptic Time 1
Scenario No ILT-N-5 field report is eceived tnat the 2B CeiD akR The NSO shutdowns the 2B CLD pY It No 5
Paue I of 1
"i-s failing due to rapid oil loss from a 3nd starts the 2A CRD urimp ROLE PLAY:
At the discretion of the NRC chief exa-per, report as NLO that "the 2B CRD pump is rapidly losing oil from the put-. outboard bearing".
Performs the following actions per DC - D300-01, Control Rod Drive System Startup and Operation:
0L May direct the NLO to perforr- -e-startup checks per the procedure.
L Verifies 2A CRD pump dischao:e valve MO 2-0301-2A open.
0L Starts 2A CRD pump.
L Stops 2B CRD pump
)
LI Verifies charging water press;--_- between 1450 to 1500 psig.
L Directs NLO to perform post-s:u-tup checks per the procedure.
ROLE PLAY:
NLO to perform 2A CRD pump pre-stawup checks (wrait 3 min):
Report "I have completed the pre-start,.- checks for2A CRD pump".
NLO to perform 2A ORD pump post-sta'-Up checks (wait 3 mi):
Report "I have completed the post-staE-,, chec~ks for 2A CR0D pump".
Directs NSO to swap CRD pumps per - 3P 0300-01, Control Rod Drive System Startup and Operation; OR, directs NSO to immediately swap ?RD pumps per DOA 0300-01, Control Rod Drive System Failure.
Notifies Shift Manager and MMD of CR pump problem.
Monitors panels and assists as directez Event 5 Completion Criteria:
CoD pumps swapped.
OR, at the direction of the NRC chi;= examiner.
W_T 01-1 NRC EXAY Scenario ILT-N-5 Page 10 of 25 Rev. 00 (02/02)
Autnor For Va i( a-Dn NSO SRO
)
ANSO
, 4 ;¸ Operator Act~on
Operator Actions Op-Test No ILT Event Descriptic' Scenario No ILT-N-5 Event No 6
Page
_1 of 2 e speed control signal fails low for recirculation pump 2A and the pump flow
'ease is stopped when the NSO locks out the scoop tube.
Applicant's Actions or Behavior SIMULATOR OPERATOR:
At the discretion of the NRC chief examiner, activate trigger 6, which fails the 2A Recirculation Pump speed feedback signal.
Performs the following actions per DAN 902-4 E-6, 2A/B Recirc PPs Speed Mismatch, and DOA 0202-03, Reactor Recirculation System Flow Control Failure:
O Places the 2A M-G Set Scoop Tube Power Lockout Reset Switch in the Lockout position.
d Verifies Core thermal power <2927 MWth.
LI Completes actions of 2A Recirc M-G Lockout in DOP 0202-12, Recirculation Pump Motor Generator Set Scoop Tube Operation.
"* Places both recirc pump speed control transfer stations to manual.
"* Runs 2A Recirc M-G Set speed demand to minimum.
"* Places caution card on its Lockout Reset switch.
]
Coordinates with licensed operator at the 2A Recirc M-G Set Scoop Tube to lower its speed to match 2B Recirc M-G Set per DOP 0202 12, Recirculation Pump Motor Generator Set Scoop Tube Operation.
SIMULATOR OPERATOR / ROLE PLAY:
NS SRO ANS3 ILT 01-1 NRC EXA' Scenario ILT-N-5 Page 11 of 25 Rev. 00 (02/02)
Am lr/or for-Val idat on Time Posit Licensed Operator to lower 2A Recirc M-G Set speed locally (wait( 31 nin)
Report "I am ready to begin lowering 2A Recirc M-G Set speed". Wjen directed to lower the speed, toggle trigger 7 active anid then inactive/ about every 10 seconds to "bump" the speed down until the NSO directs s~topping the speed drop.
Enters and directs performance of DOA 0202-03, Reactor Recirculation System Flow Control Failure.
