ML082381239
ML082381239 | |
Person / Time | |
---|---|
Site: | North Anna |
Issue date: | 08/21/2008 |
From: | Bates M, Eric Lee NRC/RGN-II |
To: | |
References | |
ER-08-301 | |
Download: ML082381239 (207) | |
See also: IR 05000338/2008301
Text
Final Submittal
(Blue Paper)
FINAL SIMULATOR SCENARIOS
NORTH ANNA JUNE 2008 EXAM
05000338/2008301 & 05000339/2008301
Appendix D Scenario Outline Form ES-D-1
Facility: North Anna Scenario No.: 1 Op-Test No.: 1
Examiners: Mark Bates Operators:
Mark Riches
Initial Conditions: Reactor is at approximately 45% power MOL ready to start a second feed pump. Unit was
returned to power yesterday following feed train work, and cleared chemistry hold 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. Rods are in manual
due to a problem with auto rod control. The letdown radiation monitor is OOS. 1-FW-P-2 (terry turbine) was
tagged out during the chemistry hold and was just returned to service. 2-CC-P-1A is tagged out for seal work.
Turnover: Start the "CO feed pump; the pump seals have already been vented in preparation for the start.
Continue to ramp unit to 100% using manual rods until instrument shop is finished troubleshooting the rod control
problem.
Event Malf. No. Event Event
No. Type* Description
1 N (B) Start a second feed pump per OP
N (B)
2 R (R) (S) Ramp unit up using normal ramping OP
3 CN0201 C (B) (S) Condensate pump trips with no auto-start of standby pump
3a RD0121 TS (S) Several minutes later IRPI indication for CB "A" rod K2 drops to 0
4 CH08 I (R) (S) Failure of 1-CH-FT-1122 high
I (B) (S) Failure of "A" SG steam pressure channel III low (which also fails steam
5 MS1701
TS (S) flow)
6 CH13 C (R) (S) Tube leak in non-regenerative HX
7 MS1001 C (B) (S) "A" SG Steam leak outside containment
"A" SG MSLB outside containment. (Reactor fails to trip. Rods will not
8 MS1001 M (ALL)
insert in auto. Motor-driven AFW pumps do not start automatically.)
RD32
9 C (ALL) Reactor doesn't trip automatically or manually (or with AMSAC).
RD38
10 RD14 C (R) (S) Rods will not insert in auto
FW2601
11 I (B)(S) Motor-driven AFW pumps don't auto-start
FW2602
Scenario may be ended when safety injection has been terminated
(Events 9-11 occur during event 8 and are numbered only for use on Forms
301-5 and 301-6)
- (N)ormal, (R)eactivitv, (I )nstrument, (C)omponent, (M)aior
IXMNCN
NIDH Jffi<\. PO¥R STAll CN
IN 11 PL U CFNiID CPERATCR ~N\TI CN
SCENARI 0 m::: 1
1. Start a second feed punp using CP
2. Ranp unit up using nornal ranping CP
3/3a. Trip of a running Cbndensate punp ~th no auto-start of standby punp
vJ I RPI for cont r 01 bank "I\.' rod K- 2 dr oppi ng toO
4. Fai 1ure of 1- ffi FT-1122 hi gh
5. Fai 1ure of st earn pressure channel low
6. Tube leak in non-regenerative HX
7. Stearnleak outside containnrnt
8. ~LB outside containnrnt
Scenario Recapitulation:
~lfunctions after ECP 2 ( React or ~ 11 not t rip aut onat i call y or
entry nanually/rods ~ll not insert in auto, IlDtor-driven
aux feed punps do not auto-start)
Total ~lfunctions 9(Running condensate punp trips/standby punp doesn't
auto-start, IRPI failure, 1-ffiFT-1122 failure, SG
stearnpressure channel failure, tube leak in non-
regen HX; stearn 1eak out side cont ai nnrnt, ~l.B,
react or ~ 11 not t rip aut onat i call y or nanuall y/ rods
~ 11 not i nser tin aut 0, IlDt or - dr i ven aux feed punps
do not aut 0- st art)
ItJnor nal Event s 5 (Running condensate punp trips/standby punp doesn't
aut 0- st art, 1- ffi Ff-1122 fai 1ure, SG st earn pressure
channel f ai 1ur e, tube 1eak in non- regen HX; stearn
1eak out side cont ai nnrnt )
~j or Transi ent s 1 (~lB out side cont ai nnrnt )
HPs Entered 3 ( FR- S. 1, B- 2, ES- 1. 1)
ECP Cbntingencies 1 (FR- S. 1)
0- it i cal Tasks 3
Sc:EN\RI 0 Il.RA1l CN
SID me 1 Page 2 Revision 0
130 Mnutes
SID m:: 1 Page 3 Revision 0
SIMULATOR EXAMINATION SCENARIO SUMMARY
SCENARIO NRC 1
The scenario starts wth the unit at approxirmtely 45%pov.er ready for a
second ~in Feed purrp to be started. The unit vas returned to pov.er last shift
follow ng feed t r ai n WJr k and cl ear ed a 30% cheni stry hoI d 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. Rods
ar e i n rmnual due t 0 a pr obI em w t h aut 0 rod cont r 01 t hat 18C i s cur rent 1y
investigating. The letdo~ radiation nonitor, l-Cll~128, is ((8. The
t ur bi ne- dr i ven auxi 1i ar y f eedvat er purrp, 1- FWP- 2, vas tagged out dur i ng the
cheni stry hoI d and has j us t been ret ur ned t 0 s er vi ce, PM' vas SM. 2- CC- P- lA
i stagged out for seal \'Dr k.
First, the creww11 start a second ~in Feed Purrp in accordance wth 1-
CP-2.1, "ihit Startup frornMlde 2 to Mlde 1," and l-CP-31.1, "Min Feedvater
System"
~xt, the crewwll rarrp the unit up in accordance wth l-CP-2.1, "ihit
St ar t up from Mlde 2 to Mlde 1." O1ce the react or pov.er has i ncr eas ed
approxirmtely 5% the first failure wll occur.
lliring the rarrp, l-CNP-IAwll trip and l-CNP-IB wll not auto-start.
The crew w 11 ent er 1- AP- 31, "Loss of Mi n Feedvat er," and st art the "B"
Cbndens at e purrp. Sever al ni nut es i nt 0 t he event, an I RPI for rod K:- 2 i n
cont rol bank "1\' w 11 drop to zero. The lB w 11 revi ew t echni cal speci fi cat i on
3.1.7 and notify the instrunent shop. O1ce condensate flow has been re-
established and tech specs reviev.ed, the next event can occur.
It this tine, charging flowtransnitter, l-CllFT-1122, wll fail high.
The cr ew w 11 res pond i n accor dance w t h the AR for G C5 and take l11lnual
cont r 01 of 1- Cll FCV- 1122. O1ce char gi ng fl ow has been res tor ed to nor rml the
next event can occur.
~xt, t he O1annel II 1st earn pr es sure trans ni t t er for "I\' SG ( 1- M- Pf-
1475) fai 1slow The crew shoul dent er 1- AP- 3, "Loss of \h al
Ins t r unent at ion," s vap steam gener at or 1evel cont r 01 channel s, and refer to
t echni cal speci f i cat ions. It t hi s tine t he next event can occur.
CUe to the earlier oscillation on the charging system a tube leak wll
develop in the non-regenerative heat exchanger. The crewwll respond in
accor dance w t h 1- AP- 16, "I ncr eas i ng Pr i rmr y PI ant Leakage." The cr ew w 11
isolate letdo~ and rmke preparations to place excess letdo~ in service. It
t hi s tine t he next event can occur.
A srmll st earn 1eak W11 develop in the rmi n st earn val ve house on t he "I\'
steam 1i ne bet v.een the l11li n steam t rip val ve and the cont ai nrrent vall. The
cr ew W11 not i ce a decr eas e in negavat t s and an i ncr eas e in react or pov.er and
enter l-AP-38, "Fxcessi ve Load Increase," and begin to rarrp the unit do~. It
SID m::: 1 Page 4 Revi s i on 0
this ti~ the next event can occur.
The "!\.' rmi n stearn 1i ne w11 r upt ur e and the cr ew w 11 be expect ed to
ent er 1- E- 0, "React or Tri p and Saf et y I nj ect ion." The react or w11 f ai 1 to
trip, requiring the crewto transition to FR-S.l, "Response to NIclear POYer
~ner at i on! JXIWi." Rods w 11 not be ab1 e to be ins er ted in aut o. Glce the
reactor has tripped the crewwll return to l-E-O and then transition to l-E-
2, "Faulted Stearn~nerator Isolation." The creww11 then transition to 1-
£5-1. 1, "SI Terrrinat i on. " The scenario rmy be ended once SI has been
t errri nat ed, or at the di scret i on of the 1ead eva1 uat or.
SID NC 1 Page 5 Revision 0
Pre-job Brief for Scenario NRC-l
Unit Status:
Unit 1 is at approximately 45% power. The unit was returned to power last shift following
feed train work and cleared a 30% chemistry hold 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. RCS boron is 1202 ppm
and core age is 9000 MWD/MTU. Aux steam is on unit 2.
Unit 2 is at 100% power.
Equipment Status:
Control rods are in manual while the Instrument Department investigates a problem with
auto rod control. l-CH-RM-128, Letdown Radiation Monitor, is out of service. 2-CC-P-IA
is tagged out for seal work.
The turbine-driven auxiliary feedwater pump, I-FW-P-2, was tagged out during the
chemistry hold and was just returned to service, PMT was SAT. Maintenance rule window
is green.
Shift Orders:
Start "C" main feedwater pump and then commence a ramp to 100% power.
The 2 non-running Main Feed Pumps have been vented per the OP.
The Unit 1 turbine building operator has been briefed and is standing by at the "C" Main
Feed pump with 1-0P-31.1.
Control rods are to remain in Manual at this time due to the problem with auto rod
control.
Ramp Directions
Reactor engineering estimates it will take approximately 4033 gallons ofPG to return the
unit to 100% power.
Approximate rod positions: 178 steps at 75% power
202 steps at 90% power
AFD limits: 50% power -27/+20
100% power -12/+6
SCENARIO TURNOVER SHEET
Read the following to the crew:
Purpose: Thi s exani nat i on i s i nt ended to eval uat e the cr ews per for rmnce of
various tasks associated wth the Initial license Q>erator Training
Pr ogr am Al act i vi ties shoul d be conpl et ed in accor dance w t h
approved operations standards.
1. You are on a day shift during the veek.
2. A rough log should be rmintained to aid in rmking reports and to help during
bri efs.
3. Respond to ~at you see. In the unlikely event that the sinulator fails
such that illogical indications result, the session wll be terninated and
the cr ew i nf or rred.
Unit Status:
lhi t 1 is at appr oxi rmt el y 45% pover . The uni t WiS ret ur ned to pover I as t
shift followng feed train oork and cleared a 30%chemstry hold 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.
RCS bor on i s 1202 ppm and cor e age i s 9000 MIY MU lux steam i s on uni t 2.
lhi t 2 is at 100% pover.
Equipment Status:
Gmt r 01 rods ar e in rmnual ~i 1e t he Ins t r urrent I£par t rrent i nves t i gat es a
pr obI em w t h aut 0 rod cont r 01 . 1- rn RM 128, Let dom Radi at i on Mni tor, 1 s out
of ser vi ceo 2- CC- P- 1A i stagged out for seal oor k.
The turbine-driven auxiliary feedWiter punp, 1-FVVP-2, WiS tagged out during
the cheni st ry hoI d and WiS just ret urned to servi ce, PM' WiS SM. Mi nt enance
r ul e w ndow i s gr een.
Shift Orders:
St ar t "C' rmi n f eedWit er punp and then comrence a r anp to 100% pover . The 2
non-running Min Feed Punps have been vented per the CP. In oper at or i s
standing by at the feed punp.
Gmt r 01 rods ar e tor ermi n in Mnual at t hi s t i rre due tot he pr obI em w. t h aut 0
rod cont rol.
SID m::: 1 Page 6 Revision 0
E\ENf 1: G ven that the uni t is at appr oxi nat el y 45% pover , the crewv.ill
st art a second Mi n Feedvat er Punp i n accor dance v.i t h 1- (p- 31. 1, "Min
Feedvat er Sys t em "
1l~ EXPIaID ICII CN I~~
SPD \er i f i ed: (I ni t i al s)
- 1- FWP- 1Cst art sand runs nor naIl y
IlP places "B" Cbndensate punp in
P1L
IlP places both control s v.i t ches
for 1- FWP- 1C i n P1L
IlP cl oses 1- FWMN- 150C
IlP verifies/places s v.i t ches for
"B" MP in P1L
IlP verifies/aligns feed reci rcs.
IlP starts each "C' MP IIDtor.
IlP opens discharge MN:
IlP ins t r uct s fi el d operat or to
IIDni t or local lube oi I
t enper at ur e.
IlP pi aces the "B" MP in PlJID and
ver i fi es its di schar ge MN opens.
IlP places "B" Cbndensate punp in
PUIU
crew di rect s i ni t i at i on of 0- <IP-
2.18.
NOTE: The next event can occur once
the crew has placed "e" MFP in service.
SID r<<:: 1 Page 7 Revision 0
E\E'[' 2: a ven that the uni t is at appr oxi rmt el y 45% pov.er and the cr ew has
been instructed to increase pov.er, the crew VIii I r anp the uni t up i n
accor dance VIi t h 1- CP- 2. 1, "lhi t St art up fromMlde 2 to Mde 1."
n~ E5<<>:ocIID ICII CN I r-81RI.CfCR ~
SPD \eri fi ed: (I ni t i al s)
- React or pov.er increases
- Turbine pov.er increases
- Tavg/Tref increase
- cenerator negavatts increase
NOTE: The crew needs to ramp to
>50% power for a TS call during Event
3. SUJ!I!:est approximately 53% power.
NOTE: The crew may raise primary
temperature prior to ramping the
turbine.
R:P adj us t s I i IIi t er pos i t ion, as
requi red.
R:P verifies/sets desired ranp
rat e (. 3% per IIi nut e) .
R:P i ncr eas es t ur bi ne sett er to
desired position.
R:P pr es ses CD on t ur bi ne.
R:P nonitors turbine ranp.
RO start s a di I ut i on men CIPS i ncl uded at back of
requi red. scenar 10.
RO VIi t hdr a Wi cont r 01 rods to
rmi nt ai n Tave VIi t hi n 1. 5°F of Tr ef
Vli.th rods above insertion IiIIits.
RO pI aces AMi!C in" N>r rml" men
procedure cri t eri a net.
NOTE: The next event can occur once
the crew has ramped to greater than
50 % power, or as determined by the
lead evaluator.
SIDm: 1 Page 8 Revision 0
E\£NI' 3/3a: a ven that the uni t is at pover and a ~in Cbndensate punp has
tripped v.i t h no aut 0- star t of the standby punp, t he crew v.i 11 be expect ed to
respond in accordance v.ith 1-AP-31,"Loss of ~in FeedVlater,"
TIl\E f..'PB:IID JC11 CN INi1RlO.tR ~
SPD \eri fi ed: (I ni t i al s)
- lnnunci at or s G 05 and, 1at er, G F6 i II uni nat e
- 1- eN P- 1A has anber br eaker di s agr eerrent light 1it
- 1- eN P- 1B does not aut 0- st art
- Feed punp suction pressure decreases
- Aft er sever al ni nutes: annunci at or s A rn and PF1 v.ill ill uni nat e
- I RPI for rod K 2 i n Cbnt r 01 Bank A v.i II drop to zero
- Rod futt om Ii ght for K 2 v.i I I ill uni nate
NOTE: Three minutes after the
Condensate pump trip, IRPI K-2 will
drop to zero.
B:P i dent i f i es annunci at or G 05,
Cl:NE'SA1E PP 1A 1B-1e AIJIO lRIP,
i 11 uni nat ed.
B:P i dent i fi es that 1- eN P-1A has
t ripped and 1- eN P- 1B has not
aut 0- star ted,
NOTE: Crew may not stop the ramp
until immediate actions of AP have been
completed.
lS di rect s crew to st op ranp and
secure anyon-going dilution,
lS di r ect sent r y i nt 0 AP- 31.
B:P checks pover > 70% (~
B:P verifies 2 rrnin feed punp
runni ng.
B:P checks MWpunp suet i on
pressure >300 psi g, (~
B:P st art s "B" Cbndensat e punp.
B:P checks any MWpunps t ripped.
(~
CI ew eval uat es reducing pover <
55%
- B:P s t abi I i zes SG level s.
SIDNC 1 Page 9 Revision 0
EWNf 3/3a: a ven that the uni t is at po~r and a ~in Cbndensate punp has
tripped w t h no aut 0- star t of the standby punp, the cr ew w 11 be expect ed to
respond in accordance w t h 1- AP- 31, "Loss of ~in Feed\1ater."
TI~ EXPInID ICII CN I N>IRI.CfCR ~
- CIew veri fi es MP per for rnmce:
- Suction pressure adequate
- <550 anps on lIDt or s
- l'llIlUnci at or F- B5 NJf lit.
NOTE: Report from field will be that
the "B" pump is running fine. Nothing
to see locally on the "A" pump. If sent
to breaker will report an overcurrent
drop.
CI ew 1UI.i nt ai ns st abl e pI ant
condi t ions.
NOTE: Three minutes after the Event 3a
Condensate pump trip, IRPI K-2 will
drop to zero.
RO i dent i f i es annunci at or s A rn,
RPI R(]) oor R(]) mP, and AFl,
aP1R Al..ARMR(]) IEW Sa)
NOTE: If unsure of conditions, the crew
may enter l-AP-l.2 for a dropped rod.
Steps in this procedure were not
included.
RO i dent i f i es I RPI K 2 i n cont r 01
bank "I':" i s r eadi ng zer o.
RO checks for ot her i ndi cat ions of
a dr opped rod.
RO i dent i fi es that no rod has
dropped, I RPI pr obI em
NOTE: If I&C is asked to investigate the
K-2 rod, they will report that it is an
IRPI problem.
US reviews Technical Specification
3. 1. 7A and det erni nes t hat a fl ux
1UI.p nust be done wthin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
(or po~r reduced t 0 <50~.
LS 1UI.kes notifications on
Cbndensate punp trip/auto-start
f ai lure, and I RPI i ndi cat ion.
NOTE: The next event may occur once
the standby Condensate pump has been
started and tech specs have been
reviewed.
SIDm2 1 Page 10 Revi si on 0
EW.Nf 4: a ven that t he char gi ng fl ow trans ni t t er has f ai 1ed hi gh, the crew
wll res pond in accor dance w t h AR for C- C5 annunci at or .
TIr-.E EXPIDID JCII eN I Ni1Rl.CfCR ~
SPD \eri fi ed: (I ni t i al s)
- Mounci at or G C5 w 11 ill uni nat e
- 1- ffi FI - 1122 w 11 indicate full scale high
- 1- ffi FCV-1122 W11 i ndi cat e ni ni num demmd
- I..at er, Gill nny al arm i f 1- ffi FC\L 1122 not yet in nnnual and open.
RO i dent if i es annunci at or G C5, rn
PP 10 RRm HX H -ill FLON
RO i dent i fi es char gi ng fl ow
indicates high on I-ffiFI-1122.
RO i dent i fi es act ual char gi ng flow
i ndi cat es low
NOTE: RO will need to monitor
pressurizer and VCT levels, and/or
letdown temperature, to adjust charging
flow.
RO takes nnnual cont rol of I-ffi
FCV-1122 and restores charging
fl ow to nornnl.
Gew nnkes report of instrwrent
failure and requests assistance.
NOTE: The next event can occur once
the crew has restored charging flow to
normal.
SIDm= 1 Page 11 Revision 0
E\ENf 5: G ven the pI ant i sin node one Wt hindi cat ions of a f ai I ed stearn
pressure t r ansm t t er, the crew w11 respond in accordance w th l-AP-3, "loss of
\i t al Inst rummt at ion. "
1l~ .F.>>>ICIID tCII CN I I I'S'IRlll(R ~
SPD \eri fi ed: (I ni t i al s)
- Pmlunci at or s F- I-D. and F- El ill um nat e
- St at us light s NO and N rB i 11 uni nat e
- I-M-PI-1475 fails low
- 1- M- PI-1474 fai I s low
- "I\..' MRV r anps cl os ed
- "1\..' SG level decreases
B:P i dent i f i es annunci at or s F- I-D.,
H S1MUf'E M> SG lA ill and F-El,
S1M<ENlA FW> SIMFLONGI III-IV.
B:P i dent i fi es 1- M- PI - 1475 and 1-
M- PI -1474 f ai ling low
lB di rect s t he crew to ent er l-AP-
3.
B:P verifies redundant channels
nornal.
B:P takes nanual control of the "I\'
Mi n Feed Reg \hI ve to cont r 01 SG
level.
Gew veri fi es fi rst st age pressure
i ndi cat ions nor nal .
G ew ver i f i es s ys tens af f ect ed by
PRZR level channel s nor nal :
- ro ver i f i es oper abl e
pressur i zer level channel
selected
- 00 veri fi es letdo~ in service
- Gew I eaves 1- rn FCV-1122 in
nanual due to previous failure
- 00 veri fi es cont rol group
heat er s ar e not tri pped.
G ew ver if i es bot h fir s t stage
pressure channels nornal.
Gew veri fi es all SCMC channel s
selected to an operable channel.
(tq
SID m::: 1 Page 12 Revision 0
E\flIrr 5: a ven t he pI ant i sin rmde one w. t hindi cat i ons of a f ai I ed steam
pressure transnitter, the creww.ll respond in accordance w.th 1-PP-3, "LDss of
\it al Ins t r ummt at ion. "
CI ew s vaps to oper abl e SCNfC
channel s.
- ro veri fi es cont rol rods in
mmual
- CI ew pI aces steam dunps i n
ei t her CFF or steam pr es sure
rmde
- BOP checks all bypass ~ in
mmual
- BOP pI aces all MR\S i n mmual
- CI ew s el ect s channel I V on
SGt(S
- CIew ver i fi es all SG 1evel
channels are operable
- BOP veri fi es st earn generat or
level s are on program
- BOP places MR\S in Auto
- ro ret urns st earn dunps to Tave
rmde
- CIewleaves control rods in
mmual due to aut 0 rod cont r 01
problem
CI ew ver i f i es oper at i on of
instrunents and enters applicable
MPs (l-MP-55.77 for stearnflow
and 55.79 for st earn pressure).
US reviews Technical Specifications:
- 3.3.1 (function 15 Cbndition~
72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> s t 0 pI ace i n trip)
- 3.3.2 (funct ions Ie, 1f, 4d, 4e
Cbndition~- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place
in trip)
- 3.3.3 (function 17 - Info
act ion)
- 3.3.4 (Table B 3.3.4-1,
Ins t r unent 3c - Info act ion) .
lS reports failure and requests
assi st ance, VR, and CR
NOTE: The next event can occur once
TS havt: been reviewed, or as directed by
the lead evaluator.
SID m::: 1 Page 13 Revision 0
E\ENf 6: Oven that there are indications of prinary plant leakage due to a
tube leak in the non-regenerative heat exchanger, the cr ew v.i II take act ions
in accordance v.ith l-.AP-16, "Increasi ng Pri nary PI ant leakage."
1I~ EXPlDID PCII CN I Ni'IRl.CIffi REMRI<S
SPD \er i f i ed: (I ni t i al s)
- letdo~ flow decreases
- \Cf 1evel slow y decreases
- <::c surge t ank 1evel slow y increases
ID i dent i fi es a decrease in
1et do~ fl ow and! or a decr eas e in
\Cf 1evel.
NOTE: Crew may also check Aux
Building and Containment sump levels
at this time.
LS announces entry i nt 0 .AP- 16.
Gew veri fi es unit in IIDdes 1, 2,
or 3.
- ID veri f i es par arret er s under hi s
cont rol:
- PRZR level
- R::S subcooling
- \Cf level.
ID checks 1- rn LC\'-1115A not
di verted.
NOTE: Crew may also notice increase in
CC surge tank level at any time.