0 Enters and directs performance of DGA 7, Unpredicted Reactivity Addition.
O Contacts QNE.
L]
May request NLO to take local speed readings 0I Directs NSO to coordinate with a licensed operator at the 2A Recirc M-G Set Scoop Tube to lower its speed to match 2B Retirc M-G Set.
0 Notifies Shift Manager and IMD of controller problem.
IBegins working through the steps of DGA 7, Unpredicted Reactivity Addition, but will not have time to complete the required actions.
I I
Appendix D
`-orm ES-D-2
lperatoi Actions Op-Test No ILT 01-1 Scenario No ILT-N-5 Even: ',
3/4 6
Event Description The speed control signal fails low for recirculatio- --,mp 2A and t increase is stopped when the NSO locks out the _u:oop tube
'p flow Time Position Applicant's Actions or Behavior ROLE PLAY:
NLO to obtain local speed of the 2A Recirc MAG Set: (Wait 5 - - :or initial reading, 1 min for subsequent)
Take variable RRNMGGEN(1) times 1150 RPM and report t- -esult as the 2A Recirc MG Set speed.
NLO to obtain local speed of the 2B Recirc MG Set: (Wait 1 r-.
Take variable RRNMGGEN(2) times 1150 RPM anrd,report the -esult as the
-2B Recirc MG Set speed.
Event 6 Completion Criteria:
forts in progress to lower 2A Recirc M-G Set speed.
OR, at the direction of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 12 of 25 Rev. 00 (02102)
Au t nor for Va iidat i
2 of 2 A,[ppendix D Sr n l [: S-D[h2
Appendix L
-rator Actions
-orm ES D 2 Op-Test No ILT 01-1 Event Description A sp tne relie SRO Sc-- ario No. _-_.-N_5 Event No 7, 8& 9 7-- 1 of 4
'urious c-sp 1 iso :-
and a reactor scram occirs A partia' *,-- jlic lock of scram c Scharge vo _-e resLlts in an ATVWS The SBLC systen - Sdue pLimp f valves :ailing oper The crew initiates alternate SBLC in"j r
Applicant's Actions -r Behavior SIMULATOR OPERATOR:
At the discretion of :he NRC chief examiner, activate trigger 8.,,,-ich inserts a spurious Group, Isolation and SBLC relief valve setpoint drif Performs the follov, -g actions per DGP 02-03, Reactor Scram I
Presses sc-am pushbuttons 0
Places moce switch in shutdown P
Checks rocs inserted; discovers ATWS condition E
Initiates AR.
U Verifies rec -c pump speed at minimum.
Enters DEOP 0100 RPV Contrnl WNhen rhcp¢i....--...
+- k*
A-
,'o vIt LIH dL -i S corndilion exists, exits DEOP '00 and enters DEOP 400-5, Failure to Scra-. and directs the followinc EV 1 Placing ADS to inhibit El Placing both CS pumps in PTL Power Leg El Running back recirc to minimum.
0 Tripping the recirc pumps El '1Directing Alternate Rod Insertion per DEOP 500-0O manual:y driving rods.
repeated scram/resets.
El Initiating SBLC before SPIT of 1 100 F.
Level Leg El Verification water level instruments are accurate El Verification any required automatic actions have occurre:
El Directing jumpers installed for MSIV low level and Off Gas high Rad isolations El ý Terminating and Preventing injection except boron and CRD until RPV/L is _< -35 inches.
El If SP/T is above 1 10°F, lets level drop until:
"* Power is below 6%, OR
"* Level drops to -143'in. (TAF), OF;
"* All ADSVs stay closed and PC/P stays below 2 psig El
'I Re-establishing injection to MAINTAIN RPV Water level above
-164 inches.
Pressure Leg El Dropping RPv/P to 945 psig using ADSVs E
Maintaining.<1060 psig using HPCI/ADSVs SIMULATOR OPERATOR I ROLE PLAY:
Operator to jumper the MSIV Groupl-59 in. and offgas hi hi radia-Dn isolations (wait 5 min)
Activate trigger 9 and report "the MSIV Groupl-59 in. and offgas - hi radiation isolations are jumpered".