G ew checks 1et do~ par arret er s
nornal f or pI ant condi t ions:
- let do~ flow (~
ID i sol at es I et do~:
- Ooses 1- rn In'- 1200B
- Ooses 1- rn LC\'-1460A and
1460R
NOTE: Until letdown valves are closed
TS 3.4.13A for RCS leakage applies (4
hours to reduce leakage to within limits).
G ew checks exces s 1et do~
tenperature and pressure.
SIDNC 1 Page 14 Revi si on 0
E\mf 6: a ven that t here are i ndi cat ions of pri rmry pI ant 1eakage due t 0 a
tube leak in the non-regenerative heat exchanger, t he cr ew w. 11 take act i ons
i n accor dance w. t h 1- JiP- 16, "Increasi ng Pri rmry Pi ant Leakage. "
TIM: EXPIDED fCIl CN I 1'S1Rl.CIffi. ~
G ew checks char gi ng par arret er s
norrml:
- Purrp discharge pressure
- Row
- Regen HX out 1et t errper at ur e
- Seal Inj ect i on fl ow
- AB sunp level.
G ew checks cont ai nrrent
par arret er s :
- Surrp purrpi ng rat e
- Terrper at ur e
- Pressure
- Radi at i on
- n spat ches oper at or w. t h AB
at t achrrent , as t i rre perni t s.
G ew checks s af eguar ds par arret er s:
- Surrp al ar m;
- Radiation nvnitors
- Terrper at ur es
- Locally check for leaks, as
requi red.
Gew veri fi es 1- rn FC\'- 1122 in
aut 0 (and det er ni nes that it is
not des ired to pI ace i n AI.JID due
to previ ous fai lure).
Gew checks sarrpl e syst em
Gew checks no C\(S mmi pul at ions
in progress.
G ew checks ~ t her rml barri er
flow
G ew checks f or act i vi ties that
coul d af f ect prirmry leakage.
G ew checks ot her par arret er s
norrml. (~
R:P i dent i fi es that c:c surge t ank
level (and possibly c:c ~ are
i ncr eas i ng.
G ew ver if i es/ i sol at es I et doW! and
nvnitors head tank level.
G ew rmkes appr opr i at e
not i fi cat ions.
SIDm: 1 Page 15 Revi si on 0
E\fNf 6: Oven that t here are i ndi cat ions of pri nary pI ant I eakage due to a
tube leak in the non-regenerative heat exchanger, the cr ew v.t 11 take act ions
i n accor dance v.t t h 1- JiP- 16, "Increasi ng Pri nary PI ant Leakage."
TIM: EXPOCIID ICIl CN I l'S'IRLCKR ~
Q ew nakes pr epar at ions to pI ace
excess letdo~ in service.
NOTE: The next event can occur once
letdown has been isolated and the crew
is making preparations to place excess
letdown in service.
SIDm: 1 Page 16 Revi si on 0
E\ENf 7: a ven a stearn 1eak bet Vleen a MlV and cont ai mrent , t he crew \\ill
res pond in accor dance \\i t h 1- J!iP- 38, "Excessive Load Increase."
1l~ EXPJDID 1CII CN I~~
SPD \-hi fi ed: (I ni t i al s)
- Mi n st earn pressure decreasi ng.
- Tave decreasing.
- POVler i ncr eas i ng.
RO i dent i f i es Tave decreasi ng
unexpect edl y.
CIewidentifies that poVler is
i ncr eas i ng.
lB di rect screw to ent er 1- J!iP- 38.
RO veri fi es all st earn dunps
cl osed.
BCP verifies all SO PCR~ cl os ed.
CIew veri fi es rmi n t urbi ne load
norrml and react or poVler ~ 100%
and st abl e. (!q
NOTE: When operators have been
dispatched, a call will be made stating
that there is steam coming out the door
of the Unit one main steam valve house.
RO comrences 1oVler i ng Tave us i ng
bor at i on! cont r 01 rods.
BCP comrences 1 oVler i ng rmi n
t urbi ne load.
NOTE: Once the crew is informed of the
steam issuing from the MSVH they may
choose to trip the reactor due to safety
concerns and because a power reduction
will cause SG pressures to increase.
CI ew checks react or poVler reduced
to the poVler level before the
event st art ed.
NOTE: The next event will occur when
ramp has been stopped, the unit has
been tripped, or as directed by the lead
evaluator.
SIDNC 1 Page 17 Revi si on 0
E\mf 8: a ven that the uni tis at poV\Cr, and a Imi n stearn 1i ne br eak has
occurred and the reactor cannot be tripped either autoImtical1y nor Imnual1y,
the cr ew W11 be expect ed tor es pond in accor dance Wt h 1- B- 0, "Reactor Trip
or Safety Inj ection," I-fR-S.l, "Res pons e t 0 Nlcl ear PoV\Cr Gner at i on! AIW, "
1- B-2, "Faul t ed St earn Gner at or I sol at ion," and 1- ES-1. 1, "SI Terni nat ion. "
1I]..E ~InID ACII CN I l'8IRl.CKR ~
SPD \eri fi ed: (I ni t i a1 s)
- lnnunc i at or s F- Fl, F-F2, F- F3 ill uni nat e
- "pt stearn gener at or pr es sur e decr eas es unt i 1 generat or is bloWl dOWl
- The reactor does not trip autoImtica11y or Imnua11y
- Gmtro1 rods do not insert in aut 0
- l'ei t her rIDt or - dr i ven PFWpunp aut 0- star t s
crew i dent i fi es a Imi n st earn 1i ne
break has occurred.
lB di rect screw to ent er 1- B- O.
ID B:P at t enpt tot ri p the
react or.
lB di r ect s t he cr ew tot r ans i t i on
to FR- S. 1.
CTI Crew identifies reactor did not Critical Task
trip, transitions to l*FR*S.l, Insert i ng cont rol rods Imnuall y
"Response to Nuclear Power is on1 y cr it i cal i f an eIrer gency
bor at i on i s not st art ed
Generation!ATWS,"
- Ra B:P Imnua11 y t rips t he
react or. (~
- BJ> t rips t he t ur bi ne
- RO manually inseJ:1s.control rods~
BJ> checks all PFWpunps running,
(~
SIDNC 1 Page 18 Revision 0
E\ENf 8: a yen that the uni t i s at pov.er, and a rrnin stearnline break has
occur r ed and the react or cannot be t ripped ei t her aut orrnt i call y nor rrnnuall y,
the cr ew v.i II be expect ed tor es pond in accor dance v.i t h 1- & 0, "React or Tr i p
or Saf et y I nj ect ion, " 1- FR- S. 1, "Response to NIcl ear Pov.er Gner at i on! A1"W>, "
1-& 2, "Faul t ed St earn Gner at or I sol at ion, " and 1- ES-l. 1, "SI Terni nat ion. "
TIM: EXPICIID ICII CN I N)'IR[TI(R RfMRKS
CT2 Crew starts AFW pumps to obtain Critical Task
required minimum of 680 gpm *Bef or e H 1 cr iter i a ar e rret
flow:
BOP starts either t-FW -P-3At.t-FW-P~
3ft.
Crew identifies reactor did not CT 1 Continued
trip, transitions to I-FR-S.l, Starting errergency boration is
onl y cr i tical if rods are not
"Response to Nuclear Power
being rrnnually inserted.
Generation!ATWS, II
- IU ver if i es at leas tone
char gi ng £u!.1£ r unni ng.
- RO places in-service boric acid
transfer pump in fast ...
- RO opens eme" eD9: borate valve lJ
- CIewverifies adequate negative
react i vi t Y i ns er t i on or i nj ect s
the BIT.
NOTE: Once the steam leak is reported
the crew may close the MSTVs.
NOTE: A safety injection will likely
occur before the reactor is tripped. The
crew will initiate attachment for SI after
the reactor has been shutdown. This
attachment is included at the back of the
scenario.
NOTE: Approximately two minutes
after operator is dispatched the reactor
will be locally tripped.
CI ew di spat ches oper at or to
I ocall y t rip react or.
NOTE: If reactor is subcritical the crew
will transition to E-O at this time, see
next pa~e for steps.
CI ew checks if react or i s
subcri tical.
NOTE: Crew may throttle auxiliary feed
in this or subsequent steps.
RJ> checks sa level s.
SIDm: 1 Page 19 Revision 0
~8: a yen that the uni t is at pov.er, and a rrain steamline break has
occur r ed and the react or cannot be tripped ei t her aut orrat i call y nor rranuall y,
the crew W11 be expect ed tor es pond in accor dance w t h 1- B- 0, "React or Tri p
or Safet y I nj ect ion, " I-FR- S. 1, "Response to Nlcl ear Pov.er Gmer at i on! ~, "
I-B- 2, "Faulted Steam~nerator Isolation," and l-ES-1.1, "SI Terninat ion. "
11M: IW.'IaID PCIl eN I Ni1Rl.CICR ~
Gew veri fi es all di 1ut i on pat hs
i sol at ed.
Gewchecks for reactIvIty
insert i on from uncont roll ed
cool doWl.
BCP closes the ~~ and Eo/pass
Val ves.
Gew checks for faulted SG
Gew checks <:EfCS less than 1200°F.
Gew veri fi es the react or is
subcri tical.
lS directs transition to 1-E-0. E-O steps
RO ver if i es react or t ripped.
BCP ver i f i es t ur bi ne tripped.
RO ver i f i es PC errer gency bus s es
energi zed.
m BCP check i f SI has act uat ed or
is required. ( '\'ffi)
BCP verifies feedvater i sol at ion:
- MR\S cl osed
- MRB\S cl os ed
- Mi n feed MM; cl osed
- St andby MP i n P1L
- Min feed punps tripped
- MP discharge ~ closed
- SGBD~ closed.
Gewverifies phase Aisolation:
- Mnually initiates Phase A
- I ni t i at es It t achrrent to ver i fy
i sol at ion.
BCP verifies aux feed punps
runni ng.
SIDm: 1 Page 20 Revision 0
E\ENf 8: a ven that the uni t is at pOYer, and a mi n st earn 1i ne break has
occurred and the reactor cannot be tripped either automtically nor mnually,
the cr ew WII be expect ed tor es pond i n accor dance v.i. t h 1- F.r 0, "Peact or Tri p
or Safet y I nj ect ion, " I-FR-S.l, "Pesponse to NIcl ear POYer Gner at i on! AIW, "
1- F.r 2, "Faulted StearnGnerator Isolation," and l-ES-1.1, "SI Ter IIi nat ion. "
TIM: E>>>OCIID ICI1 CN I NnRI.CI(R RFMRI<S
ROverifies charging purrps
runni ng.
B:P verifies low head purrps
runni ng.
B:P veri f i es all SWpurrps r unni ng.
G ew checks if mi n stearn i nes
shoul d be i sol at ed.
Gewverifies SI flow
B:P verifies aux feed flow
- RO checks Tave st abl e at or
trending to desired terrperature
and Alx. Feed flow i s adj us ted, if
requi red.
RO checks pr es s ur i zer PCR\S and
spray val ves.
- PCR\S cl osed
- Spray valves closed
- It leas tone PCRV block val ve
open.
RO checks RCP t rip and char gi ng
purrp recirc criteria:
Subcooling < 25°F. (l'q
Gew checks SG not faul ted. (l'q
lB di rect s trans i t i on t 0 1- E- 2.
B:P cl oses t he MiN and Bypas s If not done i n FR- S. 1 or using a
val ves. focused br i ef.
B:P checks pressure in all SQ;.
Gew i dent i fi es "1\' as faulted SG
NOTE: Crew may have already isolated
feed flow to the faulted generator using
a focused brief.
SID~ 1 Page 21 Pevision 0
E\fNf 8: G ven that the uni t is at pov.er, and a rrain stearnline break has
occurred and the reactor cannot be tripped either autorratically nor rranually,
the cr ew v.i 11 be expect ed tor es pond in accor dance v.i t h 1- B- 0, "React or Tri p
or Saf et y I nj ect ion, " 1- FR- S. 1, "Response to Nlcl ear Pov.er Gmerat i on!.tXIVS, "
1- B- 2, "Paul t ed St earn Gner at or I sol at ion," and 1- ES-1. 1, "SI Terni nat ion. "
TI~ EXPIDID JCIl CN I t-S'IRl.l:fCR ~
CT3 Crew isolates the faulted SG. Critical Task
- BCP verifies ~isolated. *Pr i or tot r ans i t i on out of E-2
- B:P closes' l-E'W,M}t lOOn
- BCP ver i f i es 1- FWMJI- 100A and
1- FWI-CV- 100A cl os ed.
- BCP ver i f i es "J\' SG P<:RV cl os ed.
- BCP veri fi es all SG bl OwloWl
t rip val ves cl osed.
- CI ew di spat ches an oper at or to
locally close I-M-18.
BCP checks B::ST 1evel .
BCP veri fi es IA est abl i shed to
cont ai mrent.
CIew checks secondary r adi at ion.
- RO reset s phase A
- RO reset s AM>IC (i f necessary)
- BOP checks secondary radiation
norrral.
CI ew checks if SI can be
t er ni nat ed. Cllii)
- Subcooling > 25°P
- PFWfl ow to i nt act SG> 340
gprnCR at least one i nt act SG
1evel >11%
- RCS pressure stable or
i ncreasi ng
- PRZR 1evel >21%
LS directs transition to 1- ES- 1. 1.
RO st ops all but one charging
punp.
SXJNC 1 Page 22 Revision 0
E\ENf 8: a ven that the uni t 1 S at pover, and a nain stearnline break has
occurred and the reactor cannot be tripped either autonatically nor nanually,
the cr ew w II be expect ed tor es pond in accor dance w t h 1- E- 0, "React or Tr i p
or Safety Injection," I-FR-S.l, "Response to N.1cl ear POYer Gmer at i onl tXIVS, "
1- E- 2, "Faulted StearnGnerator Isolation," and l-E)-1.1, "SI Ter ni nat ion. "
TIM: f>>lIOE) PCII CN 1~RBvfRI<S
crew t erni nat es SI:
- BCP verifies LHSI suctions from
sunp cl osed
- RO checks char gi ng punp r eci r c
fl ow pat h al i gned
- BCP cl oses BI T inlet val ves 1-
SI-MJl-.I867A and 1867B
- BCP cl oses BIT out I et val ves l-
SI - MJI-. 1867C and 1867D
- BCP ver i f i es al t er nat e SI
val ves cl os ed.
NOTE: The scenario may be terminated
after the crew terminates SI, or as
directed by the lead evaluator.
SIDNC 1 Page 23 Revision 0
PlOE1RE REv.
<::per at i ng Pr ocedur e 1- CP- 31. 1, " Min Feed\\.8ter Syst em" 42
<::per at i ng Pr ocedur e 1- CP- 2. 1, "lhi t St ar t up from Mde 2 t 0 Mde 86
I."
l-lmorrml Procedure l-A>-3, "lDss of \l tal Ins t r urrent at ion. " 22
AJnor rml Procedure l-A>-16, "I ncr eas i ng Pr i rmr y PI ant Leakage. " 25
AJnorrml Procedure l-A>-31, "lDs s of Mi n Feed\\.8t er. " 4
AJnorrml Procedure 1- A>- 38, "Excessive lDad Increase." 14
Funct i onal Fest or at i on Pr ocedur e 1- FR- S. 1, "Fesponse to NIcl ear 14
POVler ~ner at i onl ~. "
FIrer gency Pr ocedur e 1- E- 0, "Feact or Tr i p or Safet y I nj ect ion. " 36
FIrer gency Pr ocedur e 1- E- 2, "Faul t ed St earn ~ner at or Isolation. " 11
FIrer gency Pr ocedur e I-FS-1.1, "SI Term nat ion. " 18
St at i on lnnunci at or Fesponse Procedures. NA
Glide and Fef er ence Thcurrent PI - M 5000, "H1rmn Perforrmnce. " 1
IN'Q Gli del i ne for Tearrnork and Il agnost i c Ski 11 I£vel oprrent : Jan. 1988
~~~
IN'Q !CAD 07- 002 Si nul at or Tr ai ni ng Gli del i nes Jan. 2007
SID m:: 1 Page 24 Fevision 0
ATIIfiMNf 1 - SI M.l..ARR CPmtmR S CThfUIm PlURAM
ATIIfiMNf 2 - S<::EN6RI 0 PERF'rnMN::E CBJ IllI \ffi
ATI~ 3 - SIM.l..ARR PERF~ D\T.N)I-EEf (Uist page of scenario)
SID m::: 1 Page 25 Fevi si on 0
SID m: 1 Page 26 Revision 0
SIMULATOR OPERATOR'S COMPUTER PROGRAM
NRCl
Initial conditions
1. Recall Ie 161
2. Ensure Tave (555- 565), Tref, PDIT level, and \Cf I evel are sel ect ed on trend
recorders.
3. PI ace a wt nagnet on I-ffiRI-128.
4. Set D bank. to 155 steps in PCS.
5. l-CP-2.1 and l-CP-31.1 filled out to appropriate steps.
6. Reactivity plan available.
7. Rods i n nanual.
8. Rackout 2- CG P- lA and ver i fy 2- CC- P- IB is runm ng. a ose U2_CC_ll, U2_CC_4.
PRELOADS PRIOR TO SCENARIO START
CINIllCN Ml.Fl1OI eN ~ IFJ EIC
Let doWl r ad mmi t or Malfunction:
failure RMl207, Sever i t Y = - 1
Jut 0- st art fai I ure of Switch override:
l-CNP-IB (N)IB_~ = (W
Jut 0- star t f ai lure of Malfunctions:
1- FWP- 3P13B FVl601
FVl602
Fai I ure of rods to IIDve Malfunction:
in auto RDl4
Fai I ure of Jut 0 or Malfunctions:
Mnual React or Tr i p RrB2
RrB8
Remote function: RP
.AMl/C_IEFEtXr = 1RlE
SID m:: 1 Page 27 Revision 0
SCENARIO EVENTS
1) Start a ~purrp G ve appropri at e cues as "We and fi el doper at or.
~purrp suction flow; are available on Fxtrerre\1ew
2) lhi t r arrp G ve appr opr i at e cues as "We and f i el doper at or s.
3) Tr i p of "XI NOTE: If for some reason the crew starts l-CN-P-IB during
Cbndens at e purrplI RPI event 1, then delete CN0201 and change delay time on RD0121
fai 1ure to 5 seconds.
Malfunctions:
00201, Thl ay t i rre = 5, Tri gger = 3
RDOI2I, Thlay tirre = 185, Severity = -1, Trigger =3
NOTE: When sent to Condensate pumps, report that "B" is
running rme. Can see no nothing wrong with A" locally.
If sent to Condensate pump breaker, report that ISA4 has an
overcurrent drop on it.
NOTE: If I&C technicians are called about rod, can report
back that it is an IRPI problem. As they would be standing by
for IRPI adjustments during the ramp, this communication can
be given in a timely manner.
NOTE: The next event can occur once Condensate flow has
been re-established and tech specs have been reviewed.
4) Fai 1ure of 1- rn Ff- Malfunction:
1122 aD8, Thl ay t i rre = 5, Severi t y = 1, Rarrp = 10, Tri gger
=4
NOTE: If dispatched to look at valve, transmitter, etc, report
that everything looks normal.
NOTE: The next event can occur once charging has been
returned to normal, or as directed by the lead evaluator.
5) Fai 1ure of "N SG Malfunction:
GI II I st earn pressure ~1701, Thlay tirre = 5, Rarrp = 5, Severity = -1,
Tri gger = 5
NOTE: The next event can occur once Tech Specs have been
reviewed.
SID m:: 1 Page 28 Revision 0
6) Tube leak in non- Malfunction:
regen IK CHi 3, Th1 ay tim = 5, Ranp = 120, Severi t y = 50,
Tri gger = 6
NOTE: The next event can occur once letdown has been
isolated and preparations are being made to place excess
letdown in service. Do not close breaker for excess letdown
procedure until after next event initiated.
7) St earn 1eak out si de Malfunction:
cont ai rurent ~1001, Th1ay tim = 5, Ranp = 180, Severity = 2.5,
Tri gger = 7
NOTE: When operators have been dispatched, or three
minutes after crew has recognized the event, a call can be
made stating that there is steam coming out the door of the
Unit one main steam valve house.
NOTE: The next event can occur once reactor power has been
stabilized, or the unit has been tripped.
8) ~rn wt h A1V&' &>ds Malfunctions:
W11 not i ns ert i n aut 0 Update MSl00l t 0 a sever i t Y of 20 using trigger 8
Ch trigger screen set up trigger 8 as fo11o~:
INf ~1001 (0 5) 20 300
NOTE: Trigger 10 will open the RTBs TWO minutes after it
is inserted.
Remote functions:
SP_RfA_BKR = F, Th1 ay tim = 120, Tri gger = 10
SP_RIB_BKR = F, Th1 ay tim = 121, Tr i gger = 10
NOTE: Check SG pressure and decide if you could safely enter
MSVH at that time.
NOTE: The scenario may be terminated once the crew has
terminated safety injection, or at the direction of the lead
evaluator.
SIDNC 1 Page 29 Revision 0
ATIJ(}MNf 2
SCEN6RI 0 PERF~ CBJInI \ffi
SXim: 1 Page 30 Revi si on 0
SI MJ.Al(R RBJW..l FI CAlI (N ~NXIl(N
G ven equi prrent f ai 1ur es and oper at i onal sit uat ions, oper at e t he pI ant in
accor dance w t h Techni cal Speci f i cat ions t 0 br i ng the uni t t 0 a saf e
condition, using applicable procedures, and applying effective teaJlW)rk,
connuni cat i on, and di agnos tic ski 11 s.
A Drring shift operations the shift Inlnager wll take a conservative course
of act ion, es peci all y vhen uncer t ai n condi t ions exi s t, vhen deal i ng w t h
core cooling or heat sink availability, priInlry system and containrrent
integrity, and reactivity control associated wth plant evolutions.
R Drring shift operations the shift Inlnager wll provide overall crew
guidance by prioritizing and integrating the actions of the shift crewin
accor dance w t h adIIi ni st rat i ve pr ocedur es.
C Drri ng shi ft oper at ions each crew rrenber w 11 part i ci pat e ina team
effort that resolves conflicts, provides input into the teamdecision and
connunicates all the necessary inforInltion to enhance teaJlW)rk in
accor dance w t h adni ni s t rat i ve pr ocedur es.
D Drri ng shi ft oper at ions the Shi ft Techni cal Alvi sor w 11 independent 1y
assess events and based on those assessrrents nake reconnendations to the
crew regardi ng IIi t i gat i on st rat egy.
SXJr<<:: 1 Page 31 Revision 0
EVENT 1 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at appr oxi rmt el y 45% pover, the cr ew
v.i 11 star t a second Mi n FeedWlt er Punp in accor dance v.i t h
1-CP-31. 1, "Min FeedWlter System"
NORTH ANNA SPECIFIC TASKS:
R406 St art a st andby rmi n feedWlt er punp.
CRITICAL TASK:
NA
SID r<<: 1 Page 32 Revision 0
EVENT 2 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at appr oxi nnt el y 45% pover and the
crewhas been instructed to increase pover, the crewwll
r anp the uni t up i n accor dance w t h 1- CP- 2. 1, "lhi t St ar t up
from M>de 2 t 0 Mlde 1."
NORTH ANNA SPECIFIC TASKS:
Rl05 ill ut e t he ReS usi ng the bl ender.
CRITICAL TASK:
NA
SID m::: 1 Page 33 Revision 0
EVENT 3 PERFORMANCE OBJECTIVES
EVENT GOAL: a ven that the uni tis at pover and a Mi n Cbndens at e punp
has tripped ~th no auto-start of the standby punp, the crew
~ 11 be expect ed tor espond in accor dance ~ t h 1-.AP- 31, "LDss
of Min Feedvater."
NORTH ANNA SPECIFIC TASKS:
R781 Res pond to a los s of Il1li n f eedvat er.
S70 ~a1uate conp1iance ~th technical specifications.