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 13 of 25 Rev. 00 (02/02)
-:utnort
-or Validation
Form ES-D-2
-.st No ILT 01-1 Scenario No Event No 7, 8&9 Page 2
of 4 E
Description A spurious group 1 isola*
the scram discharge vol, relief valves failing open
- d a reactor scram occurs. A partial hydraulic lock of
-sults in an ATWS. The SBLC system fails due pump
- crew initiates alternate SBLC injection.
T --
Position Applicant's Actions - 3ehavior NSO /
ANSO NSO NSO Performs DEOP 4 Failure to Scram, actions as directed:
L] J/Places A-B to inhibit L]
Places bo:-
3 pumps in PTL Power Leq LI Trips recirt_ _-::on pumps E 1 Performs "rternate Rod Insertion. (see below for specific actions) l Initiates bc-: - injection. Reports SBLC has failed to inject.
Level Leg 0
4 Terminat:es and Prevents injection except boron and CRD until RPV/L is _< -"' inches.
El If SP/T is a:ce 110 0F, lets level drop until:
"* Power
- elow 6%, OR
"* Level c-: s to -143 in. (TAF), OR All ADS S stay closed and PC/P stays below 2 psig 0
4/Re-estab shes injection to MAINTAIN RPV water level above
-164 inches Pressure Leg 0L Drops RP\\/ *o 945 psig ADSVs 0L Maintains <KB60 psig using HPCI/ADSVs
'IPerforms manua' :ontrol rod insertion per DEOP 500-05, Alternate Insertion of Control : :ds, as directed:
0 Bypasses t-- eRWM 0
Maximizes -i-e water pressure using one or more of the methods in DEOP 500-:
0 Inserts rods.sing RONOR in EMERG IN or the normal rod movement ::.: trol switch
- /Performs repeated scramiresets per DEOP 500-05, Control Rods, as di--.:ted:
0i Depresses ::.:se pushbuttons for iDV vent and 0L If RPV/L <--
inches, directs pulling ARI fuses.
0l Attempts tc -set scram 0L Directs scra-jumpers installed.
0L Resets the z: am 0I Verifies all
-.-3am valves closed 0
Opens the
',/ vent and drains 0
When 902-' >-1 clears, scrams reactor 11 Repeats az -ecessary Alternate Insertion of drain valves ILT 1 NRC EXAM, Scenario ILT-N-5 Page 14 of 25 Rev. 00 (02/02)
AU tn rO r-
-r Vai idat on
-of'\\t
,olor!
-ndix D)
Operator Actions For-
-D2 P-Jest No ILT01-1 Scenario No ILT-N-5 Event No 7, 8 & 9 Page 3-4 ent
Description:
A spurious group 1 isolation and a reactor scram occurs A partial hydraulic K of the scram discharge volume results in an ATWS. The SBLC system fails due cump relief valves failing open. The crew. initiates alternate SBLC injection.
-me Position Applicant's Actions or Behavior SIMULATOR OPERATOR i ROLE PLAY:
Operator to pull ARI fuses (wait 5 min):
Verify trigger 10 activated and report "the ARI fuses are pulled".
Operator to install scram jumpers (wait 5 min):
Verify trigger 11 activated and report "the scram jumpers are installed".
SRO U
Based on failure of SBLC to inject, directs performance of DECD 0500-01, Alternate Standby Liquid Control Injection.
SRO Enters DEOP 200-1, Primary Containment Control, when PC/P reaches 2 psig and performs/directs:
LI May direct starting Drywell Coolers per DEOP 0500-02.
U Initiation of torus sprays before PC/P of 9 psig U When PC/P is above 9 psig or before DWIT reaches 281OF: (may not reach these levels)
"* Verification of DSIL
"* Tripping of recirc pumps
"* Tripping of DW coolers
"* Initiation of DW sprays 0
Initiation of torus cooling U Verifies initiation of drywell and torus H2/O2 monitors ANSO Performs DEOP 200-1, Primary Containment Control, actions as directed:
U May start Drywell Coolers after jumpers installed per DEOP 05CD-02.