CRITICAL TASK:
NA
SID m:: 1 Page 34 Revision 0
EVENT 4 PERFORMANCE OBJECTIVES
EVENT GOAL: a yen that t he char gi ng fl ow t r ansni tt er has f ai 1ed hi gh,
t he crew wI 1 respond in accordance wt h PR for e- C5
annunci at or
NORTH ANNA SPECIFIC TASKS:
Nme
CRITICAL TASK:
NA
SIDt<<: 1 Page 35 Revi sion 0
EVENT 5 PERFORMANCE OBJECTIVES
EVENT GOAL: a ven t he pI ant is in rmde one Wt hindi cat ions of a f ai I ed
stearnpressure transnitter, the crewwll respond in
accor dance w t h 1- AP- 3, "los s of Vi t al Ins t r UIrent at ion. "
NORTH ANNA SPECIFIC TASKS:
R526 Res pond to a stearn gener at or Wit er 1evel cont r 01 channel f ai lure.
S70 Evaluate conpliance wth technical specifications.
CRITICAL TASK:
NA
SIDm:: 1 Page 36 Revision 0
EVENT 6 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that there are indications of prinary plant leakage
due to a tube leak in the non-regenerative heat exchanger,
the cr ew \\i 11 take act ions in accor dance \\i t h 1- AP- 16,
"Increasing Prinary Plant Leakage."
NORTH ANNA SPECIFIC TASKS:
R520 Respond to i ncreasi ng pri nary-pI ant 1eakage.
CRITICAL TASK:
NA
SID me 1 Page 37 Revision 0
EVENT 7 PERFORMANCE OBJECTIVES
EVENT GOAL: G yen a stearn 1eak bet v.een a MnV and cont ai rurent, the cr ew
w. II res pond in accor dance w. t h 1- /JP- 38, "aces s i ve Load
Increase. "
NORTH ANNA SPECIFIC TASKS:
R539 Per for rn the i mredi at e oper at or act i 008 in res pons e to an exces si ve load
increase.
CRITICAL TASK:
NA
SXJr<<: 1 Page 38 Revi si on 0
EVENT 8 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that the unit is at po~r, and a rmin stearnline break
has occurred and the reactor cannot be tripped either
aut ormt i call y nor rmnuall y, the cr ew \\i 11 be expect ed to
res pond in accor dance \\i t h 1- E. 0, "React or Tr i p or Saf et y
I nj ect ion," 1- FR- S. 1, "Response to N.1cl ear Po~r
~ner at i on! ~," 1- E- 2, "Faul ted St earn ~ner at or
Isolation," and 1-ES-1. 1, "SI Terninat i on. "
NORTH ANNA SPECIFIC TASKS:
R224 Per for rn the i I'llredi at e oper at or act ions in response to a nucl ear po~r
gener at i on! ~.
R183 Identify and isolate a faulted stearngenerator.
R189 Terninate safety inj ection.
CRITICAL TASK:
See Follow ng Pages
SID m::: 1 Page 39 Revision °
cr St at errent :
Gewidentifies re.actor did not trip, transition to I-FR-S.l, ":Response
t 0 NIcl ear Pover elmer at i onl AlW," and take act ions t 0 br i ng the react or
subcri tical.
Safet y Si gni f i cance:
Fai 1ure to insert negat i ve react 1 VI t Y under t he post ul at ed pI ant
conditions results in an unnecessary situation in vhich the reactor
renains critical. Failure to insert negative reactivity constitutes
"IIi s - oper at i on or i ncorr ect cr ew per for nance vhi ch 1eads to i ncor r ect
react i vi t y cont rol. "
~l i d i ndi cat i on of a r equi red react or t rip by the pr es ence of a fir st
out annunci at or, wt h a f ai 1ur e of the react or tot rip aut onat i call y or
nanuall y from t he cont rol room
Perfornance Indicator:
ID insert s cont rol rods in nanual CR
IDplaces in-service boric acid transfer punp in fast speed AND
ID opens errer gency bor at e val ve 1- rn MN- 1350 CR
G ew di spat ches oper at or to 1ocall y t rip the react or us i ng at t achrrent ,
- Renvte :Reactor Trip.
Feedback:
- Cbntrol rods nvving in or fully inserted CR
- FIrer gency bor at i on fl ow i ndi cat ed
- ~utron flux decreasing.
- Pressuri zer pressure 1ess than 2335 psi g.
WD :Reference:
FR- S. 1 C- Backgr ound.
Cbndi t ions:
Prior to conpletion of step requiring its perfornance.
SXJm: 1 Page 40 :Revision 0
cr St at errent :
Gew st art saIl AfWpurrps.
Safety Significance:
Failure to start at least the nininumrequired nunber of AfWpurrps under
the pos t ul at ed pI ant condi t i ons can 1ead to vi 01 at i on of the R::s
errergency stress linit.
'Y.llid indication of a required reactor trip by the presence of a first
out annunci at or, w. t h a f ai 1ur e of the react or tot rip aut ormt i call y or
rmnuall y from t he cont r 01 room
Perforrmnce Indicator:
B:P pI aces at 1eas tone oot or dr i ven AfWpurrp cont r 01 s w. t ch to star t
Feedback:
Mni num AfWfl ow (680 gpn) i ndi cat ed to SO;.
WD &fer ence:
fR. S. 1 B- Backgr ound
Cbndi t ions:
Pr i or t 0 rreet i ng fR. H 1 cri t eri a
SIDNC 1 Page 41 Revision 0
cr St at errent :
crew i sol at es f aul t ed St earn Gner at or.
Safety Significance:
Failure to isolate a faulted SGthat can be isolated causes challenges to
the integrity CSF beyond those irreparably introduced by the postulated
condi t ions. For t he reference pI ant, nei t her of these t r ansi ent s
( bl Ov.dOWl of a s i ngl e SG v.i thor v.i t hout RCPs running) cons tit ut es an
or ange- pat h chall enge tot he i nt egr it Y CSF. lbv.ever, if the f aul t ed sa
is not i sol at ed, t he cool doWl t r ansi ent for react or vessel i nl et
t enper at ur e coul d result in an or ange- pat h chall enge tot he i nt egri t y
CSF, especi all y if RCPs are not runni ng.
- " I\.' SG i s depr es sur i zi ng in an uncont roll ed mmner or i s conpl et el y
depr es s ur i zed and
~l ve position and flow rate indication that N'W continues to be
delivered to the faulted sa
Perforrrance Indicator:
aP cl os es 1- FWMN- IOOD to secur e N'Wfl ow to" I\.' stearn gener at or.
Feedback:
N'Wfl ow i ndi cat i on to" I\.' st earn generat or decreases to zero.
'WD &ference:
E- 2 A Backgr ound.
Cbndi t ions:
Pc i or tot r ans i t i oni ng out of E- 2.
SID m:: 1 Page 42 &vision 0
Scenario Performance Datasheet
E\mf 1: a ven that the uni t is at approxi rmt el y 45% po\l.er, t he crew v.i II
st art a second Mi n Feedvat er Punp in accor dance v.i t h 1- CP- 31. 1, "Min
Feedvat er Sys t em "
SPD \er i fi ed: (I ni t i al s)
- 1- FWP-1C st art s and runs norrmlly
E\mf 2: a ven that the uni t is at appr oxi rmt el y 45% po\l.er and the cr ew has
been instructed to increase po\l.er, the cr ew v.i II ranp the unit up in
accor dance v.i t h 1- CP- 2. 1, "Thi t St art up from MJde 2 to MJde 1."
SPD \er i f i ed: (I ni t i al s)
- Reactor po\l.er increases
- Turbine po\l.er increases
- TavglTref increase
- CCnerator rregavatts increase
E\mf 3: a ven that the uni t i s at po\l.er and a Mi n Chndens at e punp has
tripped v.ith no auto-start of the standby punp, the crew wII be expected to
res pond in accor dance v.i t h 1- AP- 31, "Los s of Mi n Feedvat er. "
SPD \eri fi ed: (I ni t i al s)
- Innunci at or s G (1) and, I at er, G F6 i II uni nat e
- 1- CN P- lA has anber br eaker di s agr eerrent light lit
- 1- CN P- IB does not aut 0- st art
- Feed punp suction pressur~ decreases
- Aft er sever al ninutes: annunci at or sAm and .AF1 v.i II ill uni nat e
- I RPI for rod .& 2 i n Chnt r 01 Bank A v.i II drop to zero
- Rod &t t om li ght f or .& 2 v.i II ill uni nat e
E\mf 4: a ven that the char gi ng fl ow t r ansni t t er has f ai I ed hi gh, the crew
v.i II res pond in accor dance v.i t h AR for C- c:s annunci at or
SPD \eri fi ed: (I ni t i al s)
- Innunci at or C- c:s v.i 11 ill uni nat e
- I-ffiFI-1122 wII indicate full scale high
- 1- ffi FC\'- 1122 v.i II i ndi cat e ni ni num dermnd
- Lat er, C- ill rmy al arm i f 1- ffi FC\'-1122 not yet in rmnual and open.
Scenario Performance Datasheet
- E'VENf 5: G yen t he pI ant is in nvde one ~th indications of a failed stearn
pressure t ransni tt er, t he cr ew W11 respond in accordance ~th l-JiP-3, "lDss of
\i t al Inst rwrent at ion. "
SPD \eri fi ed: (I ni t i al s)
- Innunci at or s F- HI. and F- El ill um nat e
- St at us light s NO and N Il3 i 11 um nat e
- I-M-PI-1475 fails low
- I-M-Fl-1474 fails low
- "~' MRV r anps cl osed
- "1\' SG level decreases
- E'VENf 6: G yen that t here are i ndi cat ions of pri rmry pI ant 1eakage due t 0 a
tube 1eak in the non- r egener at i ve heat exchanger, the crew ~ 11 take act i ons
in accordance w t h 1- JiP- 16, "Increasi ng Pri rmry PI ant Leakage. "
SPD \eri fi ed: (I ni t i al s)
- Let doWl fl ow decreases
- \Cf level slow y decr eas es
- CC surge tank level slow y increases
- E'VENf 7: G yen a stearn 1eak bet v.een a M>1V and cont ai n.nent , the crew w11
res pond i n accor dance ~ t h 1- JiP- 38, "Excessive lDad Increase."
SPD \er i fi ed: (I ni t i al s)
- Mi n st earn pressure decreasi ng.
- Tave decreasing.
- Pov.er i ncr eas i ng.
E\mF 8: G yen that the unit is at pov.er, and a rmi n stearn line br eak has
occur r ed and the react or cannot be tripped either autormtically nor rmnually,
the crew ~ II be expect ed tor es pond in accor dance w t h 1- B- 0, "React or Tr i p
or Safet y I nj ect ion, " I-FR- S. 1, "Res pons e to NIcl ear Pov.er Gmer at i on! ~, "
1- B- 2, "Faul t ed St earn Gner at or Isol at ion," and l-:ES-l. 1, "SI Terni nat ion. "
SPD \eri fi ed: (I ni t i al s)
- Innunciators F-Fl, F-F2, F- F3 i 11 uni nat e
- "1\' stearn gener at or pr es s ur e decr eas es unt i I generat or is bloWl doWl
- The reactor does not trip autormtica1ly or rmnually
- Cbnt rol rods do not insert in auto
- ~ither nvtor-driven AFVVpunp auto-starts
SID m:: 1 Thte _ Revision 0
PLACING THE BLENDER IN THE ALTERNATE DILUTION MODE OF OPERATION 1-GOP-3,3.2
.,-" ... Rtrvision 5
D ....*lII9n CONTIN-UOUS U~5E Page 1 of1
North Anna Power Station
rliRI~f.. To JIl'Owdc!< il:!lwwtlau lnr f1bcias 1l1.. b .... dar ill Ihe <Ll:_.. <l1I,nioD mad;, of "~I:I.
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ANI} l'<<or ~~"'S ,st1!'lJ""red 1'0# INI'..nOnnIll.'l""",,fllll'l'rococbl'<l.
U MITATlO:'iS * l'"r lug.. d1k1liaas (> 100) pklas) mld:lo 1Il1_ IW9 distad di1tl1",m, Prior 10 mllkas 1l1.. ~ dikllla:l ....., lID ad"'PlJ<! lane ta m1D1"e proper mims Ibm (IblllEl IIDd
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I.. biI Ji:lI hI! IIl.iI lIlA hil IIlII lliil
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D:r.lo
PLACING THE BLENDER IN THE DILUTION MODE OF OPERATION 1-GOP-B,3,'I
,- R~vJ~Qn S
D9tnini9n CO,VTINUOUS USE Page 1 of '1
North Anna Power Station
r'lIRfJOSE. T.... pro.... do .mln:ldim. &... pba"S th" b....door 10 th" dlbli~ mo~ ,,£ <lpomlJm
INrnAI. <:ONUITtoNS !E L\:IiI 1 is D Moo" 3_ 4.~. or 6, THEN 1*1.DO-2A, ReS Mllb:ap I.Dg. Ius beom .,tlaJCld
PRU:'\UnONS Tomulimw Ill" m" "flll3 al'"'Jl<<~ RCS boron dlblh'J:!. ct"z1y mmllor bleQ(\<< 1lari", ~d lII:ld,orl'O {kiM>> ea51:1"O GlIl.llbe d1u1T<<1 fln_ llJ\! nlaialaiaed.
ANI) ~ dl<'dJ"S u reqai~ for lhe I'cmmnlll3c., (lftha pm:<<bre
UMn'AnONS. F<K brs" dlla1i,'IU (> 1000 ~"'OlI)mo.ke III , _ lwu dI...<:tdilclJOlU._ Prior t" mldias (b" -..end dllallm v.ui11lA lld<<qJ"\e lUll" I" ms~ prop<< mixiaStbtn nbhm llt:ld
1lI:l~:tlD It borm umple l<> coahcm e~ RtlUlts frol1llhe mt dilali:ln,
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Vtmiitld i reqml"il dl\'I!'.It;"8- CoattI.....,.., Till: 1"111al m,EN I)ER l~asu:re l'I",,,,,BJ.ENDER
P ........ liau S: LTDNlolbe JJ<GIlIllIioe fuue t.iU""4t 11 J>rq>er CONTJIDI_ Ph",e D1.J,,'NJJER J .ai-fev. I J 1M CONTROL
1.1lI1.lt.!IOa; em S4appel'l. Juxl "~ai*"de Of rorC"ummIJ'b::l1 SWlTCIiTo MODE :swrrcu In AtJTOli.:. SWlTCliT..
Revlltlw<<! mEN lXI4il)'HP PO M.d:eup Cmdrllau STOP 10DU.UrF. CI.OSED START
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l*ClI-U;V*1 me I<H*R;*JIJ4A SWITCH 19 JoMJWoIt IllAI)T()~ .Jt1Al)TO~ MOPI~ SW1TCH l-CIHCY-J 11M
A(.R~m A,Rcqs~ STI)P CLOSED CLOSED CLOSED InAVTO 10 AUTO & OPEN
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CONlROL Jlb.I;e
SV.1TCHT" '-Cn-Lev*]] IlC
START ~7.J
15li1 IQiI
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C<ltllp!de.i Uy: '"__". ._- ' _ P__ ClJ<<t; lly: . _ lk~iew<<l By' __, - * . " ,-"_
[:t'i<l(( "_ 1Al¢ DJiI¢; _
NUMBER ATTACHMENT TITLE ATTACHMENT
1-FR-S."1 2
VERIFYING APPLICABLE ACTIONS OF 1-E-O
REVISION PAGE
14 -lof5
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
NOTE: A previously-eompleted action does not have to be repeated, unless directed by the Unit SRO.
1. VERIFY BOTH AC EMERGENCY BUSSES - Do the following as directed by Unit
ENERGIZED SRO:
o a) IF no AC Emergency Bus is
energized, THEN immediately
restore power to at least one AC
Emergency Bus.
o .IE power cannot be restored, THEN
GO TO 1-ECA-O.O, LOSS OF ALL
AC POWER, Step 1.
o b) Try to restore power to
de-energized AC Emergency Bus
using O-AP-10, LOSS OF
ELECTRICAL POWER, as time
permits.
o Continue with Step 2.
NUMBER AITACHMENT TITLE ATTACHMENT
1-FR-S.1 2
VERIFYING APPLICABLE ACTIONS OF 1-E-O
REVISION PAGE
14 2 of 5
ACTION I EXPECTED RESPONSE RESPONSE NOT OBTAINED
2. CHECK SI STATUS:
a) Check if SI is actuated: a) Check if SI is reqUired as indicated
by any of the following:
o . Low-Head SI Pumps - RUNNING
o * Low PRZR pressure
o * Any SI First-Qut Annunciator - LIT
o . High Containment pressure
o . Steamline differential pressure
- High steamflow with either:
o . Lo-Lo Tave
o . Low steam pressure
o IF SI required, THEN GO TO
Step 2b.
o IF SI is NOT required, THEN
GO TO Step 9.
o b) As directed by unit SRO. manually actuate SI
NUMBER ATIACHMENT TITLE ATIACHMENT
1-FR-S.'1 2
VERIFYING APPLICABLE ACTIONS OF 1-E-O
REVISION PAGE
14 30f 5
rl STEP ACTIONI EXPECTED RESPONSE RESPONSE NOT OBTAINED ,
3. VERIFY FEEDWATER ISOLATION: 0 Perform Main Feedwater isolation as
determined by Unit SRO
0 * Main Feed Reg Valves - CLOSED
0 * Main Feed Reg Bypass Valves - CLOSED
0 * Main Feed MOVs - CLOSED
0 * Standby Main Feed Pumps in PTL
0 * Main Feed Pumps - TRIPPED
0 * Main Feed Pump Discharge MOVs -
CLOSED
0 * Steam Generator Blowdown Trip Valves -
CLOSED
4. VERIFY PHASE A ISOLATION~
0 a) Verify Panel "K"-H7, CONTAINMENT 0 a) As directed by Unit SRO, manually
ISOLATION PHASE A - LIT initiate Phase A Isolation.
0 b) Attachment 5, VERIFICATION OF PHASE A 0 b) Inform Unit SRO that Attachment 5
ISOLATION of l-E-O, REACTOR TRIP OR of 1-E-O shoUld be initiated as time
SAFETY INJECTION - PERFORMED and personnel availability pemlits.
5. VERIFY SI PUMPS - RUNNING: 0 As directed by Unit SRO, manually
start pumps.
0 * Charging Pumps - RUNNING
0 * Low-Head SI Pumps - RUNNING
6. VERIFY FOUR SERVICE WATER PUMPS - 0 As directed by Umt SRO, manually
RUNNING start pumps.
0 IF less than 4 Service Water Pumps
are running, THEN ensure Unit 2
Operator initiates O-AP-47, UNIT
OPERATION DURING OPPOSITE
UNIT EMERGENCY.
NUMBER ATTACHMENT TITLE ATTACHMENT
1-FR-S.1 2
VERIFYING APPLICABLE ACTIONS OF 'I-E-O
REVISION PAGE
14 40f5
-
ACTIONI EXPECTED RESPONSE RESPONSE NOT OBTAINED
7. CHECK IF MAIN STEAMLINES SHOULD BE
ISOLATED:
a) Check the following: o a) GO TO Step 9.
0 * Annunciator Panel "D" E-3 - LIT
0 * Containment pressure - HAS
EXCEEDED '18 PSIA
0 b) Verify MSTVs and Bypass Valves - CLOSED o b) As directed by Unit SRO, manually
close valves.
8. CHECK IF CDA IS REQUIRED:
0 a) Containment pressure - HAS EXCEEDED o a) GO TO step 9.
28 PSIA
0 b) Venfy Panel"K" H-6, CDA INITIATED - LIT o b) As directed by Unit SRO, manually
actuate CDA.
c) Verify CC Pumps - TRIPPED o c) As directed by Unit SRO. stop CC
Pumps.
0 * 'I-CC-P-'IA
0 * 1-CC-P-1B
0 d) Verify all RCPs - STOPPED o d) As directed by Unit SRO, stop all
RCPs.
e) Verify as Pumps - RUNNING o e) As directed by Unit SRO, manually
start QS Pumps.
0 * 'I-QS-P-1A
0 * 1-QS-P- 'IS
(STEP B CONTINUED ON NEXT PAGE)
NUMBER ATTACHMENT TITLE ATTACHMENT
'I-FR-S.1 2
VERIFYING APPLICABLE ACTIONS OF i-E-O
REVISION PAGE
'14 50f5
ACTION! EXPECTED RESPONSE RESPONSE NOT OBTAINED
8. CHECK IF CDA IS REQUIRED: (Continued)
f) Verify as Pump Discharge MOVs - OPEN o f) As directed by Unit SRO, manually
open valves.
o . 1-QS-MOV-101A
o . 1-QS-MOV-10iB
o g) On the Unit 1 Ventilation Panel, verify o g) Place switch in CLOSE.
1-5W-TV-10'IA&B SERVICE WATER
SUPPLY & RETURN TO RECIRC AIR FANS
- SWITCH IN CLOSE POSITION
o h) Verify ATTACHMENT 2, VERIFICATION OF o h) Inform Unit SRO that Attachment 2
PHASE B ISOLATION of 1-E-O, REACTOR of 1-E-O should be initiated as time
TRIP OR SAFETY INJECTION - and personnel availability permits.
PERFORMED
9. INFORM UNIT SRO THAT APPLICABLE
ACTIONS OF 'I-E-O HAVE BEEN VERIFIED
FOR 1-FR-5.1
- END-
Appendix D Scenario Outline Form ES*D-1
Facility: North Anna Scenario No.: 2 Op-Test No.: 1
Examiners: Mark Bates Operators:
Mark Riches
Initial Conditions: Unit at 100% power MOL. The letdown rad monitor is OOS and 1-FW-P-2 (terry turbine) was
just retumed to service last shift. 2-CC-P-1A is tagged out for seal work.
Tumover: Maintain 100% power and support maintenance on 2-CC-P-1A
Event Malt. No. Event Event
No. Type* Description
C (B) (S)
1 SW0104 SW pump trips
TS (S)
2 RD07 I (R) (S) Uncontrolled inward rod motion
R (R) (S) Loss of condenser vacuum due to loss of air ejector loop seal. Will need to
3 N (B) ramp unit back.
3a FW0801 I (B)(S) During ramp will lose error signal to "An MFRV
CH2201 C (R) (S) Running charging pump degrades, auto-start defeated on standby pump,
4 CH2101 TS (S) discharqe check valve will stick on degraded pump
5 RC04 TS (S) RCS leak
6 RC0101 M (All) SBLOCA (No auto Safety Injection. BIT inlets do not open automatically.)
7 SI08 I (All) Auto SI will not actuate when required
8 C (B) (S) BIT inlets will not open automatically
Scenario can be terminated after crew enters 1-E-1.
(Events 7 and 8 occur during event 6 and are numbered only for use on
Forms 301-5 and 301-6)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)a;or
IlMNCN
N:RIH Pl'N\ .PC:J.¥R STAn CN
IN 11 AL U CFNiID CPmATIR F)WdN\TI CN
SCEN\RI 0 m: 2
E\B'-U' IESCRI PIT CN
1. SWpunp t ri ps
2. Thcontrolled inWlrd rod IIDtion
3/3a. Los s of condens er vacuum llir i ng r anp w 11 1os e 1evel er r or signal
to" I\.' !\FRV
4. Running charging punp degrades, auto-start defeated on standby punp,
discharge check valve wll stick on degraded punp
5. ~ leak
6. SBLCD\.
Scenario Recapitulation:
~lfunctions after ECP 2 (Fai 1ure of aut 0 SI, BIT i nl et s do not open)
entry
Total ~lfunctions 8 (SWpunp trip, uncontrolled rod IIDt i on, loss of
condenser vacuuIij loss of level error signal to !\FR~
degradation of running charging punp/stuck open check
valve, ~ leak, SH...CD\ failure of auto SI, BIT
inlet s do not open)
Itlnor rml Event s 5 (SWpunp trip, uncontrolled rod IIDtion, loss of
condenser vacuuIij degradation of running charging
punp/stuck open check valve, ~ leak)
~j or Transients 1 (SII..CD\)
ECPs FIlt er ed 1 (E- 1)
ECP Cbntingencies o
Qi tical Tasks 6
90 Mnutes
SIDm: 2 Page 2 Revi si on 0
SIMULATOR EXAMINATION SCENARIO SUMMARY
SCENARIO NRC 2
The scenario begins v.i.th the unit at 100%pov.er. The letdoW! radiation
mmi t or i s i l l and t he t er r y t ur bi ne WiS ret ur ned t 0 s er vi ce 1as t shi ft . 2- cr:-
P- 1A i stagged out for seal rmi nt enance.
Ii t er the cr ew as surres t he Wit ch, the uni t 2 "I\' s er vi ce Wit er punp v.i. 11
trip resul t i ng ina loss of servi ce Wit er to "B' header. The crew shoul d
respond in accordance v.i. t h 1- AP-12, "loss of Servi ce vat er," and aft er checki ng
systemintegrity, start the unit 1 "B" SWpunp. liter the service Witer system
has been verified stable, the next event v.i.ll occur.
The next event v.i.ll be a failure of the autormtic rod control system
Cbnt rol rods v.i.ll st art insert i ng for no knoW! reason. The crew v.i.ll be
expected to performthe il'lIrediate operator actions of AP-1.1, "Cbntinuous
lhcont roll ed Rod Mt ion," and pI ace rod cont r 01 i n rmnual. Ii t er the cr ew
s t abi 1i zes the uni t and di r ect s I8C depar t rrent to i nves t i gat e, t he next event
v.i. 11 occur.
The cr ew shoul d i dent i f y an i ncr eas e i n Mi n Cbndens er pr es sure and ent er
1- AP- 14, "low Cbndens er '\hcuum" tor es pond tot he event. h di r ect ed by 1- AP-
14, the cr ew shoul d reduce rmi n t ur bi ne load unt i 1 rmi n condens er vacuum
st abi 1i zes . Drr i ng the r anp the "I\.' MRV v.i. 11 1os e its 1evel er r or signal. D.1e
tot hi s f ai 1ure t he val ve v.i.ll not aut ormt i call y cont rol 1evel at progr am
during transient conditions. \lien sent to investigate the vacuum loss, the
turbine building operator v.i.ll report that the "I\' Itr ijector loop seal is hot
tot he t ouch. If v.i. 11 be di r ect ed to i sol at e the loop seal. Glee t hi s has
been done, vacuum v.i.ll star t to i npr ove and the cr ew v.i.ll stop the r anp. \lien
the uni tis st abl e t he next event can occur.
~xt, the running charging punp, 1-GlP-1A v.i.1l degrade. The crewv.i.ll
star t anot her char gi ng punp. \lien the cr ew s ecur es t he degr aded punp its
discharge check val ve v.i.ll stick open. The crew should enter 1-AP-49, "loss of
N:>r rml Char gi ng." The cr ew v.i. 11 cl os e the "I\.' char gi ng punp di schar ge and
restore charging to norrm!. The crewv.i.ll then use AP-49 to reestablish
1et doW! and st abi 1i ze t he pI ant. The lhi t Super vi s or shoul d ref er t 0 Techni cal
Speci f i cat ions and decl ar e the "I\' char gi ng punp i noper abl e. D.1e to" C' punp
having no auto-start capability, and thus only being operable ~en running, the
cr ew v.i. 11 rmke pr epar at ions t 0 star t t hi s punp. Pi: t hi s poi nt t he next event
v.i. 11 occur.
The trans i ent on t he char gi ng s ys t em v.i. 11 caus e an ~ 1eak t 0 occur
i ns i de the cont ai nrrent . The cr ew shoul d res pond i n accor dance v.i. t h 1- AP- 16,
"Increasing Prirmry Plant Leakage." The l.S should refer to Technical
Speci f i cat ions and ei t her di r ect the cr ew t 0 COl'lIrence a uni t shut doW! or rmke
preparations for a containrrent entry due to excessive ~ leakage. Glce the
cr ew has comrenced ei t her a r anp or star t ed pr epar at ions f or a cont ai nrrent
SID NC 2 Page 3 Revi si on 0
ent r y, t he next event v.i. 11 occur.
The OCS leak v.i.ll v.orsen and the crewv.i.ll trip the reactor and enter 1-
&0, "Reactor Trip or Safety Inj ection." Safety inj ection v.i.ll fail to actuate
aut ormt i call y, but can be rmnuall y i ni t i at ed. The BI T inlet val ves v.i. 11 f ai 1
to open aut ormt i call y and v.i. 11 have to be rmnuall y opened. The crew v.i. 11 st op
the ~ and close the charging punp recirc valves. The crewv.i.ll transition
t 0 1- E- 1, "lDs s of React or or Secondar y Chol ant." O1ce the cr ew has per f or rred
sorre act ions in 1- E- 1, the scenar i 0 can be t erni nat ed.
SXi m:: 2 Page 4 Revision 0
~~Pre-iob Brief for Scenario NRC-2
A ~q-; ~
Unit Status: 'tp
Unit 1 is at 100% power, RCS boron is 978 ppm and core age is 9000 MWD/MTIJ. Aux
steam is on unit 1.
Unit 2 is at 100% power.
Equipment Status:
l-CH-RM-128, Letdown radiation monitor, is DOS. I-FW-P-2 was returned to service last
shift, PMT was SAT. 2-CC-P-IA is tagged out for seal maintenance. Maintenance rule
window is green.
Shift Orders:
Maintain current plant conditions and support maintenance on 2-CC-P-IA.
SCENAJUO TURNOVER SHEET
Read the following to the crew:
Purpose: Thi s exani nat i on i s i nt ended t 0 eval uat e the cr ew s per for rmnce of
various tasks associated wth the licensed cperator Training
Pr ogr am All act i vi ties shoul d be conpl et ed i n accor dance w t h
approved operations standards.
1. You are on a day shift during the veek.
2. 1\rough log should be rmintained to aid in rmking reports and to help during
briefs.
3. Respond to W1at you see. In the unlikely event that the sinulator fails
such that illogical indications result, the session wll be terninated and
the cr ew i nf or ned.
Unit Status:
lhi t 1 i s at 100% pover. K:S bor on i s 978 ppm and cor e age i s 9000 M'D'MU
lux steam i s on uni t 1.
lhi t 2 i s at 100% pover .
Equipment Status:
1- rn RM 128, Let doWl r adi at i on nvni t or, i s (lJ). 2- CC- P- 11\ i stagged out for
seal rmintenance. I-FWP-2 vas returned to service last shift, PM'vas SAl'.
Mi nt enance r ul e w ndow i s gr een.
Shift Orders:
Mi nt ai n cur rent pI ant condi t ions and s uppor t rmi nt enance on 2- CC- P- 11\
SID m.:: 2 Page 5 Revision 0
- E..'VfNI' 1: a ven the pI ant in node 1 and indications of a loss of one service
vater punp, the crew v.i 11 res pond i n accor dance v.i t h O-.AP- 12, "loss of Servi ce
Wter. "
11~ I EXPH.:IID ICII CN I N;1RlCfCR REM\RKS
SPD \er i fi ed: (I ni t i al s)
- Pnnunciators J - IB and J - ID ill urri nat e
- "B" SWheader pressure and flow decrease
B:P i dent i f i es annunci at or s J - I:B,
SWPP I-PIA 2- PIA PUIO 1RI P, and
J-ID, SERV WR REIlRN H:R ill Fl.ON
B:P i dent i f i es I ow fl ow condi t i on
on "B" SWheader.
B:P i dent i fi es uni t - 2 "P\.' SWpunp
t ri pped.
lS di rect s ent r y i nt 0 O-.AP- 12.
B:P checks SWreservoir level.
Q ew det er rri nes no fl oodi ng i s
i ndi cat ed.
Qewverifies SWheaders are
i nt act.
B:P verifies at I east one SWpunp
running on each header. (tq
B:P st art s "B" SWpunp.
B:P verifies ret urn header fl ow is
i ndi cat ed.
B:P verifies SWsyst em st abl e.
1S nakes notifications.
US references Technical Specification
3.7.8 and det errri nes that action
"P\.' appl i es, \'hi ch allow; 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> s
to veri fy SWthrot tied.
NOTE: The next event will occur after
the US refers to technical specifications,
or as directed by the lead evaluator.
SIDNC 2 Page 6 Revision 0
E\mI' 2: a ven that the uni t i soper at i ng at pov.er and cont r 01 rods are
i ns er t i ng f or no appar ent r eas on, t he cr ew w. II be expect ed tor es pond i n
accor dance w. t h 1- PE'- 1. 1, "Gmt i nuous lhcont roll ed FDd MIt ion. "
11I\E ~K1ID ICII <:N I NnRLITCR RIMRI i dent i f y no knOWl caus e of
rod insert ion.
lB di rect screw to ent er AP-1. 1.
CTI Crew takes action to stop rod Critical Task
motion and stabilize the unit. *Before Lo-Io insertion limits
- RO olaces rod control in MANUAL!
.00 verifies rod nvtion stopped.
00 veri fi es 1- RC- 11- 1408A i s
norrml.
CIewverifies control rods above
t he I 0- I 0 i ns er t i on I i IIi t.
00 checks RCS Tave w t hi n I i IIi t s
on at t achrrent 2 and adj us t s as
di r ect ed by t he lB.
00 checks PRZR pr es sure s t abl e or
t rendi ng to 2235 psi g.
00 checks PRZR level st abl e.
CI ew checks cont r 01 s r ods above
t he 1 0 i ns er t i on I i IIi t.
CIew rmi nt ai ns st abl e pI ant
condi t ions:
- Tave
- PRZR pressure
- PRZR level.
lB not i f i es 18C t 0 i nves t i gat e
failure.
The lB reports the failure to the
Wr k Cont r 01 Center and requests
that the reactivity rmnagerrent
adIIi n pr ocedur e be ref er enced,
appropriate notifications rmde,
and Wr k Reques t and Condition
Report be i ni t i at ed.
SXJNC 2 Page 7 Revision 0
E\ENf 2: a ven that the uni tis oper at i ng at pov.er and cont r 01 rods ar e
insert i ng for no apparent reason, t he crew v.i 11 be expect ed to respond in
accor dance v.i t h 1- Pl'- 1. 1, "Gmt i nuous Thcont roll ed Rod Mit ion. "
TI~ EXPOCIID ICIl CN I~REMtRRS
NOTE: The next event will occur after
the crew has stabilized the plant, or as
directed by the lead evaluator.
SID m:: 2 Page 8 Revision 0
E\ENf 3/3a: G ven that the uni t i s at pov.er and I os s of condens er vacuum i s
occurring, the crew wll respond in accordance w th l-AP-14, "Low Cbndens er
\acuum"
TIM: EJa>B:TID ICll CN I l'S'IRlCfCR ~
SPD \eri fi ed: (I ni t i al s)
- Cbndenser vacuum ror sens
- Pnnunci at or A GI. al arm; if vacuum reaches set poi nt
- Pnnunciator F-Fl alarm;
- 1\.' WRV wll not control in aut 0
It
NOTE: The following condenser vacuum
limitslsetpoints apply:
G-F3 (Vacuum pre-trip) < 25"HgV (-5"
HgA)
A-Gl (Loss of C-9) > 4"HgA
E-D2 (Turbine trip) 20"-23"HgV (6.9-
9.8"HgA) AND ASO pressure < 45 psig
Monitor> 5.5"HgA - Trip reactor
0' ew i dent i f i es ror s eni ng condens er
vacuum
lS di rect screw to ent er 1- AP- 14.
B:P r eIIDves t ur bi ne from val ve
pos i t i on 1i IIi t er , as r equi red.
B:P pI aces t ur bi ne cont r 01 in I M>-
IN
B:P COl'lIrences rnmual t urbi ne load
reduct ion.
lS di r ect sent r y i nt 0 ei t her l-CP-
2.2 or 1- AP- 2.2 vhi 1e cont i nui ng
w th l-AP-14.
- 0' ew IIDni t or s condens er vacuum
3.5" or 1ess.
B:P verifies condenser vacuum
br eaker cl os ed.
B:P verifies all condenser
~terboxes in service. (WS)
SIDNC 2 Page 9 Revision 0
~3/3a: a ven that the uni tis at poYer and 1os s of condens er vacuum i s
occurring, the crewwll respond in accordance wth l-AP-14, "LDw Cbndenser
'Vclcuum "
TI~ EXPB:IID ICII CN I l'S1RI.CKR ~
NOTE: During the ramp the BOP will Event3a
identify the failure of the" A" MFRV to
automatically control SG level at
program. Annunciator F-Fl will alarm
when level is +/-5 % from program. This
valve will need to be adjusted in manual
during the ramp.
- ElF ver if i es ai r ej ect or 1i neup.
- ElF verifies gl and steam
operat ion.
G ew di spat ches Wit chs t ander to
perf or m local act ions.
NOTE: When dispatched, the field
operator will isolate the loop seal per the
AP-14 attachment and then inform the
control room. At this time vacuum will
begin to improve.
RO cont rol s RCS t enper at ure w t h
b1 ender or cont r 01 rods.
G ew checks vacuum s t abl e or
i nprovi ng.
Gew checks condensat e and ci rc
Wit er syst em.
Gew veri fi es vacuum st ab1 e or
i nprovi ng.
Gew veri fi es rrain turbine on line
G ew checks caus e of vacuum 1os s
i dent i fi ed and repai red.
tB rrakes r epor t to V0rk Cbnt ro1
cent er and r eques t s that VR, CR,
and rranagenent notifications be
rrade.
NOTE: Once the crew has stabilized the
unit the next event can occur.
SID m::: 2 Page 10 Revi si on 0
E\tENf 4: Clven that the unit is at pover and there is a degradation of the
running char gi ng punp and a f ai I ed open di schar ge check val ve occur s vhen the
punp is secured, the crewwll respond in accordance wth l-AP-49, "loss of
Nlr nal Olar gi ng. "
TIM': EXPlDID JCII CN I~REMRKS
SPD \eri fi ed: (I ni t i al s)
- Olarging flowinitially decreases
- Olarging punp discharge pressure decreases
- Tenperature increases on I-SVVTI-I03A
- Innunci at or s C- Ri and C- (]j i II um nat e
- Innunci at or s C- 83, C-BS, and C- c:s ilIum nat e vhen "I\.' char gi ng punp is
stopped
- Olar gi ng fl ow goes t 0 zer 0 vhen "I\.' char gi ng punp is stopped
ROidentifies degrading conditions
on I-ffiP-IA
RO i dent i f i es annunci at or C- Ri,
ffi P- lA B- C llBE a L H 1HJ>.
NOTE: Report from the field will be
that l-CH-P-IA is making a lot of noise.
lS directs starting of I-ffiP-IB
or I-ffiP-IC
lS directs stopping of I-ffiP-IA
G ew i dent i f i es I os s of char gi ng
flow
NOTE: The crew may isolate letdown
based on AR instructions. If so, step 6
will restore letdown.
lS di rect screw to ent er 1- AP- 49.
G ew checks t he char gi ng punp that
vas started for gas binding. (!'Q
Gew i dent i fi es that a char gi ng
punp nanipulation has taken place.
CT2 Crew closes discharge MOVs for, Critical Task
the previousl~ running UlD'(J.
CtA")J
- l-CH-MOV-1286A
- l-CH-MOV-1287A
RO ver i f i es char gi ng condi t ions
ret urni ng to norrml.
SIDm:: 2 Page 11 Revision 0
E\ENf 4: Oven that the unit is at pover and there is a degradation of the
running charging punp and a failed open discharge check valve occurs ~en the
punp iss ecur ed, the cr ew w. 11 respond in accor dance w. t h 1-Jif'- 49, "lDss of
N>r nal Char gi ng. "
1l~ EXPlDID 1CII CN 11'S'IRLCfCR RaNU i dent i fi es char gi ng fl ow
i ncr eas i ng.
B:P i dent i f i es cont ai IlIrent sunp
1evel i ncr eas i ng.
(} ew i dent i f i es cont ai IlIrent
radiation levels are increasing.
l.B di r ect sent r y i nt 0 1- liP- 16 and
l-liP-5.
(}ew ver i fi es uni t in rrode 1. AP-16
K> ver if i es pri mr y par arret er s
under oper at or cont r 01 .
NOTE: Crew may isolate letdown at this
time.
K> checks l..C\'- 1115A not di vert ed.
K>verifies letdoWl in service
w th norml i ndi cat ions.
K> checks exces s 1et doWl
par arret er s .
K> checks char gi ng s ys t em
pararreters norml.
B:P checks Auxiliary Building sunp
1evel norml.
(} ew checks cont ai IlIrent
condi t ions.
(}ew i dent i fi es i ncreasi ng
cont ai IlIrent radiation and sunp
purrpi ng rat e.
SIDNC 2 Page 13 Revision 0
E\ENf 5: a ven that the uni tis at pover and an K:s 1eak has developed, the
crew wll be expect ed tor es pond in accor dance w t h 1- /JP- 16, "Pri tmry PI ant
Leakage. "
TI~ :EXPRAID ICII CN I~REMRI<S
US references Technical Specification
3.4. 13A - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to rest ore
1eakage tow t hi n I i IIi t S (or w 11
have to shut doWl per Chndi t i on B).
lS di r ect s cr ew t 0 ei t her comrence
a unit shutdoWl or tmke
pr epar at ions f or a cont ai rurent
entry.
lS tmkes report to V0rk Chntrol
cent er and r eques t s CR and
tmnageIrent not i f i cat ions.
fealth Physics departIrent is AP-5 steps for l-RM-RMS-l60 alarm
i nf or Ired of t he hi gh r eadi ng on 1-
RMRM- 160 and asked tot ake
cont ai rurent gaseous and part i cuI at e
sanpl es, if required.
A pr i tmr y leak rat e cal cuI at i on i s
i ni t i at ed.
IF i s r eques ted tot ake cont ai rurent
sunp sanpl es.
NOTE: The next event will occur after
the crew either makes preparations to
ramp, makes preparations for a
containment entry, or as directed by the
lead evaluator.
SIDm: 2 Page 14 Revision 0
E\ENf 6: a ven that the uni tis at pover and a I..!rA has occurred, the crew
v.i II res pond i n accor dance v.i t h 1- E- 0, "React or Tri p or Safet y Inj ect ion, "
and 1- E-l, "LDs s of React or or. Secondar y Cbol ant. "
1Ir-.E EXPK1ID ICII CN I:t'S1Rl.CfCR RfMRKS
SPD \eri fi ed: (I ni t i al s)
- Pressuri zer 1evel and pressure rapidly decrease
- Cont ai IlIrent pressure slowy increases
- SI does not aut OImt i call y act uat e, if requi red
- BI T i nl et val ves do not open autonatically
00 i dent i fi es P.RZR pressure and
1evel r api dl y decr eas i ng.
lE di rect screw to ent er 1- E-O.
CI ew nanuall y t rips the react or .
llP ver i f i es t ur bi ne t rip.
00 veri fi es PC e~rgency busses
energi zed.
CIew checks if saf et y i nj ect i on has
act uated, or should have actuated.
NOTE: An SI will be required on low
pressurizer pressure (1780 psig). The
crew may manually ini~SI before an
auto si~al is 2enerated.
CT3 Crew manually actuates SI prior to Critical Task
exiting 1-E-O: SI will not automatically actuate.
- ROtBOP manually actuate SIJ
BOP verifies feedvater isolation:
- M'R~ closed
- MRB~ closed
- ~in feed ~ closed
- St andby MP i n fYIL
- ~in feed punps tripped
- MP discharge ~ closed
m BOP nanuall y i ni t i at e phase A
isolation.
BOP verifies AFVVpunps running.
NOTE: Crew may have previously held
a focused briefed and started 1-CH-P-
1C.
SID m::: 2 Page 15 Revision 0
afNI' 6: G ven that the uni t i s at pOYer and a L<rA has occurred, the crew
vi 11 res pond i n accor dance vi t h 1- & 0, "React or Tri p or Safet y I nj ect ion, "
and 1-&1, "IDs s of React or or Secondar y (hoI ant. "
1I~ EXPlnID ICIT CN I Ni'IRl.[1(R ~
0" ew ver if i es SI punps r unni ng.
(tq
O"ew st art s 1-GlP-1C
ff:P verifies all SWpunps running.
(tq
O"ew di rect s lhi t 2 to enter O-Jil-
47.
0" ew checks if M> shoul d be
i sol at ed. (YES)
O"ew veri fi es/ cl oses M>I\S.
- O"ew checks if CD\. requi red. (tq
NOTE: The following is a continuous
action step and actions will be
performed when containment pressure
has exceeded 20 psia.
- 0" ew checks if Q) is r equi red.
O"ewrmnually starts Q):
- Q) discharge valves are
opened
- Q) punps are started
- ~ outlet valves are opened
NOTE: Crew may have aligned BIT
using CAP #2 which states: IF SI is
actuated AND High-Head Cold Leg SI
flow in NOT indicated, THEN initiate
attachment 6.
O"ewverifies SI flow (tq
lB di r ect s i ni t i at i on of
at t achrrent 6.
NOTE: Attachment 6 and Continuous
Action Page are attached to back of
scenario.
SIDm: 2 Page 16 Revision 0
~6: a ven that the uni t is at pov.er and a UTA has occurred, the crew
wll respond in accordance wth 1-&0, "Reactor Trip or Safet y I nj ect ion, "
and 1-&1, "lDss of React or or Secondary Cbol ant. "
11M: EXPIDED 1CII CN I:N)1RI.CI(R ~
CT4 Crew manually aligns the BIT Critical Task
prior to exiting E-O: Attachment 6 steps
- 00 ver i f i es char gi ng punp
Ii ne- up
- B:P verifies BIT reci rc val ves
cl osed.
- B:P verifies BIT out I et valves
oeen.
- BOpimanually OP1.PAJ-sI*M;~
1867A OR 1867B.
BOP verifies AFVVflow
- 00 checks RCS Tave st abl e at or
t rendi ng to requi red t enper at ure.
BOP adj us t s AFVVfl o~ if required.
00 checks PRZR PCR\S and s pr ay
val ves.
NOTE: The RCPs may have already
been stopped using CAP #3.
CT5 Crew stops all RCPs during a Critical Task
00 checks RCS s ubcool i ng <25°F
[85°F] .
Crew checks at least one chargingJ~um~
running and flowing to the RCS_
NOTE: Crew may have already closed
HHSI pump recircs per Cap #4.
CT6 Crew takes action to prevent HHSI Critical Task
NAF-~1+04-~
pump ronout.
00 checks RCS pressure < 1275. psi g
~
ET (Lw"rz/
[1475 psig]. ~ c.~ Yv"1 ~ ~ ~ 1=i().J
ROIBOP closes cbarging,pump recirc
vah:~ vlv-.:J!-'..s \M.ov- CH- 12 7SA, 8/ C-
~\C. [~ CrtfttlCt
BOP checks SO; not faulted. (YES)
BOP checks SO; not rupt ured. (YES)
Qew checks if RCS is i nt act
i ns i de cont ai mrent . (~
SIDm: 2 Page 17 Revision 0
E\ENf 6: a ven that the uni tis at poVler and a urA has occurred, the crew
v.i II res pond i n accor dance v.i t h 1- & 0, "React or Tri p or Safet y Inj ect ion, "
and 1-&1, "lDss of React or or Secondary Cbol ant. "
1I~ EXPECIFD ICIl CN I N)1RlCIffi. REMRKS
l.B di r ect s cr ew tot r ans i t i on to I-
E-I.
RO checks RCP t rip and char gi ng
punp recirc criteria.
B::P checks SO; not f aul ted. (YES)
B::P checks i nt act SG level s.
0- ew checks secondar y r adi at ion:
- o-ewverifies IAtrip valves
open
- RO res et s AMiJ;(:
- 0- ew checks SG Bl OvdOWl, Ag
Mi n st earn i ne, and terry
turbine exhaust radiation
ooni t or s nor rml
- B::P checks SG level s
- 0- ew i ni t i at es at t achrrent to
pi ace ED r ad ooni t or sin
servi ce
- B::P opens SG surf ace s anpl e
trip valves and inforIT5
cheni stry.