0 May initiate torus sprays and drywell sprays per Hard Card LPCI/CCSW OPERATION, as directed U
Initiates torus cooling per Hard Card LPCI/CCSW OPERATION as directed U Verifies initiation of drywell and torus H/0 2 monitors SIMULATOR OPERATOR I ROLE1 PLAY:
Operator to install jumpers to defeat DW Cooler trips (wait 5min)-:
Verify trigger 12 activated and, report "the DW Cooler trip jumpers.are installed".
ROLE PLAY:
Five minutes after the start of this event, call the Control Room as an IMD, Supervisor and report "While checking the Main Steam Line Flow instruments in the LPCI corner room, I slipped and fell into the instrument ex rack. I do not require medical attention".
C IL 01-1 NRC EXAM, Scenario ILT-N-5 Page 15 of 25 Re/ 00 (02/02)
Au ti lcr
-For Va I Idat i on
Appendix D F
.%D.
Op-TestNo: ILT01 -1 Scenario No.
IL.T-N Event 7 8 & 9 Page 4
3f 4 Event
Description:
A spurious group 1 isolation an: : reactor scram o-: --s A partial hydraulic ock of the scram discharge volume res s in an ATWS BLC' system fails due pump relief valves failing open. The c-,v initiates alterna:,-
SBLC injection.
Time Position Applicant's Actions or Be-.-vior SIMULATOR OPERATOR:
After the crew has reset t-e scram and at the scretion of the NRC chief examiner, RUN CAEP File ClrHydLk.cae whic-will remove the SDV hydraulic lock.
SRO Based on report that all rocr: are inserted, exi:s DEOP 400-05, Failure to Scram, and enters DEOP" :0, RPV Control ar: directs:
0 Securing Boron inection if any was sta-ted.
0 Restoring RPV le,,- to +8 to +48 inches.
I Develop a cooldon strategy (i.e.; rec:en MSIVs and/or restart RWCU)
NSO Reports that all rods inserm.e..t and performs the 'allowing as directed:
LI Restores level to -: to +48 inches.
Critical Tasks: (identified by I in guide) 11 With a reactor scra-m required and the -eactor not shutdown, TAKE ACTION TO REDUCE POWER by inje:ting boron and/or inserting control rods, to preent exceeding the cimary containment design limits.
[I With a reactor scram required, reactor "ot shutdown, and conditions for ADS blowdowr, are met, INHIBIT ADS to prevent an uncontrolled RPV depressuriza:cn, to prevent caus,-g a significant power excursion.
0 During an ATWS wrt conditions met tc perform power/level control TERMINATE AND PREVENT INJECTION, with exception of boron and CRD, into the :PV until conditions are met to re-establish injection.
El When conditions a-- met to re-establish injection use available injection systems t: MAINTAIN RPV water level above -164".
Scenario CompletionCriteria:
o Control rods inserted.
El RPV level and pressure stabilized.