NOTE: The scenario may be terminated
after the crew checks secondary
radiation, or as directed by the lead
evaluator.
SXJm= 2 Page 18 Revision 0
PRa:ID..RE REv.
Jlbnorrml Procedure 0- AP- 12, "LDss of Servi ce Wt er. " 33
Jlbnorrml Procedure 1- AP- 1. 1, "Gmt i nuous lhcontrolled Rod MIt ion. " 8
Jlbnorrml Procedure l-AP-13, "LDs s of Ole or MIre a rcul at i ng Wt er 13
Punps. "
Jlbnorrml Procedure 1- AP-14, "LDw Gmdens er vacuum" 20
Jlbnorrml Procedure l-AP-49, "LDs s of ~r rml Chargi ng. " 14
Jlbnorrml Procedure 1- AP- 16, "Increasi ng Pri rmry PI ant Leakage. " 24
Jlbnorrml Procedure l-AP-5, "lhi t 1 Radi at i on MIni t or i ng Sys tern" 26
FIrer gency Pr ocedur e 1- E- 0, "Reactor Tri p or Safet y I nj ect ion. " 36
FIrer gency Pr ocedur e 1-8-1, "LDss of Reactor or Secondar y (bol ant. " 22
St at i on ltmunci at or Response Procedures. NA
Chide and Ref er ence Thcurrent PI-M5000, "HIrmn Perforrmnce. " 1
INlQ Chideline for Tearrnork and n agnost i c Skill Thvel oprrent : Jan. 1988
INlQ ACAD07-002 Sinulator Training Chidelines Jan. 2007
SIDm: 2 Page 19 Revision 0
ATIIG-MNT 1 - SI MI.A1tR 0'ERA1tR S cr:M>UIFR PIURAM
ATIIG-MNT 2 - Sc:EN6RI 0 PERFCRMN:E CBT ffTI \ffi
ATIIG-MNT 3 - SI MI.A1tR PFRFCRMl'lE OO'~HEf (las t page of s cenar i 0)
SID m::: 2 Page 20 Revision 0
ATIKlMNf 1
SI MIA1(R CPFRATCR S cr:MUIffi PlURAI\1
SID m:: 2 Page 21 Revision 0
SIMULATOR OPERATOR'S COMPUTER PROGRAM
SXGNRC2
Initial conditions
1. Recall Ie 162
2. Ensure Tave, Tref, PDIT level, and \Cf level are selected on trend
recorders.
3. PI ace VR rmgnet on 1- ffi RI - 128.
4. Rackout 2- cr-P-IA and veri fy 2- CGP-IB is runni ng. a ose m_cr_4, m-cr_l1.
PRELOADS PRIOR TO SCENARIO START
a:Nl1I<N Ml.FlN:TI CN ~ IFf EIC
letdo~ ~failure Malfunction:
RMl207, Sever i t Y = - 1
Fai 1ur e of BI T inlet s Switch Override (SI): (¥eeps val ves from openi ng on SI)
to open on SI ~67 A_a...c:BE::CN
~67B_a...c:BE::CN
Set up so t hat val ves w 11 open vhen CPEN but t on
pressed:
Set up t rigger 10 as follow;
~67A_CPE"{1)=1 (you need the (1) for t hi s val ve
onl y)
IIR ~67A_a...c:BE
Set up trigger 11 as follow;
~67B_CPEN=1
IIR ~67B_a...c:BE
Fai 1ure of aut 0 SI Malfunction:
SI08
I-ffiP-IB wll not Switch Override:
aut 0- st art ClPIB_~TP = CFF
SID m:: 2 Page 22 Revi si on 0
SCENARIO EVENTS
1) Loss of servi ce Malfunction:
vater SWO 104, Trigger = 1
NOTE: When sent to pump can report that 2-SW-P-IA looks
normal and I-SW-P-IB is running normally.
NOTE: When sent to breaker for 2-SW-P-IA (2SHS) can
report an overcurrent trip.
NOTE: The next event will occur after the US refers to
technical specifications, or as directed by the lead evaluator.
2) Rod Insertion. Malfunction:
RUn, Iel ay t i Ire = 5, Tri gger =2
NOTE: The next event will occur after the crew has stabilized
the plant, or as directed by the lead evaluator.
3) Loss of Cbndenser Malfunction:
\acuurn (N090l, Ielay tiIre = 5, Ranp = 120, Severity = 100,
Fai I ure of level si gnal Tri gger = 3
to "1\.' MRV
NOTE: When sent to perform attachment, verify that enough
of a ramp has occurred, then close I-VP-21 either on
ExtremeView or a monitor screen. (If no one dispatched with
attachment in hand, than initially report the loop seal is hot
and get direction to isolate.)
Malfunction:
FV0801, Iel ay t i Ire = 5, Tri gger =3
NOTE: Allow the crew to stabilize the unit before proceeding
with next event, or as directed by the Lead Evaluator.
SXJ m:: 2 Page 23 Revision 0
4) ~gradation of l-Cll Malfunctions:
P- lA v.i t h check val ve GQ20l, ~l ay t i rre = 5, Ranp = 120, Sever it y = 50,
fai I ure Tri gger =4
GQlOl, ~l ay t i rre = 5, Tr i gger =4
NOTE: If operator sent to l-CH-P-IA, can report that it is
making a lot of noise. If asked, can also report that I-SW-
TCV-I02A is full open.
NOTE: If asked to check on l-CH-P-IB (C), can report that the
pump appears to running satisfactorily, with no seal leakage.
NOTE: Once the US has referred to Tech Specs or as directed
by the Lead Evaluator, the next event will occur.
5) K:S leak Malfunction:
OCD4, ~l ay t i rre = 5, Ranp = 300, Severi t y = 10,
Tri gger = 5
(Thv.brtot -20754)
NOTE: If asked about whether to ramp or make containment
entry, ask for recommendation. Can either agree with US, or
say you will get back with them.)
NOTE: The next event will occur after the crew either makes
preparations to ramp, makes preparations for a containment
entry, or as directed by the lead evaluator.
6) SIUX'A Malfunction:
ReDlOl, ~lay tirre = 5, Ranp = 30, Severity = 0.3,
Tri gger =6
NOTE: The scenario may be terminated after the crew checks
secondary radiation, or as directed by the lead evaluator.
SID t<<: 2 Page 24 Revision °
ATIKlMNf 2
SCFN6RI 0 PffiFCRMN::E CBTffTI \ffi
SID m:: 2 Page 25 Revision 0
SI MIArCR RIQ.Wl H OOI CN ~N\11 CN
G ven equi prrent f ai 1ur es and oper at i onal sit uat ions, oper at e t he pI ant i n
accor dance v.i. t h Techni cal Speci f i cat ions to br i ng the uni t t 0 a s af e
condition, using applicable procedures, and applying effective tea~rk,
connuni cat i on, and diagnostic skills.
CE1'ffiI C PmFCRMN::E CBJ H:TI YES
A Drr i ng shi ft oper at ions the shi ft mmager v.i.ll take a conservat i ve cour se
of act ion, es peci all y vhen uncer t ai n condi t ions exi s t, vhen deal i ng v.i. t h
cor e cool i ng or heat sink avai 1abi 1it y, pri l11lr y sys t em and cont ai nrrent
integrity, and reactivity control associated v.i.th plant evolutions.
R Drr i ng shi f toper at ions the shi ft l11lnager v.i. 11 pr ovi de over all cr ew
guidance by prioritizing and integrating the actions of the shift crewin
accor dance v.i. t h adni ni st r at i ve pr ocedur es .
C Drr i ng shi ft oper at ions each cr ew rrenber v.i.ll par t i ci pat e ina team
effort that resol ves conflicts, provides input into the tearndecision and
connunicates all the necessary inforl11ltion to enhance tea~rk in
accor dance v.i. t h adni ni st rat i ve pr ocedur es .
D Drr i ng shi ft oper at ions the Shi ft Techni cal Mvi sor v.i.ll independent 1y
assess events and based on those assessrrents l11lke reco~ndations to the
crew regardi ng ni t i gat i on st rat egy.
SID m:: 2 Page 26 Revision 0
EVENT 1 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven the pI ant in rmde 1 and i ndi cat ions of a loss of one
s er vi ce Wlt er punp, the cr ew W11 res pond in accor dance W t h
0-.t\P- 12, "Los s of Ser vi ce Wt er . "
NORTH ANNA SPECIFIC TASKS:
R653 Respond to a loss of a service Wlter punp.
S70 ~aluate conpliance wth technical specifications.
CRITICAL TASK:
NA
SID m::: 2 Page 27 Revision 0
EVENT 2 PERFORMANCE OBJECTIVES
EVENT GOAL: a ven that the uni tis oper at i ng at pover and cont r 01 rods
are inserting for no apparent reason, the crewwll be
expect ed tor es pond in accor dance w t h 1- PI'- 1. 1, "Gmt i nuous
lhcontrolled Rod Mtion."
NORTH ANNA SPECIFIC TASKS:
R:1-74 Restore stable plant conditions followng continuous uncontrolled rod
rmt ion.
S70 Eval uat e conpl i ance w t h t echni cal speci f i cat ions.
CRITICAL TASK:
See next page
S)G~2 Page 28 Revision 0
cr St at errent :
Gewtakes action in accordance wth PI'-1.1, to stop rod IIDtion and
stabilize the unit.
Safety Significance:
Cbre reactivity is not under control of the operator due to the failed
cont r 01 channel. "I tis expect ed that the oper at or W11 at t enpt tot ake
rrnnual actions to correct for anorrnlous conditions during pover
oper at ion. "
Cbnt i nuous i nvard cont rol rod IIDt i on w t h TAVE and TREF rrnt ched.
Perforrrnnce Indicator:
00 pI aces rod cont r 01 to rrnnual.
Feedback:
Rod IIDtion stops
WD Reference:
Nme
Cbndi t ions:
Pr i or to cont r 01 rod 10-1 0 i ns er t i on 1i ni t.
SIDNC 2 Page 29 Revision 0
EVENT 3 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at pover and 1os s of condens er vacuum
i s occur ring, the cr ew W11 res pond i n accor dance w t h 1- /iP-
14, "lDw Cbndenser \acuum"
NORTH ANNA SPECIFIC TASKS:
R517 Perform the imrediate operator actions in response to a loss of one or
nDre circulating vater purrps.
R518 Respond to a partial loss of condenser vacuum
CRITICAL TASK:
NA
SXJ m:: 2 Page 30 Revision 0
EVENT 4 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that the unit is at pover and there is a degradation
of the running charging punp and a failed open discharge
check val ve occur s \\hen the punp iss ecur ed, the cr ew v.i 11
res pond i n accor dance v.i t h 1- AP- 49, "Los s of Nlr rml
Chargi ng. "
NORTH ANNA SPECIFIC TASKS:
R704 Respond to a loss of norrml charging.
S70 Eval uat e conpl i ance v.i t h t echni cal speci f i cat ions.
CRITICAL TASK:
See next page
S)(}~ 2 Page 31 Revision 0
cr St at errent :
(} ew takes act i on to pr event char gi ng punp r un- out due to a stuck open
discharge check valve on a non-running charging punp.
Safety Significance:
Fai I ur e to pr event char gi ng punp r un- out cons tit ut es a "ni s - oper at i on or
incorrect crewperforrnmce ffiich leads to degraded HIS capacity."
- Indication/annunciation that one charging punp has tripped or been
shutdo~ ~th a stuck open discharge check valve.
- H gh anps on the r unni ng char gi ng punp.
- Low' no char gi ng fl ow or seal i nj ect i on i ndi cat ed.
Perfornance Indicator:
(}ewcloses charging punp discharge ~ on the previously running
char gi ng punp.
Feedback:
Ilscharge ~ for the previously running punp indicate closed and
char gi ng and seal i nj ect i on fl ow ret ur ns to nor nal.
VITi Ref er ence:
Nme.
Cbndi t ions:
Pr i or to Saf et y I nj ect i on bei ng r equi red by degr aded pI ant condi t ions.
SID m::: 2 Page 32 Revision 0
EVENT 5 PERFORMANCE OB,IECTIVES
EVENT GOAL: G ven that the uni tis at pover and an K:s 1eak has
developed, the cr ew w 11 be expect ed tor es pond i n accor dance
wth l-.AP-16, "Prinary Plant Leakage."
NORTH ANNA SPECIFIC TASKS:
R520 Respond to increasing prinary-plant leakage.
S70 ENaluate conpliance wth technical specifications.
CRITICAL TASK:
NA
SID m:: 2 Page 33 Revision 0
EVENT 6 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at pOYer and a LCl)\ has occur red, the
creww.ll respond in accordance w.th I-EO, "Reactor Trip or
Saf et y I nj ect ion," and 1- E- 1, "Los s of React or or Secondar y
Cbol ant. "
NORTH ANNA SPECIFIC TASKS:
RI85 Perform the imrediate operator actions in response to a reactor trip or
s af et y i nj ect ion.
RI84 Restore the HowloWl radiation mmitors.
R730 \er i f Y s af et y i nj ect i on fl ow
CRITICAL TASK:
See FolloW. ng Pages
SIDNC 2 Page 34 Revision °
cr St at errent :
CI ew mmuall y i ni t i at es s af et y i nj ect ion.
Safety Significance:
Fai lure to mmuall y act uat e SI under the pos t ul at ed condi t ions
constitutes "llis-operation or incorrect crew perforrmnce that leads to
degr aded HIS capaci t y. "
I ndi cat i oni annunci at i on that SI i s r equi red, w. t h N) i ndi cat i on that SI
has act uat ed.
Perforrmnce Indicator:
ID:ocP rmnuall y act uat es s af et y i nj ect ion.
Feedback:
I ndi cat i oni annunci at i on that SI has act uat ed.
WD Reference:
E- 0 D &ckgr ound.
Cbndi t ions:
Pr i or tot r ans i t i oni ng out of E- O.
SID m::: 2 Page 35 Revision 0
cr St at errent :
G ew al i gns Char gi ng punps.
Safet y Si gill f i cance:
Failure to mmually establish flow from at least one HEI punp
cons tit ut es "ni s- oper at i on or i ncor r ect cr ew per for rmnce v.hi ch leads to
degr aded HIS... capaci t y. "
I ndi cat i on! annunci at i on that SI is in pr ogr es s v.i t h no HEI fl ow
i ndi cat ed.
Perforrmnce Indicator:
00 rmnuall y opens 1- SI - MN- 1867A CR 1867B
Feedback:
HEI fl ow tot he col d legs i s i ndi cat ed.
WG Reference:
E- 0 I - Backgr ound.
Cbndi t ions:
Pr i or tot r ans i t i oni ng out of E- O.
SID m:: 2 Page 36 Revision 0
cr St at errent :
Q ew stops React or Cbol ant Punps.
Safety Significance:
Tr i ppi ng KPS at t hi s t i rre "pr event s exces s i ve depl et i on of OCS Wit er
invent ory through a srmll break in the OCS WIi ch IIi ght 1ead to severe
core uncovery if the ~ vere tripped for sorre reason later in the
accident." The ~ should be tripped "before OCS inventory is depleted
tot he poi nt WIer e t r i ppi ng the punps \'Dul d caus e the br eak t 0
i ~di at el y uncover. "
Indi cat i on of:
- Subcool i ng 1es s t han 25°F [85°F].
- It 1eas t one char gi ng punp r unni ng and fl ow ng tot he OCS.
Perforrmnce Indicator:
RCY ffP pI aces cont r 01 s w t ch( es) for all r unni ng ~ in srrP.
Feedback:
Indication/annunciation of no ~ running.
WD Reference:
ReP Tr i pi Res t ar t Backgr ound Il>current.
Cbnditions:
Prior to conpleting the step directing its perfornance.
SID m::: 2 Page 37 Revision 0
cr St at errent :
G ew takes act i on t 0 pr event HEI punp r unout .
Sat et y Si gill t i cance:
Failure to prevent HEI punp runout constitutes a "nis-operation or
incorrect crew performmce vhi ch leads to degraded HIS capaci t y. "
- Indication/annunciation that SI is actuated and is required and
- Indication of RCS pressure less than 1275 psig [1475 psig] and
- RCPs tripped
Perfornance Indicator:
00 cl os es char gi ng punp r eci r c val ves:
- 1- rn MN- 1275A
- 1- rn MN- 1275B
- 1- rn MN- 1275C
Feedback:
Charging punp recirc valves indicate closed.
WD Reference:
Nme.
Cbndi t ions:
Prior to RCS pressure reaching 1000 psig CR conpletion of transfer to
recirculation nDde, vhichever corres first.
SIDm: 2 Page 38 Revision 0
.r
Scenario Performance Datasheet
E\ifNf 1: a yen the pi ant in IIDde 1 and i ndi cat ions of a loss of one servi ce
Witer punp, the crew wll res pond i n accor dance w t h O-.PP- 12, "loss of Service
Viter. "
SPD \eri fi ed: (I ni t i al s)
- Pnnunci at or s J - I:B and J - ill i II um nat e
- " H" SWheader pressure and flow decrease
E\ifNf 2: G yen that t he uni t i soper at i ng at pover and cont r 01 rods are
insert i ng for no apparent reason, t he crew v.i II be expect ed tor es pond i n
accordance w th 1-.PP-1. 1, "Gmt i nuous Thcont roll ed Rod Mit ion. "
SPD \er i fi ed: (I ni t i al s)
- Rods step in at rmxi mun speed
E\ifNf 3: G yen that the uni t is at pover and loss of condenser vacuwnis
occurri ng, the cr ew v.i 11 res pond i n accor dance w th 1-.PP-14, "low Chndenser
\hcuum"
SPD \eri fi ed: (I ni t i al s)
- Chndens er vacuum W>r s ens
- Pnnunciator AGl alarm if vacuumreaches set poi nt
- Pnnunci at or F- F1 al ar m
- "I'\..' MRV wll not cont rol in aut 0 .
E\ifNf 4: a yen that the uni t is at pover and t her e i s a degr adat i on of the
running charging purrp and a failed open discharge check valve occurs ~en the
purrp is secured, the cr ew v.i II respond in accordance v.i t h 1-.PP- 49, "loss of
Nlrrml Olarging. "
SPD \eri fi ed: (I ni t i al s)
- Olar gi ng fl ow i ni t i all y decr eases
- Charging purrp discharge pressure decreases
- Terrper at ure increases on 1- SWll-103A
- Pnnunci at or s G ffi and G en i II uni nat e
- Pnnunci at or s Gill, GR), and G CS i II um nate ~en "1\' char gi ng purrp i s
stopped
- Olarging flow goes t 0 zer 0 ~en "I'\..' char gi ng purrp iss topped
E\ifNf 5: G yen that the uni t is at pover and an KS I eak has developed, the
crew w II be expect ed tor es pond in accor dance w t h 1- AP- 16, "Pr i rmry PI ant
Leakage. "
SIDm: 2 Illte _ Revision 0
SPD \er i f i ed: ( I ni t i al s)
- Pressuri zer I evel decreases (B-F8 al arm)
- Cbntainnrnt surrp level increases
- (barging flow increases
- Radiation levels on 1-~~-160 and 1-~~-163 increase
- Itmunci at or s K- Il?, and I at er, K- rn al ar m
SID m:: 2 Dite _ Fevision 0
Scenario Performance Datasheet
EWNf 6: a ven that the uni t i s at pov.er and a I...CrA has occur red, the crew
vi II r ?s pond i n accor dance vi t h 1- & 0, "React or Tr i p or Safet y Inj ect ion, "
and 1- &1, "Los s of React or or Secondar y Cbol ant. "
SPD \eri fi ed: (I ni t i al s)
- Pressurizer level and pressure rapidly decrease
- Cbnt ai rurent pr es sure s I ow Y i ncr eas es
- SI does not aut OInlt i call y act uat e, if requi red
- BI T i nl et val ves do not open autoInltically
SIDNC 2 Thte _ Revi si on 0
CONTINUOUS ACTION PAGE FOR '-E-O
1. ADVERSE CONTAINMENT CRITERIA
IF either of the following conditions exist, THEN use setpoints in brackets:
Cl * 20 psia Containment pressure, OR
Cl * Containment radiation has reached or exceeded 1.0ES Rlhr (70% on High Range Recorder).
2. SI FLOW CRITERIA
Cl .!.E SI is actuated AND High-Head Cold Leg SI flow is NOT indicated, THEN initiate ATTACHMENT 6,
MANUAL VERIFICATION OF SI FLOWPATH.
3. RCP TRIP CRITERIA
IF both conditions listed below exist, THEN trip all RCPs:
Cl * Charging Pumps - AT LEAST ONE RUNNING AND FLOWING TO RCS, AND
Cl. RCS subcooling based on Core Exit TCs - LESS THAN 25"F [85°F].
4. CHARGING PUMP RECIRC PATH CRITERIA
Cl. IF RCS pressure decreases to less than 1275 psig [1475 psig] AND RCPs tripped, THEN close Charging
Pump Recirc Valves.
Cl. IF RCS pressure increases to 2000 psig, THEN open Charging Pump Recirc Valves.
5. ECST LEVEL CRITERIA
Cl WHEN the ECST level decreases to 40%, THEN initiate l-AP-22.5. LOSS OF EMERGENCY
CONDENSATE STORAGE TANK 1-CN-TK-l.
6. CDA ACTUATION CRITERIA
IF Containment pressure exceeds 28 psia, THEN do the following:
Cl a. Manually actuate CDA.
Cl b. Ensure CC Pumps STOPPED.
Cl c. Stop all RCPs.
Cl d. Ensure as Pumps RUNNING.
Cl e. Ensure as Pump Discharge MOVs OPEN.
Cl 1. Initiate ATTACHMENT 2, VERI RCATION OF PHASE B ISOLATION.
Cl g. Initiate ATTACHMENT 3, PRIMARY PLANT VENTILATION AUGNMENT.
7. CONTAINMENT RECIRC MODE CRITERIA
Cl To prevent possible radioactive release from the RWST, VCT level should be maintained greater than 12%.
8. RCP CRITERIA
Cl seal injection flow should be maintained to all RCPs.
9. REACTIVITY CONTROL CRITERIA
Cl An Operator should be sent to locally close and lock 1-CH-217, PG to Blender Isolation Valve.
NUMBER AITACHMENT TITLE AITACHMENT
1-E-O 6
MANUAL VERIRCATION OF SI FLOWPATH
REVISION PAGE
36 1 of 3
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
1. OPEN CHARGING PUMP SUCTION FROM D Locally open at least one valve.
RWST ISOLATION VALVES:
D * l-CH-MOV-1115B D WHEN at least one valve is open,
THEN GO TO Step 2.
D * l-CH-MOV-1115D
2. CLOSE CHARGING PUMP SUCTION FROM D Locally close at least one valve before
VCT ISOLATION VALVES: continuing with Step 3.
D * 1-CH*MOV-1115C
D * 1-CH-MOV-1115E
3. CLOSE AT LEAST ONE NORMAL CHARGING D Place 1-CH-FCV-1122 in MANUAL
ISOLATION VALVE: and close.
D * 1-CH*MOV-1289A
D * 1-CH-MOV-1289B
4. CLOSE BIT RECIRC VALVES: IF both of the following valves will NOT
close, THEN locally close l-SI-71, BIT
D * 1-SI*TV-1884A
Outlet HdrTo Boric Acid Tank lsol
0 * 1-SI-TV-1884B Valve:
0 * 1-SI*TV-1884C 0 * 1-SI*TV-1884A
D * 1-SI*TV-18848
D Continue with Step 7.
NUMBER ATIACHMENTTITLE ATIACHMENT
1*E*Q 6
MANUAL VERIFICATION OF SI FLOWPATH
REVISION PAGE
36 20f 3
ACTIONI EXPECTED RESPONSE RESPONSE NOT OBTAINED
5. OPEN AT LEAST ONE BIT OUTLET VALVE: 0 Locally open at least one valve while
continuing with Step 7.
0 * 1-SI*MOV-1867C
0 * 1-SI-MOV-1867D
6. OPEN AT LEAST ONE BIT INLET VALVE: 0 Locally open at least one valve while
continuing with Step 7.