F. OR, at the direction of the NRC chief examiner.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Pane 16 of 25 Rev. 00 (02/02)
AU t hor fo I a I i d at i o-Operaý-
--ctions
REFERENCES PROCEDURE DAN 902-3 C-DAN 902-4 F-,
DAN 902-7 E-11 DAN 2252-7 A-q DOP 0202-03 DOP 0202-12 DOP 1000-06 DOP 0300-01 DOA 0202-03 DOA 0300-01 DOA 1300-01 DGP 02-03
+/-
TITLE Isol Cc emp Hi 2A/B F- -
PPs Speed Mismatch H2 Se2
& Alterrex Pnt Trouble Machir- -:3s Temperature High Reactc-
-*sirculation Flow Control System Operatior RecircL
-:n Pump Motor Generator Set Scoop Tube
-ation Rotatin:-
e SDC Pumps Control J Drive System Startup and Operation Reactor :-circulation System Flow Control Failure Control d:
- Drive System Failure Isolatior - endenser Tube Leak Reactor S::ram REVISION 12 13 05 20 20 03 32 05 18 15 54 DGP 03-01 Routine :::wer Changes 40 DGA 7 Unpredi:zed Reactivity Addition 14 DEOP 0100-00 RPV Co-:1 09 DEOP 0200-01 Primary :.:ntainment Control 09 DEOP 0400-05 Failure tc scram 12 DEOP 0500-01 Alternate ý:-andby Liquid Control Injection 09 DEOP 0500-02 Bypassir-nterlocks and Isolations 10 DEOP 0500-05 Alternate -sertion of Control Rods 12 ii ILT 01-1 NRC EXAM, Scenario -- N-5 Page 17 of 25 Aut-hor for Val idation Rev. 00 (02/02)
I i
I
PRE-SCENARIO ACTIVITIES
- 1.
If applicable, conduct pre-scenario activities in accordance with TQ-AA-106-0107. SIMULATOR EXAMINATION BRIEFING.
- a.
Provide the crew with a copy of Control Room work request list
- b.
Provide the crew with a copy of DGP 03-01, Routine Power Ch down the second reactor feed pump.
- c.
Provide the crew with a copy of DOP 1000-06, Rotating Idle SE
- d.
Provide the crew with a shutdown plan.
- e.
rvd th "c.it
- copy, of the -REMA.
- f.
Inform the crew that (select an individual) is the QNE present ii
- g.
Direct the crew to perform their briefs prior to entering the simL
- 2.
Simulator Setup (the following steps can be done in any logical ord
- a.
Initialize simulator in IC 12 and reduce recirc pump speed to.6'2"%. (below exclusion range I
- b.
Run the initial setup caep file: ilt-n-5.cae
- c.
Establish the following simulator conditions:
- 1) Master Recirc Flow controller at -62%
C
- 2)
MWe at-710
- 3)
Condensate Demin dP between 20 and 45 psid [EPU]
- 4) Condensate pump amps between 160 and 255 amps [E
- d.
Secure the following equipment and tag out of service:
- 1) Place IRM 16 902-5 panel joystick in bypass and place
- e. Advance the chart recorders.
- f.
Add variables RRNMGGEN(1) and RRNMGGEN(2) to a Monitor screen
- g.
Mark up rod sequence as completed through step 130.
P~l,* t R~EMA.h..........
opiat bok
- i.
Complete the Simulator Setup Checklist.
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 18 of 25 Rev. 00 (02/02)
Author For Va idat ion
,omputeIr Aided Exercise Progranis ILT 01-1 NRC EXAM SCENARIO ILT-N-5 Initial Setup CAEP:
It-n-5 cae
- Setup for ilt-n-5
- Written by JAS
-Rev 00
-ýDate 12101
- INITIAL CONDITIONS
ý- Inserts SDV hydraulic lock.
mf rdhlvfpa 89.0 mf rdhlvfpb 89.0 mf rdhldega 89.0 mf rdhldegb 89.0
- overrides 902-3 G-13 off.
mf ser0240 off
- overrides IC rad mon downscale alarm off
ýmf serOO04 off Imf ser0019 off overrides SDC pump pressure meters to 25 psig and isolates the suction pressure tri: Switch.
ior sdgppad 25.018 ior sdgppbd 25.018 ior sdgppcd 25.018 irf sd10440A closed18 irf sd1044OB closedl8 irf sd10440C closedl8
- SETUP EVENT TRIGGERS
- Event Trigger 2 Inserts main generator hydrogen temperature controller output fails Io1',
trgset 2 "0"12 ior mgdh2cmn (2) man12 ior mgth2man (2) 0.012
- Event Trigger 3 When main generator hydrogen temperature controller is not in AUTO :r BAL, remove S MAN override.