0 * 1-SI*MOV-1867A
0 * 1-SI*MOV-1867B
7. VERIFY CHARGING PUMPS* RUNNING 0 Manually start pumps.
NUMBER AITACHMENT TITLE ATIACHMENT
1-E-O 6
MANUAL VERIFICATION OF 51 FLOWPATH
REVISION PAGE
36 30f3
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
8. VERIFY COLD LEG 51 FLOW - INDICATED: !.E Cold Leg SI flow is NOT indicated,
THEN do the following:
0 * 1-SI-FI-1943 0 a) Turn on control power to AND open
1-SI-MO\f-1836, SI COLD LEG
0 * 1-51-FI-1943-1 INJECTION ALTERNATE HDR
ISOLATION.
0 * 1-51-FI-1961 (NO) b) IF 1-SI-MOV-1836 will NOT open,
THEN tum on control power to AND
0 * 1-SI-FI-1962 (NO) open one of the following valves
(Key Required):
0 * 1-SI-FI-1963 (NO)
0 * 1-51-MOV-1869B, 51 Hot Leg
Injection Normal Header Isolation
0 * 1-SI-MOV-1869A, SI Hot Leg
Injection Alternate Header
Isolation
0 c) Continue attempts to align 51 flow
through the BIT while continuing
with this procedure.
IF 51 flow through the BIT is
established, THEN ensure the
following valves are closed AND
turn off control power:
0 * 1-SI-MOV-1836
0 * 1-SI-MOV-1869B
0 * 1-SI-MOV-1869A
9. RETURN TO PROCEDURE AND STEP IN
EFFECT
-END-
Appendix D Scenario Outline Form E5-D-1
Facility: North Anna Scenario No.: 3 Op-Test No.: 1
Examiners: Mark Bates Operators:
Mark Riches
Initial Conditions: Unit at 100% power MOL. The letdown rad monitor OOS and1-FW-P-2 (terry turbine) was just
returned to service last shift. 2-CC-P-1 A is tagged for seal maintenance.
Turnover: Maintain current plant conditions and support maintenance on 2-CC-P-1A.
Event Malf. No. Event Event
No. Type* Description
1 C (B) (S) BC pump trips and standby pump does not auto-start
2 RC1501 I (R) (S) Tavg unit fails high causing rods to step in
3 C (B) (S) Running IA compressor trips with no auto-start of standby compressor
I (R) (S)
4 RC0803 Selected pressurizer level channel fails low, letdown isolates
TS (S)
4a N (R) (S) Return letdown to service
R (R) (S)
5 C (B) SG PORV fails partially open, unit is ramped back
TS, (S)
Running feed pump trips with no auto-start of standby pump, unit must be
6 FW2201 C (All)
tripped. (No auto reactor trip.)
FW2101
7 FW2102 M (All) Main feed suction lines all break
FW2103
8 FW1102 Terry turbine will trip on overspeed and can't immediately be reset,
C (All)
FW1402 discharge line break on 1-FW-P-3B and 1-FW-P-3A will degrade - FR-H.1
9 RD32 I (All) No auto reactor trip will occur when required
Terminate scenario when feed flow has been restored from the Terry
Turbine
(Event 9 occurs during event 6 and is numbered only for use on Forms
301-5 and 301-6.)
. (N)ormal, (R)eactivitv, (I)nstrument, (C)omponent, (M)aior
rrMNCN
NIDH Al'N\ ~ STATI CN
S~Om::3
E\fNf IESCRI PTI CN
1. Be purrp trips and standby purrp does not auto-start
2. Tavg unit fails high causing rods to step in
3. :&Inni ng I A corrpr es sor t rips Wt h no aut 0- star t of standby corrpr es sor
4/4a. Selected pressurizer level channel fails 10vVrestore letdo~
5. sa PCRV f ai 1spar t i all y open, uni tis r arrped back
6. :&Inning feed purrp trips wth no auto-start of standby purrp, unit
nus t be t ripped
7. ~in feed line suctions wll break
8. Ter r y t ur bi ne w 11 t rip on over speed, di schar ge 1i ne br eak on one
Ml*Wpurrp and
the ot her w 11 degr ade, endi ng in an H I scenar i 0
Scenar i 0 Recapi t ul at ion:
~lfunctions after ECP 2(~in feed line break, AFVVpurrps not available)
entry
Total ~lfunctions 8 (Be purrp t r i psi standby purrp does not aut 0- star t ,
Tavg unit fails high, running IAcorrpressor
trips/standby conpressor does not auto-start,
pressuri zer 1evel channel fai 1s 1o~ sa PCRV fai 1s
open, rmin feed punp trips/standby punp does not
auto-start, rmin feed line break, AFVVpurrps not
available)
limor rml Event s 6 (Be punp trips/standby punp does not auto-start,
Tavg uni t fai 1s hi gh, runni ng IA corrpressor
trips/standby corrpressor does not auto-start,
pressuri zer 1evel channel fai 1s 1o~ sa PCRV fai 1s
open, rmin feed purrp trips/standby punp does not
aut 0- st art)
Mjor Transients I (Min feed line suction break)
ECPs fut er ed 2 (FS-O.I, FR-HI)
ECP Cbntingencies 1(FR-HI)
G i tical Tas ks 6
SID m:::: 3 Page 2 Revision 0
Sc:EN6RI 0 IlRA1l CN
100 Mnutes
SID m::: 3 Page 3 Revi si on 0
SIMULATOR EXAMINATION SCENARIO SUMMARY
SCENARIO NRC 2
The scenario begins vijth the unit at 1009bpover. The letdo~ radiation
nonitor is GC6 and the terry turbine vas returned to service last shift. 2-OC-
P- lA i stagged out for seal rmi nt enance.
The "!\' bear i ng cool i ng punp, 1- Ie- P- lA vij 11 t rip. The cr ew shoul d
identify the loss of bearing cooling and respond in accordance vijth 1-.PP-19,
"loss of Bearing Cboling Wter." The crew should deternine that the "B'
beari ng cool i ng punp di d not aut ormt i call y st art, and per the RN) st art 1- OC- P-
lR O1ce the cr ew has ver if i ed that the OC Sys t em has been res t or ed, or as
di r ect ed by t he Lead Eval uat or, t he next event vij 11 occur.
The next event vij 11 be the f ai 1ur e of the nedi ani s el ect Tave uni t . The
crew vij 11 be expect ed to respond IAWl- .PP-l. 1, "Cont i nuous Thcont roll ed Rod
MIt i on, " and place rod control in ~ crew should address annunciator
res pons e for B- A7, MIl AN' H TA\G < > 1REF IEVI PJ] ~ and take mmual cont r 01
of charging flo~ and place steamdunps in steampressure node. After these
actions have been conpleted and plant conditions are stable, or as directed by
the 1ead eval uat or, t he next event vij 11 occur.
A 1os s of i ns t r unent ai r vij 11 occur vhen 2- I A G 1 t rips. The cr ew vij 11
enter 1-.PP-28, "loss of Instrunent Itr," and start all available air
conpressors. (I-IAGI vijll not start autormtically, but vijll start in l-W'Q.
O1ce instrunent air pressure is returned to norrml, the next event vijll occur.
~xt, PRZRlevel transnitter, 1-~-LT-1461, vijll fail low The crewvijll
respond to the failed channel IAWl-.PP-3, "loss of \hal Instrunent ati on. " The
cr ew vij 11 s vap to an oper abl e 1evel channel, res tor e 1et do~ (~r rml event),
and r evi ew Tech Specs.
The next f ai 1ur e t 0 occur vij 11 be the "B" SG PCRV f ai 1i ng open due tot he
f ai 1ur e of the FI P. The cr ew vij 11 reduce pover per 1-.PP- 38, "Exces s i ve load
Increase." They vijll restore reactor pover to less than 1009band dispatch an
operator to find the cause of the pover increase, close the valve locally, and
stabilize the unit. The next event vijll occur after the crew has stabilized
the uni t, or at the di r ect i on of the 1ead eval uat or .
Shortly after the unit is stabilized, I-FWP-IAvijll trip due to lowoil
pr es s ur e. The BJ> nus t i dent i f Y the punp trip, r ecogni ze that "B" MP di d not
autormtically start and take actions IAWl-.PP-31, "loss of Min Feedvater." The
crewvijll trip the reactor in accordance vijth the imrediate actions of 1-.PP-31
and ent er 1- E- 0, "React or Tr i p or Safet y I nj ect ion." The next event vij 11 take
pI ace on the react or t rip.
SID m:: 3 Page 4 Revision 0
The react or w II not aut ormt i call y t ri p, if requi red, and as a result of
t he trans i ent pi aced on the rmi n f eedvat er s ys t em a feed line br eak w II
occur on the rmin feed purrp suction line resulting in a loss of all rmin feed
purrps. Sever al ni nut es aft er the react or is t ripped, 1- FWP- 2 w II t rip on
overspeed and wII not be able to be innediately reset. Since a safety
i nj ect i on w II not be r equi red at t hi s t i Ire, the cr ew wIlt r ans it i on to 1- ES-
0.1, "Reactor Trip Response." Chce the crewtransitions to l-ES-O.l, "Reactor
Tr i p Response," t he last event w II occur.
"B" MW'Wpurrp di schar ge line w II break in the M\H and no fl ow w II
reach the SG The "1\' MW'Wpurrp wll degrade due to irrpeller darmge. The
crew should identify the loss of all feedvater and transition to I-FR-H 1,
"Response to Loss of Secondary That Sink." Ch their first pass through I-FR-
HI, the crewwII not be able to restore rmin feed, auxiliary feed, or
condensat e fl ow tot he st earn gener at or s. It t hi s poi nt, 1- FWP- 2 w 11 be
reset and the crew should establish adequate auxiliary feedvater flowto the
sa, a110wng thernto transition out of I-FR-H 1. The scenario rmy be
t erni nat ed aft er t r ansi t i on, or at the di rect i on of t he lead eval uat or.
SIDm: 3 Page 5 Revision 0
Pre-job Brief for Scenario NRC-3
Unit Status:
Unit 1 is at 100% power. RCS boron is 978 ppm and core age is 9000 MWD/MTU. Aux
steam is on unit 1.
Unit 2 is at 100% power.
Equipment Status:
l-CH-RM-128, Letdown radiation monitor, is ODS. 1-FW-P-2 was returned to service last
shift, PMT was SAT. 2-CC-P-1A is tagged out for seal maintenance. Maintenance rule
window is green.
Shift Orders:
Maintain current plant conditions and support maintenance on 2-CC-P-1A.
SCENARlOTURNOVERSHEET
Read the following to the crew:
Purpose: Thi s exani nat i on i s i nt ended t 0 eval uat e the cr ews per for nance of
var i ous t as ks as s oci at ed Wt h t he Ii cens ed Q>er at or Tr ai ni ng
Pc ogr am All act i vi ties shoul d be conpl et ed i n accor dance w t h
approved operations standards.
1. You are on a day shift during the veek.
2. )\rough log should be naintained to aid in naking reports and to help during
bri efs.
3. Respond to ~at you see. In the unlikely event that the sinulator fails
such that illogical indications result, the session wll be terninated and
the cr ew i nf or Ired.
Unit Status:
lhi t 1 i s at 100% pover. g:s bor on 1s 978 ppm and cor e age 1s 9000 M'fY MU
AIx steam i s on uni t 1.
lhi t 2 is at 100% pover.
Equipment Status:
Let doWl r adi at i on IlDni t or, 1- rn RM 128, i s ill. 2- CD P- 1A is tagged out. 1-
FWP- 2, terry t urbi ne, WiS ret urned to servi ce last shi ft, PM' WiS SM.
Mi nt enance r ul e w ndow i s gr een.
Shift Orders:
Mi nt ai n cur rent pI ant condi t ions and s uppor t nai nt enance on 2- <:r::- P- 1A
SID m::: 3 Page 6 Revision 0
E\ENf 1: a ven t he pI ant i sin Mide 1 and the "I\.' bear i ng cool i ng vat er punp
has tripped the crewwll respond in accordance wth l-AP-19, "Loss of Bearing
G>oling Wter."
1I~ E>>>IaID !Cll CN I~REMRKS
SPD \eri fi ed: (I ni t i al s)
- hmunci at or s . F- F4, F-rn, F- I-E i 11 uni nat e
- 1- Ie- P- lA has a br eaker ni sal i gmrent (anber and green lights lit)
- I-OC-P-IB does not auto-start
B:P i dent i f i es annunci at or F- F4, Ie
WR PP lA IB IiJID 1RIP S\S
MSPU<:ND
B:P i dent i fi es 1- Ie- P- lA has
t ri pped.
B:P i dent i fi es that l-Ie-P-IB did
not aut ormt i call y st art.
lB di rect screw to ent er 1- AP- 19.
B:P checks st at us of Ie punps.
B:P st art s I-OC-P-IR
B:P veri fi es at I east one Ie punp
r unni ng nor rmll y.
CI ew ver if i es t hat Ie s ys tern i s
operating tover-to-tover.
CIewverifies that Ie systemis
oper at i ng nor rmll y.
CI ew IIDni t or s rmi n gener at or
t enper at ur es.
CI ew di spat ches oper at or to check
equi pIrent s uppl i ed by oc;
MP, Cbnd purrps, FlC IPs, lPs.
lB report sloss of Ie punp and
failure of standby punp to auto-
start and requests assistance, V0rk
Request, and Cbndi t i on Report.
NOTE: When sent to investigate, the
operator will report that there is an
overcurrent trip on the breaker for I-BC-
P-IA.
NOTE: The next event can occur once the
crew has restored BC or at the discretion
of the lead evaluator.
SID m:: 3 Page 7 Revi si on 0
E\ENf 2: G ven that the uni tis in node 1 and the rredi ani s el ect Tave uni t has
fai 1ed, the crew wI 1 be expected to respond in accordance wth 1-AP-1.1,
"Chnt i nuous Thcont roll ed Rod ~t ion," and annunci at or s ~ J(J and ~ /J8.
TIM: EXPIDID K:TI CN I lIS1Rl.ITCR ~
SPD \eri fi ed: (I ni t i al s)
- Rods stepping in at rrnxirrurnspeed
- Pnnunci at or s ~ J(J and ~ /J8 ar e ill uni nat ed
- St at us 1i ght MFA ill uni nat es
RO i dent i f i es annunci at or s ~ J(J,
i\H1 PN H TA\G < > 1RFF IE\i AlI CN
and ~/J8, UXP1A ~ C TA\G
IE\iAlICN
RO i dent i fi es cont rol rods
s t eppi ng in at rrnxi rrurn speed.
RO i dent i fi es rredi ani sel ect Tave
uni t fai led.
lB di rect screw to ent er AP-1. 1.
CTI Crew takes action to stop rod Critical Task
motion and stabilize the unit: *Pr i or tor od 10-10 insert i on
RO places FOd control in MANUAL Ii ni t
RO ver i fi es rod not i on st opped.
RO ver i f i es that 1-:OC- TI -1408 is
norrrni. (tq
Oewinitiates action of AR~J(J, See actions below
Yhi I e cont i nui ng.
Oew veri fi es cont rol rods above
t he I 0- I 0 i ns er t i on 1i ni t.
RO checks RCS Tave and adj us t s as
di r ect ed by t he lB.
RO checks PRZR pressure.
RO checks PRZR level.
o ew checks cont r 01 s rods above
t he I 0 i ns er t i on I i ni t.
Oewrrnintains stable plant
condi t ions.
NOTE: The following actions are lAW
annunciators B-A7.
SID m::: 3 Page 8 Revision 0
E\ENf 2: Oven that the uni tis i n IIDde 1 and the rredi ani se1 ect Tave uni t has
f ai 1ed, the cr ew v.i 11 be expect ed tor es pond in accor dance v.i t h 1- ftP- 1. 1,
"Cbnt i nuous Thcont roll ed Rod M>t ion," and annunci at or s B- J(J and B- P8.
TI~ EXPInID 1CIl CN I Ni'IRlUt:R ~
00 pI aces PRZR 1evel cont rol in
~ and cont r 01 s PRZR 1evel .
Om us e 1- rn FC\L 1122 and! or 1-RG
I..CV-1459G
00 trans f er s condens er stearn dunps
to st earn pr essur e IIDde.
- Bot h St earn llinp I nt er lock
s w. t ches to CFF/ RESEr
- St earn llinp Cbnt roll er t 0
Mnua1
- M>de Se1 ect or to S1EAMPRESS
- Ens ur est earn dunp demmd i s
zero
- St earn llinp Cbnt roll er to aut 0
- St earn llinp I nt er lock s v.i t ches
to CN
18 i nf or m Wr k Cbnt r 01 cent er of
failure and requests assistance,
VR, and CR
NOTE: If the US requests permission to
withdraw rods to restore temperature, it
will be ';ven.
NOTE: The next event will occur after
the crew has stabilized the plant, or as
directed by the lead evaluator.
SID m:: 3 Page 9 Revision 0
EVfNf 3: a ven that the uni tis at pov.er and i ndi cat ions exist of a loss of
i ns t r ummt ai r , the cr ew v,i 11 res pond in accor dance v,i t h 1-/JP- 28, "Loss of
Inst rwrent Ii r. "
TIf\E IN'H:1ID ICll CN I 1'S'IRlCfCR ~
SPD \eri fi ed: (I ni t i al s)
- Ifmunci at or 11 -rn i 11 uni nat es
- IA pressure drops
- l-IAGI v,ill not st art aut onnt i call y, if required
- Ifmunciators J-E8 and F- F8 ill uni nat e
KJ IlP i dent i fi es annunci at or J - rn,
I NIT AI R CQ.FRI IRYER 1IU.RE
NOTE: Crew may not enter AP-28 until
low air pressure alarms come in.
lB di r ect sent r y i nt 0 1- /JP- 28.
NOTE: I-IA-C-I will not automatically
start, but can be started in HAND.
CT2 Crew starts all available air Critical Task
com~ressors.
- Prior to IA pressure decreasi ng
- BOP starts I-IA..C-1J, I-IA-C-2A, and to 70 psi g
I-IA-C-2B.
CIew veri fi es i nst rurrent ai r
pressure> 70 psi g.
NOTE: If sent, after approximately 5 Pri nt cont ai ni ng these
minutes, the auxiliary building operator conponent sis FM82B sheet 2 of
will report a MOTOR OVERLOAD 4.
annunciator lit on the local panel for 2-
IA-C-I and an air leak at the compressor.
He will report that there are only 2 things
between the air receiver and the
compressor, 2-IA-6, which is a check
valve, and 2-IA-7, which is a manual
isolation. He will ask for 2Uidance.
CIewverifies loss of instrurrent
ai r cor r ect ed.
CIew veri fi es i nst rurrent ai r
pressure> 94 psi g. (N::}
B:P i sol at es I A t 0 cont ai nrrent by
cl osi ng 1- IA 'IV 102A
B:P checks IA pressure out si de
cont ai nrrent i ncreasi ng.
SID m:: 3 Page 10 Revision 0
E\f.Nf 3: a ven that the uni tis at pover and i ndi cat ions exi s t of a loss of
i ns t r lllrent ai r , t he crew W11 respond in accordance wt h 1- JiP- 28, "Loss of
Ins t r UIrent A r. "
TI~ EXPIDID PCII CN I!'S1RlCI(R ~
NOTE: Whether the leak location has
been reported and direction made to
isolate it will determine how the crew
proceeds through l-AP-28. Once the leak
has been isolated the crew should reopen
the containment IA TVs, if closed.
NOTE: The next event will occur after
instrument air pressure is returned to
normal, or as directed by the lead
evaluator.
SIDm: 3 Page 11 Revi si on 0
E\IENf 4/ 4a: a ven that the uni t i s at pover and a s el ect ed pr es sur i zer 1evel
channel has f ai 1ed, the cr ew v.i 11 be expect ed tor es pond in accor dance v.i t h
1- JiP- 3, "Loss of \1. t al Ins t r ummt at ion. "
1l~ EXPB::TID !CIl CN I NrrRI.InR ~
SPD \eri fi ed: (I ni t i al s)
- I'llnunciators B-F8, B-Gl, and B- E2. are i 11 urri nat ed
- l-RC-U-1461 fails low
- Let doWl i sol at es
RO i dent i f i es annunci at or s B- F8,
PZR ill lE\H, and B-Gl, PZR ill L\L
HIR5 CFF- I..EIIX:J.'N I Sa...
NOTE: Identification of failure may not
occur at this time.
RO identifies 1-RC-LT-1461 failing
low and the loss of 1et doWl.
RO not i fi es lS of fai 1ure.
lS directs crewto performthe
i mredi at e act ions of JiP- 3.
G ew ver i f i es redundant i ndi cat i on
norrml.
Gewverifies SGcontrol
par arret er s nor rml .
Gewverifies first stage pr es sure
i ndi cat ions norrml.
RO ver if i est pI aces 1- rn FC\'-1122
in rmnual and adj ust s to cont rol
pressurizer level at program
RO sel ect soper abl e pr es sur i zer
1evel channel (459/460) .
RO verifies letdoWl in service.
(fq
SID m:: 3 Page 12 Revision 0
FMNf 4/4a: a ven that the uni t i s at pOYer and a s el ect ed pr es sur i zer 1evel
channel has faifed, the cr ew v.i 11 be expect ed tor es pond in accor dance v.i t h
1-AP-3, "Loss of \oi t al I nst rUIrent at ion. "
11M': EXPEDID ICIl (N INnRl.Cf(R ~
CT3 Crew returns letdown t&se~~ Critical Task
using attachment of l-AP-3'. NJrrml Event
- Pr i or t 0 a PRZR hi 1evel
- RO es t abl i shes at 1east 25 gpm react or t rip
of charging
1460B
- RO puts 1-GIPC\'-1145 in
rmnual
- RO full y opens 1-GIPC\'-1145
rmintain 300 psig
Alto.
RO veri fi es PRZR 1evel cont rol in
auto. (!'q
RO restores press uri zer 1evel to
program
ROverifies/adjusts output of 1-
RG LC\'- 1459G
crew di scusses need to 1eave
char gi ng cont r 01 in rmnual due to
previ ous fai 1ure.
RO ver i fi es press ur i zer cont rol
heat er s not t ripped. (!'q
RO resets control heaters by
pI aci ng s v.i t ch t 0 START.
BOP verifies both first stage
pressure channels norrml.
BOP verifies operable channels
sel ect ed for SCN£.CS.
crew i dent i fi es t he correct MP
(55.72) for placing channel In
t rip.
US references Technical Specifications:
-
3. 3. 1 (Punct i on 9 Cbndi t i on L - 72
hours to place channel in trip)
TS 3.3.3 (Function 13 - Info
act ion).
lSI SS rmke not if i cat ions about
f ai I ed channel.
SIDr<<: 3 Page 13 Revision 0
E\mf 4/4a: a ven that the uni tis at pov.er and a sel ect ed pr es sur i zer 1evel
channel has fai 1ed, the cr ew vi 11 be expect ed tor es pond in accor dance vi t h
1- Pl'- 3, "Loss of \ital Instrunent at i on. "
11M: EXPEOID ICIl CN I~~
NOTE: When the crew reestablishes
letdown and the US has reviewed TS,
then the next event will occur.
S)G~3 Page 14 Revision 0
E\fNf 5: a ven that the uni t is at pov.er and a SG PCRV has f ai 1ed open, the
cr ew v.i 11 res pond i n accor dance v.i t h 1- /JP- 38, ":Excessive Load Increase."
11l\E ~JCfICN I NITRl.CItR ~
SPD \eri fi ed: (I ni t i al s)
- React or pov.er slow y i ncr eas es .
- Mgav.at t s slow y decrease .
RO IlP i dent i fi es increase in
reactor pov.er/decrease in ~
lS di rect screw to ent er 1- /JP- 38.
ID ver i f i es all steamdunps
cl osed.
NOTE: Crew may identify "B" PORV
open from PCS alarm and PNID screen.
NOTE: BOP may place "B" PORV in
manual and press the "Down" button.