trgset 3 ".not. (mgdh2cau.or. mgdh2cbl).and. mgdh2cmn"12 trg 3 "dor mgth2man"12
- Event Trigger 4 acknowledges the alterrex panel trouble alarm trgset 4 "0"12 irf t8l (4) truel2
- Event Trigger 5 inserts an Isolation Condenser tube leak (0.5%).
trgset°5 "0"12 imf ictublk (5) 0.512 4 Event Trigger 6 inserts 2A recirculation pump controller speed feedback signal failure
- rgset 6 "0"14
ýmf rrmafdbk (6)14
- Event Trigger 7 lowers 2A recirculation M-G Set speed at scoop tube.
trgset 7 "0"J4
'rg 7 "irf rrrascdc decrease"14 ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 19 of 25 Rev C 02/02)
AU thor-f or Va i i da t i on
- Event Trigger 8 inserts sputious group i --tuation anc Inserts full SDV hydraulic lock after 2 min trgset 8 0'4 imf cigpli (8)14 imf scrlfvad (8) 200,014 imf scrlfvbd (8) 200.014 imf rdfhylk (8 02:00)14 scram uand SBLC pump relief valves fail ope'
trgset 9 "0"16 irf ci59jp (9) in16 irf ogogjp (9) in16
- Event Trigger 10 pulls ARI fuses trgset 10 "0"16 irf aw4 (10) pulled 6
- Event Trigger 11 installs scram jumpers trgset 11 "0"16 irf rpjumpas (11) onI6
- Event Trigger 12 installs DW cooler jumpers trgset 12 "0"18 irf cidw28jp (12) inl8 irf cidw29jp (12) inI8
- Event Trigger 16 ramps 2A SDC PP Pressure up trgset 16 "sddpastr(1)"110 trg 16 "ior sdgppad 100.0 00:02"110
- Event Trigger 17 ramps 2A SDC PP Pressure down trgset 17 "sddpastp(1)"110 trg 17 "ior sdgppad 25.0 00:02"110
- Event Trigger 18 ramps 2B SDC PP Pressure up trgset 18 "sddpastr(2)"110 trg 18 "ior sdgppbd 100.0 00:02"110
- Event Trigger 19 ramps 2B SDC PP trgset 19 "sddpastp(2)"110 trg 19 "ior sdgppbd 25.0 00:02"110 Pressure down
- Event Trigger 20 ramps 2C SDC PP Pressure up trgset 20 "sddpastr(3)"I 10 trg 20 "ior sdgppcd 100.0 00:02"110
- Event Trigger 21 ramps 2C SDC PP Pressure down trgset 21 "sddpastp(3)"I10 trg 21 "ior sdgppcd 25.0 00:02"110
- END ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 2C : 25 Rev. 00 (02/02 Au * - -r
-For-i da t i on
t -- ears HydrE d.
rdfhylk ir a
-dhlvfpa 0 ir..-.dhlvfpb 0 C irt' -dhidega 0 irn-* -dhldegb 0
- END Support CAEP File CIrH,, -.- k.cae Lock ILT 01-1 NRC EXAM, Scenario ILT-N-5 Page 21 of 25 Rev. 00 (02/02)
AutAhor for-VaItid;-
on
Date: TODAY Unit 2 Turnover ECCS Status:
All Online Information Shutdown Information 710 MWe MODE 1 Time to Boil: N/A Online Risk: Green DF:
1.00 Shutdown Risk: N/A Risk Equipment:
Protected Path: N/A Unit 2 Priorities Station Priorities Continue Unit Shutdov, LCORAs LCORA # None Start Title Clock Ends Shift I Activities (X = C: -:ieted)
Shift 2 Activities Shift 3 Activities F-1
--I Continue Power Reduction LI I Common Unit Activities Shift 1 Activities (X = C:--:ieted)
Shift 2 Activities Shift 3 Activities LI LII
[II Common Unit Procedu es / Surveillances in Progress None Unit 2 Conditions, Stat-s, Abnormalities 2 hr ago 0500 IRM 16 OOS due to power supply failure. IMD waiting for replacement power supply to arrive from Quad Cities Station.
6 hr ago 5650 2B EHC pump OOS due to a problem with its pressure compensator. Expected BIS next shift.
Compensatory Actions Extra Checks ILT 01-1 NRC EXAM, S -iario ILT-N-5 Page 22 of 25 Rev 00 (02/02)
Au t or
-For Va I i dal i on
Equipment OOS 2 hr ago 990045654 6 hr ago 990045652 Service Unit Status IRM 16 2B EHC Pump 9 days a 7 days a_ :
16 days
-'a 2 days a2:
11 days E:o 6 days a, 2 days a--
376 days :go 240 days -go 20 days ;:o 76 days 2A Co 2B Co 2C C' 2D Coa' 2E Cor 2F Cor 2G Coa '
2A RW/
2B RWC 2C RW-_
U2 FPC pjl C ut In
-m Cut In
-n Cut In
-min Cut In m
min Cut In
'-ain Cut In
-min Cut Out Cut In Cut Out Cut Out e-fin Cut In Unit 2 Abnormal Component Position U2 Open Operability Determinations with Compensatory Actions Events and Misc. Information Power reduction in progress per DGP 03-01, Routine Power Changes The QNE directed reducing power per station procedures using reverse control rod sea'_--ce. No REMA is required.
A Drywell entry is required to perform a leak inspection. Drywell deiner-ng will be perfor-ed next shift.
DOP 1000-06, Rotating Idle SDC Pumps, step G.I, Bumping the Motor should be perfc--ed next. Step G.3 of DOP 1000-06, Clearing Low Suction Pressure Trip Signal, was performed the previous shift.
Then continue the shutdown.
DW samples:
Iodine 131 Beta/Gamma 2.5 X 10-13 1.5 X 1011 ILT 01-1 NRC EXAM, Scenario ILT-N-5 AU t Ior Page 23 of 25 for Val*
da't Rev. 00 (02/02)
Date: TODAY Unit 3 Turnover ECCS Status: All available Online Information Shutdown Information N/A MWe MODE 4 Time to Boil: 24 hrs.
Online Risk: N/A Shutdown Risk: Green Risk Equipment: N/A Protected Path: None Unit 3 Priorities Station Priorities Complete startup checklists LCORAs LOORA # None Start Title Clock Ends Shift I Activities (x = Completed Shift 2 Activities Shift 3 Activities D]
-- ontinue startup activities n]
E]
[l Common Unit Activities Shift 1 Activities (X = Completed Shift 2 Activities Shift 3 Activities nI L-F]
El K
LI Common Unit Procedures / Surveillances in Progress None Unit 3 Conditions, Status, Abnormalities DGP 01-S1, Start-up Checklist. n progress Compensatory Actions, Extra Checks None ILT 01-1 NRC EXAM, Scenario _T-N-5 Page 24 of 25 A,-
Or for II dat ion Pev. 00 (02/02)
Equipment OOS None Service Unit Status 5 days ago 8 days ago 10 days ago 5 days ago 3 days ago 15 days ago 3 days ago 750 days ago 390 days ago 60 days ago 444 days ago 3A Cord Derin 3B Cond Detain 3C Cond Detain 3D Cond Dernin 3E Cond Dernin 3F Cond Dentin 3G Cond Dernin 3A RWCU 3B RWCU 3C RWCU U3 FPC Demin Unit 3 Abnormal Component Position None U3 Open Operability Determinations with Compensatory Actions None Events and Misc. Information DGP 01-S1, Start-up Checklist, in progress 1
ILT 01-1 NRC EXAM, Scenario ILT-N-5 Pane 25 of 25 Rev 00 (02/02)
Author-
ý Val idalt ion C it In CUt tIn Cut In Cut Out Cut Out Cut Out Cut Out Cut in Cut Out Cut Out Cut In
÷