IlP verifies all SG PCR\S i ndi cat e
closed.
IlP verifies t urbi ne load norml.
IDverifies reactor pov.er is less
t han or equal t 0 100% pov.er . (tq
IlP r anps dOWl t ur bi ne tor educe
pov.er t 0 :s; 100%
CIewdispatches operators to check
for the source of stearn
NOTE: The operator will report that the
"B" steam generator PORV is open.
CI ew di r ect s the oper at or to
locally close the "B" SGPCR"Y.
NOTE: The field operator will report
that the PORV handwheel is bound and
he cannot close the valve.
CIew di rect soper at or to i sol at e
PCRV us i ng 1- M>- 59.
CI ew checks pov.er 1evel reduced to
the pov.er 1evel bef or e t he event
st art ed.
CIew stops ranp.
IlP places t urbi ne in IM>- IN if
requi red.
SID m: 3 Page 15 Revision 0
~5: a ven that t he uni t is at pov.er and a SG F(RV has f ai I ed open, the
creww.ll respond in accordance w. t h 1- Pf'- 38, "Excessive Load Increase."
TI~ E>>>HAID PCII CN INnRlCfCR ~
llJ' checks rmi n gener at or out put.
llJ' checks all st earn fl ow
indications norrml.
llJ' checks turbine control in
oper at or aut o.
CI ew checks pI ant steam syst em:
SGF(R~
SG safet i es
MR inlet FGS
AS PCv.
US consults Technical Specification
3.7.4 Cbndi t i on A and det erni nes
that the F(RV i s i noper abl e and
rrust be returned to operable
w. t hi n 7 days .
CI ew ref er ences React i vi t y adni n
( CP- Pf'- 300) , as t i Ire perni t s.
NOTE: US may request permission to
restore reactor power.
NOTE: The next event will occur after
the crew has stabilized the unit, or at the
direction of the lead evaluator.
SID m::: 3 Page 16 Revision 0
EVENf 6: G ven the pI ant i sin Mde 1 w t hindi cat ions of a 1os s of "P\.' Mi n
Feedvat er Punp and a f ai 1ur e of "B" Mi n Feedvat er Punp t 0 aut 0ll1lt i call y
st art. the crewwll respond in accordance wth 1-AP-31, "Loss of Min
Feedvat er ," and 1- E- 0, "React or Tri p or Safet y I nj ect ion. "
n~ EXPH:1ID ICTI eN INnRlCI(R~
SPD \er i fi ed: (I ni t i al s)
- Innunci at or E- H5 ill uni nat es
- "N MP br eaker shave anber and gr een 1i ght s 1it
- "B" MP does not aut 0- st art
- Avai 1abI e feed fl ow is 1ess than st earn fl ow
IlP i dent i f i es annunci at or IE- H5,
FWPThP 1A llJE GL PRESS I..o.V
IlP i dent i f i es t rip of "P\.' MP.
IlP inform lS of MP tri p.
IlP i dent i f i es star t f ai 1ur e of UHf
MP.
lS di rect the IlP tot ake act ions
of 1- AP- 31.
IlP checks reactor pover greater
than 70% ( YES)
IlP checks 2 feed punps running.
(~
lS di reet crew to ent er 1-E-0.
NOTE: The next event will be initiated
when the reactor is tripped.
SIDNC 3 Page 17 Revision 0
EWNf 7: G ven that a rrnin feed suction line has broken, t he crew v.i 11
res pond in accor dance v.i t h 1- E- 0, React or Tr i p or Safet y I nj ect i on. II
11~ EXPECIID 1CIl (N I N)'IRlCItR ~
SPD \er i fi ed: (I ni t i al s)
- The reactor does not trip autorrntically, if requi red
- Irnlunci at or s F-:Eli, GF6, F-Dl, F-rn, F-r8, F-M, F-ffi, F-Fl, F-F2, F-F3,
G CB ill uni nat e
--===-
- ~in feed punp suction pressure rapidly decreases
- Standby rrnin Cbndensate punp starts
- \oar i ous t ur bi ne bui 1di ng sunp al ar III i 11 uni nat e
NOTE: The crew may manually trip the
reactor before getting a first out on SG
low level with steam flow/feed flow
mismatch. The reactor will not
automatically trip when required.
CT4 ROIBOP trip the reaetorJ Critical Task
a:P veri fi est t ri ps t urbi ne.
ro ver i f i es IC eIrer gency bus ses
energi zed.
a:P i dent i f i es annunci at or IF- :Eli,
M\I N FD PThPS SlIT HR La PRffiS.
NOTE: G-C8 is the turbine building
flooding alarm.
IlP identifies auto-start of the
standby condensate punp.
a:P i of or III cr ew that feed punp
suction pressure is rapidly
decr eas i ng.
ro ver i f i es pover t 0 IC eIrer gency
busses.
crew checks i f SI has act uat ed.
(rq
crew checks if SI is requi red.
(rq
lS di rect s t earn tot r ans it i on to
1- fS- 0. 1.
NOTE: Crew may use O-AP-39.1 for
Turbine Building Flooding to direct
securin2 of secondary pumps.
SIDm: 3 Page 18 Revision °
E\fNf 7: a ven t hat a Il1li n feed s uct i on 1 i ne has br oken, the crew w 11
res pond i n accor dance wt h 1- E- 0, React or Tr i p or Safet y I nj ect ion. "
1Il\E EXPECIID 1CIl CN I l'SIRl.Cf(R ~
lS di rect s a:P to secure Il1li n
feed, condensate and heater drain
punps.
a:P s ecur es Il1li n feed, condens at e,
and heater drain purrps.
NOTE: The terry turbine will trip 2
minutes after starting.
NOTE: The next event can occur once
secondary pumps have been stopped, or
as directed by the lead evaluator.
SXJ~3 Page 19 Revision 0
E\ENf 8: G ven that a loss of all rrnin and auxiliary feed vater purrps has
occurred, the crew vi 11 respond in accordance VIi t h 1- FR- H 1, "Response to
Loss of Secondary That Sink."
n~ fJ<<>R:1ID PCII CN I r-sIRI.CTCR ~
SPD \eri fi ed: (l ni t i al s)
- Itmunci at or s F- [8 ill uni nat es
- ~ fl ow i ndi cat ed to" P:.' SG
( :Y
- PI ow from 1- FWP- 3B i s not r eachi ng the "B" sq VR. level decreasing
1- FWP- 3A degr ades and fl ow drops to zero
NOTE: A break will occur on "B" AFW
pump discharge line in the MSVH, and
the"A" AFW pump will degrade after
startin~.
- ID checks ReS aver age t errper at ur e
stable or trending to desired
t errper at ur e.
B:P i dent i f i es annunci at or F-:eg,
11.RBI t'-E IRI WN AFWPTl\P 1lU..BI.E <R
llBE OL 1RBL
NOTE: Once H.1 is entered, a security
officer, or any operator sent to the
vicinity of the MSVH, will report that
water and steam are issuing out the
door.
Gew identifies that "B" SG VR.
level is not i ncreasi ng.
G ew i dent i f i es that I-FWP-3A
fl ow is degr adi ng.
B:P identifies there is no AFW
fl ow avai I abl e.
Gewidentifies that there has been
a I os s of t he heat sink cr i tical
safet y funct ion.
tE di r ect s cr ew tot r ans it ion to
I-FR-H 1.
G ew checks i f secondar y heat sink
is required. ('YES)
Gew di spatches an operator to
check 1- FWP- 3A and the terry
turbine.
NOTE: Operator will report "A" AFW
pump does not sound right, mechanics
suspect internal damage. The terry
turbine trip valve is closed.
SIDNC 3 Page 20 Revi si on 0
- E..VENf 8: Civen that a loss of all rrain and auxiliary feed ~ter punps has
occurred, the crewwll respond in accordance wth I-FR-Hl, "Response to
lDss of Secondary That Sink."
n~ EXPInID iCI1 eN INnRlCfCR~
NOTE: The operator instructed to reset
the overspeed trip valve will report that
the he can't get it to stay reset.
(}ew t ri es to est abl i sh PFWfl ow to
at 1east one SO
- BJ> checks SG Bl. OroOWl and
sanple isolation valves closed
- Q ew r evi ew; cont r 01 room
i ndi cat ions to det erIIi ne loss
of PFWflow
- ew det er IIi nes that they
Q
cannot start an PFWpunp from
the MR
(} ew det er IIi nes that t hey do not
have adequate PFWflow
CT5 Crew stops reactor coolant pumps Critical Task
to conserve SG inventory and delay *Prior to nreting bleed and feed
need for bleed and feed. cri t eri a
- RO stqps aD reactor coolant pumpsJ
(} ew di spat ches an oper at or w t h
AP-22 series procedures.
Qewattenpts to establish Min
Feed fl ow tot he SO;:
- (}ew det erni nes that t here are
no condensat e punps runni ng. v/
B:P checks SG w de range level sin
2/3 SO; less the 14% (~
lS returns to step l.
t lThLs-L - - ---- --
s bleed and feed criteria
NOTE: The operator dispatched to reset
the overspeed trip valve will now inform
the crew that I-FW-P-2 has been reset.
CT6 Crew establishes adequate AFW Critical Task
flow to SG(s). *Prior to nreting bleed and feed
cr iter i a
- B0P establishes adequate AFW flow:
as indicated by core-exit TCS
~ecr~g and SG wide.r~~km
JncreasJne;t~maybe <340 om.
Qew veri fi es core- exi t ill
decr eas i ng and "I\' SG WR level
i ncr eas i ng.
SIDm: 3 Page 21 Revision 0
E\ENf 8: a ven that a loss of all rrain and auxiliary feed vater punps has
occurred, the crew W11 respond in accor dance wt h 1- FR- HOI, "Response to
Loss of Secondary ~at Sink."
11M: EXPIDID ICIl {N I!'SJRI.CI(R ~
lS di r ect s trans it i on to 1- ES- O. 1.
NOTE: An Sf may occur on delta P if
AFW flow is not throttled to "A" SG.
NOTE: The scenario may be terminated
once the crew has established adequate
AFW flow, or at the discretion of the lead
evaluator.
SID m::: 3 Page 22 Revision 0
P1UHl.RE REv.
Pbnorml Procedure l-AP-19, "Loss of Beari ng Cbol i ng Wt er. " 16
Pbnorml Procedure 1- AP-l. 1, "Cbntinuous Thcontrolled Rod Mlt i on. " 8
Pbnorml Procedure l-AP- 28, "Loss of Instrurrent lir." 30
Pbnorml Procedure 1- AP- 3, "Loss of \1. t al Inst rurrent at ion. " 22
Pbnorml Procedure 1- AP- 38, "Excessive Load Increase." 14
Pbnorml Procedure l-AP-31, "Loss of Mi n Feedv.at er. " 4
FIrer gency Pr ocedur e l-E-O, "React or Tri p or Safet y I nj ect ion. " 36
FIrer gency Pr ocedur e l-:ES- O. 1, "React or Tri p Response. " 26
Funct i onal Restoration Procedure I-FR-H 1, "Response to Loss of 17
Secondary !-eat Sink. "
Station Innunciator Response Procedures. NA
Chide and Ref er ence Ihcurrent PI-AASOOO, "I-hmn Performnce. " 1
INlQ Chi del i ne for Tearmork and II agnost i c Skill Thvel oprrent : Jan. 1988
INlQ ICM) 07- 002 Si nul at or Tr ai ni ng Chi del i nes Jan. 2007
SIDm: 3 Page 23 Revision 0
AITJGMNf 1 - SI Ml..A1tR (]>:ERAl{R S CThPUIffi PRXRAM
AITJGMNf 2 - S~ 0 PmFrnMN:E CBTHTI \£s
AITJGMNf 3 - SIMl..A1tR PERFCRM>N:E OO'ASI-EEf (last page of scenario)
SIDm: 3 Page 24 Revision 0
ATIIQMNf 1
SI M1.A1tR CPERtmR S CThPUIER PlURAM
SIDm: 3 Page 25 Revision 0
SIMULATOR OPERATOR'S COMPUTER PROGRAM
SXGNRC3
Initial conditions
1. Recall Ie 163
2. Fnsure Tave, Tref, PDIT level, and \Cf level are selected on trend
recorders.
3. PI ace a VR rmgnet on l-GlRI-128.
PRELOADS PRIOR TO SCENARIO START
CINlTICN ~ CN OvERRIIFI EIC
Fai 1ure of "B" MP to Switch override:
aut 0- st art FWIBC~ = CFF
FWIB2_~ = CFF
Failure of aut 0 react or Malfunction:
trip RIl32
Let doWl r ad IIDni t or Malfunction:
fai I ure RM207, Sever i t Y = - 1
Fai I ure of l-IAGI to Switch override:
aut 0- st art IICl_PlJIQ ().rerride = CFF
SCENARIO EVENTS
E\ENf ~ eN OvERRIIFI CIMIN OOI <M
1) Loss of OC Remote functions:
IlPIA_POOIR:A = T, frl ay t i Ire = 5, Tri gger = 1
IlP_PlJID_IEF'FAf = T, frl ay t i Ire = 5, Tri gger = 1
NOTE: When sent to investigate, the operator will report that
there is an overcurrent drop on the breaker for" A" BC pump.
NOTE: The next event will occur once BC is restored, or at the
discretion of the lead evaluator.
SXJm= 3 Page 26 Revi si on 0
2) ~dianlselect Tave Malfunction:
fai I ure lU.501, !Xl ay t i Ire = 5, Ranp = 5, Severi t y = 1,
Tri gger = 2
NOTE: If the US requests permission to withdraw rods to
restore temperature, it can be given. (Always ask for a
recommendation and then concur with it.)
NOTE: The next event will occur after the crew has stabilized
the plant, or as directed by the lead evaluator.
3) Loss of instruIrent Remote function:
air lQ_IICCFPlLT = 1RI..E Tri gger = 3
Malfunction:
00402, !Xl ay t i Ire = 8, Ranp = 10, Sever it y = 10,
Tri gger = 3
NOTE: If sent, after approximately 5 minutes, the auxiliary
building operator will report a MOTOR OVERLOAD
annunciator lit on the local panel for 2-IA-C-l and an air leak
at the compressor.
He will report that there are only 2 things between the air
receiver and the compressor, 2-IA-6, which is a check valve,
and 2-IA-7, which is a manual isolation. Ask what they would
like you to do.
NOTE: If sent to check 2-IA-TV-211 can report it either open
or closed (opens when IA pressure at the dryer is <90 psig). If
open report was made, can later report that reset was pressed
when so directed.
NOTE: When told to close 2- IA-7, wait 1 minute then delete
malfunction CA0402 and report that leak is isolated.
NOTE: The next event will occur after instrument air pressure
is returned to normal, or as directed by the lead evaluator.
4) PRZR level 01 I, LT- Malfunction:
461 fai I s low KD803, !Xl ay t i Ire =5, Ranp = 30, Severi t y = -1,
Tri gger = 4
NOTE: When the crew reestablishes letdown and identifies the
correct MOP and TS action, then the next event will occur.
SXim: 3 Page 27 Revision 0
5) St uck open SG PCRV Remote function:
MlPCVlOIB_K; 1:£1 ay t i Ire = 5, Ranp = 5, val ue = 100,
Tri gger = 5
NOTE: Approximately two minutes after crew dispatches an
operator to the MSVH, report that the "R" steam generator
PORV is open.
NOTE: When asked to close the valve using the handwheel
report back after several minutes that the handwheel is
bound and you cannot operate it.
When directed to isolate the PORV then close I-MS-59 over
70 seconds using PNID.
NOTE: The next event will occur after the crew has stabilized
the unit, or at the direction of the lead evaluator.
6) Trip of "~' M'P Malfunction:
FV0401, 1:£1 ay t i Ire = 5, Ranp = 60, Sever it y =100,
Tri gger = 6
NOTE: When requested to investigate cause for loss of oil
pressure informs US that oil is leaking from a flanged
connection on the south end of the MFP.
NOTE: The next event will occur when the reactor is tripped.
SIDNC 3 Page 28 Revision °
7) Loss of MW Malfunctions:
FV2101, 2102, 2103, ~lay ti~ = 5, Ranp = 0, Severity
= 100, Tri gger = 7
Alarm overrides:
VlIF8_W ~l ay t i ~ = 15, Qrerr ide = Cl"{ Tr i gger =7
VlIXB_W ~l ay t i ~ = 20, Qrerr ide = Cl"{ Tr i gger =7
VlIOi_W ~l ay t i ~ = 20, Qrerri de = Cl"{ Tri gger =7
VlCI:8_W ~l ay t i ~ = 25, Qrerri de = Cl"{ Tri gger =7
Vl.AI:E_W ~l ay t i ~ = 30, Qrerr ide = Cl"{ Tr i gger =7
Set up trigger 7 to occur when the reactor is tripped.
RX_RfA_52 . E'Q °
NOTE: The following trips the Terry Turbine on overspeed 2
minutes after the reactor is tripped:
Remote function:
MITV115 = 0, ~l ay t i ~ = 120, Tri gger = 10
Set up trigger 10 to actuate on reactor trip breaker being
open.
RX_RfA_52 . E'Q °
NOTE: A security officer, or operator if one has been sent to
area, will call the MCR on the gaitronics and inform the crew
that there is a large amount of steam in the east end of the
turbine building basement.
NOTE: Operator will report the terry turbine trip valve is
closed.
NOTE: When the operator is instructed to reset the
overspeed trip valve: Report that the valve will not stay reset
and request assistance.
NOTE: The next event will occur after the crew secures CN
and lIP pumps, or as directed by the lead evaluator.
SID m::: 3 Page 29 Revi si on °
8) Loss of heat si nk Malfunction:
FW402, Thl ay t i Ire = 5, Severi t y = 30, Ranp = 30,
Tri gger = 8
FW102, Thl ay t i Ire = 10, Severi t y = 30, Ranp = 120,
Tri gger = 8
NOTE: Operator will report "A" AFW pump is noisy. If
sent, mechanics can report suspected impeller damage.
NOTE: Once operators have determined that they have a loss
of heat sink and have entered H.l, someone can report that
steam and water are coming out the door of the MSVH.
NOTE: Watch SG WR levels, reset terry turbine before feed
and bleed criteria are met.
NOTE: After the crew has looped back to step 1 of I-FR-H.l,
reset overspeed trip valve using remote function:
MSTV115 =100, Ramp =30
NOTE: The operator dispatched to reset the overspeed trip
valve will inform the crew that I-FW-P-2 has been reset.
NOTE: The scenario may be terminated once the crew has
established adequate AFW flow, or at the discretion of the
lead evaluator.
SXi m:: 3 Page 30 Revision °
SXJm: 3 Page 31 Revision 0
SI MI..AIrn. RHJ.W1 H OOI CN EX<W:NUI CN
lERMN6L PFRFrnl\mE CBTH:TI \E
a ven equi prrent f ai 1ur es and oper at i onal sit uat ions, oper at e t he pI ant in
accor dance w t h Techni cal Speci f i cat ions to br i ng the uni t to a saf e
condition, using applicable procedures, and applying effective tea~rk,
connuni cat ion, and diagnostic skills.
G*RI C PERFrnM'\NE CBT H:TI \ffi
A Ilrring shift operations the shift mmager wll take a conservative course
of act ion, es peci all y vhen uncer t ai n condi t ions exi s t, vhen deal i ng w t h
core cool i ng or heat si nk avai 1abi Ii t y, pri rmry syst em and cont ai nrrent
integrity, and reactivity control associated wth plant evolutions.
B Ilrring shift operations the shift rmnager wll provide overall crew
guidance by prioritizing and integrating the actions of the shift crewin
accor dance w t h adni ni st rat i ve pr ocedur es.
C Ilrring shift operations each crew rrenber wll partIcIpate in a team
effort that resolves conflicts, provides input into the teamdecision and
connunicates all the necessary inforrmtion to enhance tea~rk in
accor dance w t h adni ni st rat i ve pr ocedur es .
D Ilrr i ng shi f toper at ions t he Shi f t Techni cal A.lvi sor w 11 independent 1y
assess events and based on those assessrrents rmke recorrnendations to the
crew regardi ng ni t i gat i on st r at egy.
SIDm:: 3 Page 32 Revision 0
EVENT 1 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven t he pI ant i sin Mlde 1 and the "/\' bear i ng cool i ng
Wl.t er punp has t ripped the cr ew v.i 11 res pond i n accor dance
v.ith l-AP-19, "Loss of Bearing (boling \\Iter."
NORTH ANNA SPECIFIC TASKS:
R122 St abi 1i ze the uni t foIl ov.i ng a loss of beari ng cool i ng Wl.t er.
CRITICAL TASK:
NA
SID m:: 3 Page 33 Revision 0
EVENT 2 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that the unit is in DDde 1 and the rredianlse1ect Tave
uni t has f ai 1ed, the cr ew W11 be expect ed tor es pond in
accor dance w t h 1- JiP- 1. 1, "Gmt i nuous lhcont roll ed Rod
M>t ion," and annunci at or s B- KI and B- AS.
NORTH ANNA SPECIFIC TASKS:
R248 Respond to a T-A'lJ -REF IEVI.tXII CN annunci at or a1 arm
R:l75 Perform t he i IJIredi at e oper at or act ions in response to a cont i nuous
uncont roll ed rod DDt ion.
CRITICAL TASK:
See next Page
SID m::: 3 Page 34 Revision 0
cr St at errent :
CIewtakes action in accordance wth I-J1P-1.1, to stop rod rmtion and
stabilize the unit.
Safety Significance:
Cbre reactivity is not under control of the operator due to the failed
cont r 01 channel. "I tis expect ed that the oper at or w 11 at t enpt tot ake
nnnual actions to correct for anonn10us conditions during pover
oper at ion. "
Indication of a failed ~ lhit.
Cbnt i nuous i nwn d cont r 01 rod rmt i on w t h Tave and Tr ef nnt ched.
Perfornnnce Indicator:
00 pI aces rod cont r 01 in nnnual.
Feedback:
Rod rmtion stops.
VffJ Reference:
Nme
Cbndi t ions:
Pr i or t 0 a Rod 10- 10 i ns er t i on 1i ni t.
SIDm::: 3 Page 35 Revi si on 0
EVENT 3 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at pov.er and i ndi cat ions exi st of a
loss of instrurrent air, the crewwll respond in accordance
w t h 1- AP- 28, "Los s of I ns t r urrent Pi r. "
NORTH ANNA SPECIFIC TASKS:
R530 Res pond t 0 a I os s of i ns t r urrent ai rout side cont ai rnrent .
CRITICAL TASK:
See next page
SID me 3 Page 36 Revision 0
cr St at errent :
Gewstarts all available an conpressors.
Safety Significance:
Failure to start all available air conpressors under the postulated plant
condi t ions cons tit ut es ni s - oper at i on or i ncor r ect cr ew per for rmnce Wli ch
leads to degr adat i on of pI ant condi t ions Wli ch coul d res ul tin a uni t
trip and/or safety inj ection. In this case, the instrurrent air pressure
can be rmi nt ai ned above the t ri p set poi nt by st art i ng the ai r
conpressors. Therefore, failure to start the air conpressors also
represents a "dernmstrated inability by the crew to take an action or
conbi nat i on of act ions that wml d pr event a chall enge t 0 pI ant s af et y. II
Instrurrent air lowpressure alarm
Mter indication of lowinstrurrent an pressure.
Perforrmnce Indicator:
BCP starts all available air conpressors.
Feedback:
Instrurrent an pressure stabilizes above the trip set point.
VffJ Reference:
Nme.
Omdi ti ons:
Pr i or tor eachi ng t he t rip set poi nt of 70 PSI G
SID m::: 3 Page 37 Revi si on 0
EVENT 4 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that the unit is at pover and a selected pressurizer
- 1 evel channel has f ai 1ed, the cr ew W11 be expect ed to
respond in accordance w th l-AP-3, "Loss of Vi. tal
Ins t r UIrent at ion. "
NORTH ANNA SPECIFIC TASKS:
H633 Respond to a failure of the controlling pressurizer level channel.
S70 Evaluate corrpliance wth technical specifications.
CRITICAL TASK:
See next page
SXi r<<: 3 Page 38 Revision 0
cr St at emmt :
fr ew takes mmua1 cont r 01 of PRZR 1eve1, ni ni ni zes char gi ng, and res tor es
1et doWl.
Safety Significance:
Fai 1ure tot ake mmua1 cont ro1 of PRZR 1eve1 const i t ut es a "ni s- oper at i on
or i ncor r ect cr ew per for rmnce" v,hi ch w11 res u1 t i n an unneces sar y
react or trip on hi gh PRZR 1eve1 .
The cont roll i ng PRZR 1eve1 channel i s f ai 1ed 1o~ 1et doWl i sis 01 at ed.
Perforrmnce Indicator:
00 ver if i es/ pI aces cont roll er for 1- rn PC\'- 1122 in rmnua1 and cont r 01 s
PRZR 1eve1.
00 per for m; RN) step and se1 ect soper ab1 e channel.
00 res tor es char gi ng and 1et doWl as di r ect ed by t he lB.
Feedback:
PRZR 1eve1 does not exceed t rip set poi nt .
WD Reference:
Nme.
Qmdi t ions:
Pri or to a PRZR hi gh 1eve1 react or t ri p.
SID m::: 3 Page 39 Revision 0
EVENT 5 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at pover and a SG PCRV has f ai 1ed
open, the cr ew W11 res pond in accor dance w t h 1- N'- 38,
"Excessive Load Increase."
NORTH ANNA SPECIFIC TASKS:
R539 Perforrnthe innediate operator actions in response to an excessive load
increase.
S70 ENaluate corrpliance wth technical specifications.
CRITICAL TASK:
NA
SID m:: 3 Page 40 Revision 0
EVENT 6 PERFORMANCE OBJECTIVES
EVENT GOAL: a ven t he pI ant i sin Mde 1 w t hindi cat ions of a los s of
"X' Mi n Feed'Wlt er Punp and a f ai I ur e of "B" Mi n Feed'Wlt er
Punp to aut ormt i call y st art, t he crew wI I respond in
accordance wth 1-AP-31, "Loss of Min Feed'Wlter," and 1-E-
0, "React or Tr i p or Saf et y I nj ect ion. "
NORTH ANNA SPECIFIC TASKS:
R781 Respond to a loss of rmin feed'Wlter.
CRITICAL TASK:
NA
SID m:: 3 Page 41 Revision 0
EVENT 7 PERFORMANCE OBJECTIVES
EVENT GOAL: Civen that a rrnin feed suction line has broken, the crew
W11 res pond i n accor dance w t h 1- E- 0, React or Tr i p or
Saf et y I nj ect ion. "
NORTH ANNA SPECIFIC TASKS:
RI85 Perform the il'lIrediate operator actions in response to a reactor trip or
s af et y i nj ect ion.
CRITICAL TASK:
See next page
SXJ m:: 3 Page 42 Revision 0
cr St at errent :
cr ew mmuall y t rips t he React or.
Safety Significance:
Fai lure to mmuall y t rip the react or caus es a chall enge t o t he
s ubcr it i cal i t y (SF beyond that i r r epar abl y i nt r oduced by the pos t ul at ed
conditions. Aiditionally, it constitutes an "incorrect perforrmnce that
neces sit at es the cr ew t aki ng cOIIpens at i ng act i on \'hi ch conpl i cat es the
event nitigation strategy and dermnstrates the inability by the crew to
recognize a failure of the autormtic actuation of the RPS."
I ndi cat i on and! or annunci at i on t hat pI ant par arret er (s) exi s t that shoul d
resul tin aut ormt i c react or t ri p but react or does not aut ormt i call y t ri p.
Perforrmnce Indicator:
ID R:P opens bot h react or t rip br eaker s.
Feedback:
React or t rip br eaker s open, rod bot t om light s lit, I RPI s at zer 0 steps,
react or pover <5%
WD Ref er ence:
E- 0 Backgr ound.
Cbndi t ions:
Pr i or t 0 a trans i t i on t 0 FR- S. 1.
SIDm: 3 Page 43 Revision 0
EVENT 8 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that a loss of all nnin and auxiliary feed vater punps
has occur red, the cr ew w 11 res pond i n accor dance w t h 1- FR-
H 1, "Response to Loss of Secondary !fat Si nk. "
NORTH ANNA SPECIFIC TASKS:
N:me.
CRITICAL TASK:
See Follow ng Pages
SID m:: 3 Page 44 Revision 0
cr St at errent :
G ew stops react or cool ant punps.
Saf et y Si gni f i cance:
Tr i ppi ng the KPs WIen ent er i ng t hi s gui del i ne "... can appr eci abl y del ay
t he need for bl eed and feed and 1os s of secondar y heat sink... " Fai 1ur e
to trip the KPs "... can also reduce the effectiveness of bleed and feed.
ReP heat input to the RCS ~ll result in increased stearngeneration
hi nder i ng the depr es sur i zat i on of the RCS dur i ng bl eed and feed. "
I ndi cat i on of:
- Reactor trip and
- t ot al f eedWlt er flow 1es s than 340 gPI1l and
- all SG 1evel s 1es s than 11 % m
Perforrrance Indicator:
ID Ill' put s cont r 01 s ~ t ch( es) f or all r unni ng KPs i n S1Q>.
Feedback:
I ndi cat i on! annunci at i on of no KPs r unni ng.
WXJ Ref er ence:
fR. H 1 backgr ound docurrent.
Cbndi t ions:
Pr i or t 0 bei ng r equi red to i ni t i at e RCS bl eed and feed.
SID m::: 3 Page 45 Revision 0
cr St at errent :
Gew est abl i shes Feed F1 ow to at I east one SG
Safety Significance:
Failure to establish feedVl8ter flowto any SGresults in the crews
having to rely upon the lover-priority action of establishing RCS bleed
and feed t 0 IIi ni IIi ze cor e uncover y. Thi s cons tit ut es i ncor r ect
per for ml.llce that "I eads to degr adat i on of any bar r i er to f iss ion pr oduct
release. "
EXtrerre (red-path) challenge to the heat sink CSF
Indication that RCS pressure renains above the pressure of all sa
I ndi cat i on that RCS t errper at ur e r enai ns above the t errper at ur e f or pI aci ng
the RlR systemin service
I ndi cat i on and! or annunci at i on t hat no AFWfl ow is avai I abl e aft er
repeated attenpts to establish
-AN)
Level i ndi cat i on that SG dr yout has not yet occur red.
Perfornance Indicator:
Gew di rect s operat or to I ocall y reset terry t urbi ne trip val ve and
es t abl i sh fl ow v.i. t h 1- FWP- 2. BJ> est abl i shes adequat e AFWfl ow as
i ndi cat ed by cor e- exi t ill decr eas i ng and SG v.i. de- range level i ncr eas i ng.
Feedback:
I ndi cat i on of AFWfl ov.( i ncr eas i ng v.i. de- range SG I evel and decr eas i ng
core-exit thernvcouples.
WD Reference:
fR. H 1 Backgr ound docurrent.
Cbndi t ions:
Pr i or t 0 bei ng r equi red toper for m RCS feed and bl eed.
S)G~3 Page 46 Revision 0
Scenario Performance Datasheet
E\ENf 1: a ven the pI ant i sin Mide 1 and the "X' bear i ng cool i ng vat er punp
has t ripped the crew wll respond in accor dance w t h 1- AP- 19, "Loss of Bearing
Cboling Viter. "
SPD \eri fi ed: (I ni t i al s)
- Innunci at or s F- F4, F-E4, F-lE ill uni nat e
- 1- OC- P- lA has a br eaker ni sal i gmrent ( anber and green lights lit)
- 1- OC- P-IB does not aut 0- st art
E\ENf 2: a ven that the uni t is in node 1 and the tredian/select Tave unit has
fai 1ed, the crew w 11 be expect ed to respond in accordance w t h 1- AP-l. 1,
"Chnt i nuous Thcont roll ed Rod Mit ion," and annunci at or s B- KI and B- AS.
SPD \eri fi ed: (I ni t i al s)
- Rods stepping in at Imxi num speed
- Innunci at or s B- KI and B- AS ar e ill uni nat ed
- St at us 1i ght ME4 ill uni nat es
E\ENf 3: a ven that the" uni t is at pov.er and i ndi cat i ons exi st of a loss of
i ns t r Utrent air, the crew w 11 respond in accordance w t h 1- AP- 28, "Loss of
Ins t r Utrent It r . "
SPD \eri fi ed: (I ni t i al s)
- Innunciator lJ-rn i 11 uni nat es
- IA pressure drops
- l-IAGI wll not st art aut OImt i call y, if requi red
- Innunciators J-E8 and F- F8 ill uni nat e
E\ENf 4: a ven that the uni t is at pov.er and a selected pressurizer level
channel has fai 1ed, the crew w 11 be expected to respond in accordance wth
l-AP-3, "Loss of Vi t al I nst rutrent at ion. "
SPD \er i fi ed: (I ni t i al s)
- Innunci at or s B- F8, B-Gl, and B-E2 are i 11 uni nat ed
- l-RC-U-1461 fails low
- Letdo~ isolates
E\ENf 5: a ven that the uni t is in node 1 and the tredian/select Tave unit has
f ai 1ed, the crew w 11 be expected to respond in accordance wth l-AP-l.l,
"Chnt i nuous Thcont roll ed Rod Mit i on," and annunci at or s B- KI and B- AS.
SPD \er i fi ed: (I ni t i al s)
- Rods stepping in at Imxi num speed
- Innunci at or s B- KI and B- AS ar e i 11 uni nat ed
- St at us 1i ght ME4 ill uni nat es
SIDm= 3 Thte _ Revision 0
E\FNf 6: a yen the pI ant i sin M>de 1 v.t t hindi cat ions of a 1os s of "I\.' Mi n
FeedWlt er Punp and a f ai 1ur e of "B' Mi n FeedWlt er Punp to aut ormt i call y
st art, the crew v.t 11 respond in accordance v.t t h 1- PF- 31, "lDss of Min
FeedWit er ," and 1- B 0, "React or Tri p or Safet y Ini ect ion. "
SPD \eri fi ed: (I ni t i al s)
- Irnlunci at or Er H; ill um nat es
- "I\.' M'P br eaker s have anber and gr een 1i ght s 1it
- "B' M'P does not aut 0- st art
- Avai 1abl e feed fl ow is 1ess than st eamfl ow
E\FNf 7: a yen that a rmin feed suction line has broken, the crew v.t 11
respond in accordance v.t t h 1- B 0, React or Tr i p or Safet y I nj ect ion. "
SPD \eri fi ed: (I ni t i al s)
- The react or does not t rip aut ormt i call y, if requi red
- Irnlunci at or s F- B5, GF6, F-Dl, F-rn, F- Il3, F-M, F-BS, F-Fl, F-F2, F-F3,
C- CB i 11 um nat e
- Min feed punp suction pressure rapidly decreases
- Standby rmin Cbndensate punp starts
- \ari ous t urbi ne bui 1di ng sunp al arm ill um nat e
E\FNf 8: a yen that a loss of all rmin and auxiliary feed Witer punps has
occurred, the crew v.t 11 respond in accordance v.tth I-FR-H 1, "Response to
lDss of Secondary ~at Sink. "
SPD \er i f i ed: (I ni t i al s)
- Irnlunci at or s F- ~ ill um nat es
- ~ fl ow i ndi cat ed to" I\.' SG
- A ow from 1- FWP- 3B is not reaching the ffB" sq VR 1evel decreasing
- 1- FWP- 3A degr ades and fl ow dr ops to zer 0
SXJ37 Thte _ Revi si on 7
Appendix D Scenario Outline Form ES-D-1
Facility: North Anna Scenario No.: 4 Op-Test No.: 1
Examiners: Mark Bates Operators:
Mark Riches
Initial Conditions: Unit at approximately 22% power with ramp held to allow turnover. Unit was returned to service
last shift after an outage to repair a leak on the EHC interface valve. 1-FW-P-2 (terry turbine) was tagged out
during the outage and was just returned to service. The letdown radiation monitor is OOS. 2-CC-P-1A is tagged
out for seal maintenance. Control rods are in Manual while I&C verifies proper operation due to a prior problem.
Turnover: Shift orders are to ramp unit to 100% power.
Event Malf. No. Event Event
No. Type* Description
R (R) (S)
1 Commence ramping unit to 100% power
N (B)
C (R) (S)
2 RC29 Master pressure controller fails high causing PORV and sprays to open
TS (S)
I (B) (S)
3 FW0106 Failure of "B" SG channel III level transmitter
TS (8)
4 NI0104 I (R)(S) N-44 failure
4a N (R) (S) N-44 is placed in trip
5 EL09 C (B) (S) Main Generator voltage regulator fails
"B" SGTL increasing until reactor trip is required. (Turbine does not trip
6 RC2402 C (All)
automatically.)
6a RC1201 C (R) (S) Seal leak on "A" RCP after reactor. trip
7 RC2402 M (All) "B" SGTR after unit stabilized from trip
8 TU03 C (B) (S) Turbine does not trip automatically
Terminate scenario once crew completes cooldown in E-3
(Event 8 occurs during event 6 and is numbered only for use on Forms
301-5 and 301-6.)
- (N)ormal, (R)eactivitv, (I)nstrument, (C)omponent, (M)ajor
IXMNCN
N:RIH At-N\. PCJJfR STAll CN
IN 11 PL U CFNifI) CPmAltR EXAMN\1I CN
SCFNARI 0 m::: 4
E\ofNf IESCRI Pll CN
1. Cbnmmce r anpi ng uni t t 0 100% pover
2. Mster pressure controller fails high causing PCRVand sprays to open
3. "B' SG channel II I 1evel t r ansni t t er f ai 1slow
4/4a. N 44 f ai 1sand is pI aced in t rip
5. Mi n Gner at or vol t age r egul at or f ai 1s
6 "B" SGIL i ncreasi ng unt i 1 react or t ri pis requi red. Turbi ne does not
6a trip aut ormt i call y. KP seal fai 1ure.
7. "B' SGIR
Scenar i 0 F£capi t ul at ion:
Mlfunctions after BOP 2 (Failure of turbine to trip autormtically, KP seal
entry failure)
Total Mlfunctions 8 (Ms t er pr es sure cont roll er f ai 1s hi gh, SG 1evel
channel fai 1s 1 o~ N44 fai 1s, MJ \R. fai 1s, SGIL
r equi ring react or t rip, SGIR, f ai 1ur e of t ur bi ne t 0
trip autormtically, KP seal failure)
Pbnor rml Event s 5 (Mster pressure controller fails high, SGlevel
channel f ai 1s 1o~ N 44 f ai 1s, MJ \R f ai 1s, SGIL
requi ri ng react or t ri p)
Mj or Tr ansi ent s l(SGIR)
BJ>s Ent er ed 2 (ES-O.1, E-3)
BOP Cbnt i ngenci es o
CI it i cal Tasks 5
S~ 0 Il..lWI CN
120 ninut es
SXJNC 4 Page 2 F£vision 0
SIMULATOR EXAl\fiNATION SCENARIO SUMMARY
SCENARIO NRC 4
Scenar i 0 begi ns w t h the uni t at appr oxi ml.t el y 22% pover w t h a pover
increase held for turnover. lhit WiS returned to service last shift after an
outage to repair a leak on the EI-I: interface val ve. The terry turbine WiS
tagged out during the outage and has just been returned to service. The
let doWl r adi at i on mmi t or i s ill. 2- CI- P- lA is tagged out for seal
ml.intenance. Shift orders are to ranp to 100% Gmtrol rods are in ml.nual
~ile the instru~nt shop verifies proper operation due to a previous problem
The cr ew w II i ncr eas e react or pover i n accor dance w t h 1- CP- 2. 1, "lhi t
St art up from Mlde 2 to Mlde 1."
Glce a sat i sf act or y r anp has been obs er ved, the PRZR ml.S t er pr es sure
cont roll er w II f ai I caus i ng 1- K::- PC\L 1455C and bot h s pr ay val ves t 0 open. The
lS should direct the crew to enter l-PIJ-44, "Loss of R::s Pressure." The 00
wll ml.nually close l-K::-PC\L1455C and use the ml.ster pressure controller to
close the spray valves. Glce the crew has stabilized R::s pressure and
consulted Tech Specs, or at the direction of the lead evaluator, the next event
wll occur.
G1anneI III level transnitter for the "B' steamgenerator wll fail 10Vl
The crew should identify this failure and take ml.nual control of the "B" ml.in
feed reg. val ve to restore level in the "B" SG The crew should enter l-PIJ-3,
"Los s of \1 t al Ins t r u~nt at ion," and ref er tot echni cal s peci f i cat ions to
deternine operability of the transnitter. Glce the crew has identified the
applicable ~ and referred to Tech Specs, the next event wll occur.
1'ext, N.1cl ear Ins t r u~nt channel N 44 wll f ai I hi gh caus i ng the cont r 01
rods to drive in at ml.xinum speed. The 00 nust identify N44 as failing and
place rod control in ~ The crew wll enter l-PIJ-4.3, "Mlfunction of
Nlcl ear Ins t r u~nt at i on (Pover Range)," and pI ace N 44 i n t rip (N)r ml.1 event).
The lS shoul d revi ew Techni cal Speci fi cat i on 3.3. 1. lit er N 44 has been
pi aced in t rip, t he next event w II occur.
The ml.i n gener at or vol t age r egul at or wi I f ai I and the cr ew wll be
expect ed tor es pond in accor dance w t h 1- PIJ- 26, "Los s of Mi n Qner at or \bl t age
Gmt rol." The I(p wll t urn off t he volt age regul at or and cont rol vol t age
using base adjust. liter generator voltage has been brought under control, the
next event w II occur.
A tube leak wll occur on "B' SG The first indication wll be the N16
radi at i on mmi t or for "B" SG i ndi cat i ng increased I eakage. The lS shoul d
direct the crew to enter l-PIJ-5, "lhit 1 Radiation Mlnitoring System" and
di r ect IF/ G1eni s try to obt ai n and anal yze a "B" SO bl OwiOWl s anpl e.
Event uall y, the ml.i n st eani i ne header N 16 rroni t or i ndi cat i on wi 1 increase and
SID NC 4 Page 3 Revi si on 0
the cr ew v.i. 11 have backup i ndi cat i on of a tube 1eak in the "B" SG Bas ed on
conf i r tred 1eakage, the lB s houl d di r ect the cr ew to ent er 1- Pl?- 24, "St earn
~ner at or Tube Leak." The tube 1eakage v.i. 11 i ncr eas e unt i 1 a react or t rip is
neces s ar y. The cr ew v.i.ll ent er 1- E- 0, "React or Tr i p or Safet y I nj ect ion." The
turbine v.i.ll not trip autormtically and lIDst be tripped rmnually using the
pushbut tons. FoIl ov.i. ng a t r ansi t i on to ffi- 0. 1, "React or Tr i p Response," the
" !\' KJ> v.i. 11 develop a seal f ai 1ur e and the cr ew v.i. 11 need t 0 s ecur e i t and
close the seal leakoff valve per 1-Pl?-33.1, "Reactor Cbolant Punp Seal
Fai 1ure. "
~xt a SGIR v.i. 11 develop i n the "H' steam gener at or. FoIl ov.i. ng
i dent i f i cat i on of degr adi ng pri rmr y pI ant condi t ions the cr ew v.i. 11 rmnuall y
s af et y i nj ect and trans i t i on back to E- 0, "React or Tr i p or Saf et y Inject ion. "
The crew v.i.ll proceed through E-O and transition to and perform E-3, "Steam
~nerat or Thbe RIpt ure. " The crew v.i.Il cool doWl the R:S to the requi red
tenperature using B-3. It this titre the scenario can be terninated.
SIDNC 4 Page 4 Revi si on °
Pre-job Brief for Scenario NRC-4
Unit Status:
Unit 1 is at approximately 22% power. The unit was returned to service last shift after an
outage to repair a leak on the EHC interface valve. The ramp was held for turnover. RCS
boron is 1412 ppm and core age is 9000. Aux steam is on unit 2.
Unit 2 is at 100% power.
Equipment Status:
Letdown rad monitor, 1-CH-RM-128, is OOS. 2-CC-P-IA is tagged out for seal
maintenance. 1-FW-P-2, terry turbine, was tagged out during outage and has just been
returned to service. Control rods are in manual while the instrument shop verifies proper
operation due to a previous failure. I&C is currently monitoring rod motion and will infonn
the crew when rods may be returned to auto. The maintenance rule window is green.
Shift Orders:
Ramp the unit to 100%.
Ramp Directions
Reactor engineering estimates it will take approximately 6500 gallons of PG to return the
unit to 100% power. -
Approximate rod positions:
160 steps at 50% power
178 steps at 75% power
L
202 steps at 90% power
AFD limits: 50% power -27/+20
100% power -12/+6
SCENAlUOTURNOVERSHEET
Read the following to the crew:
Purpose: This exanination is intended to evaluate the crews perforrnmce of
various tasks associated wth the licensed QJerator Training
Pr ogr am I'll act i vi ties shoul d be conpl et ed in accor dance w t h
approved operations standards.
1. You are on a day shift during the veek.
2. A rough log shoul d be rmi nt ai ned to ai din rmki ng report sand to hel p duri ng
bri efs.
3. Respond to ~at you see. In the unlikely event that the sinulator fails
such that illogical indications result, the session wll be terninated and
the cr ew i nf or rred.
Unit Status:
lhit 1 is at approxirmtely 22%pover. The unit WlS returned to service last
shi ft aft er an out age tor epai r a I eak on the B-C i nt er face val ve. The r anp
WlS held for turnover. RCS boron is 1412 pprnand core age is 9000. Aux steam
is on uni t 2.
lhi t 2 is at 100% pover.
Equipment Status:
Let doWl r ad IIDni t or, 1- rn RM 128, i s ill. 2- CC- P- 1A is tagged out for seal
rmintenance. 1-FWP-2, terry turbine, WlS tagged out during outage and has
just been ret urned to servi ceo Cbnt rol rods are in rmnual ~i let he i nst rurrent
shop verifies proper operation due to a previous failure. I8C is currently
IIDnitoring rod IIDtion and wll informthe crew~en rods rmy be returned to
aut O. The rmi nt enance r ul e w ndow i s gr een.
Shift Orders:
Ranp the uni t to 100%
SID m::: 4 Page 5 Revision a
E\mf 1: G ven that the urn t is at approxi nut eI y 22% po~r and it is desired
to increase react or po~r, t he crew wI I r arrp t he uni t in accordance w t h 1-
CP- 2. 1, "Urit 5t art up Mlde 2 to Mlde 1. n
TI~ ~FCIED !Cll CN I 1'S1Rl..CfCR ~
SPD \eri fi ed: (I ni t i aI s)
- Reactor po~r increases
- Turbine po~r increases
- Tavg/Tref increase
- Gner at or out put increases
NOTE: The crew may raise primary
temperature prior to ramping the
turbine.
B::P adj ust s Ii ni t er posi t ion, as
requi red.
B::P verifies/sets desired rarrp
rate (. 3%per ninute).
B::P increases turbine setter to
desired position.
B::P presses CD on t urbi ne.
B::P mmi t or s t ur bi ne r arrp.
00 star t s a di 1ut i on Wlen n 1ut i on CIPs i ncl uded at back
requi red. of scenari 0
00 w. t hdr a\lS cont rol rods to
nui nt ai n Tave w t hi n 1. 5°F of Tref
w. t h rods above insert i on 1i ni t s.
NOTE: The next event can occur once
the crew has ramped approximately 5 %
as determined by the lead evaluator.
SID m:: 4 Page 6 Revision 0
E\-ENf 2: a ven the uni t is at po\l.er and the PRZR pressure rmster controller
fai 1s hi gh, the crew \\ill res pond i n-' accor dance \\i t h 1- ftP- 44, "Loss of
React or (bol ant Syst em Pressure. "
1l~ EXPF£IID K:TI eN I Ni'IRIl:TCR RB\MKS
SPD \eri fi ed: (I ni t i al s)
- Itmunci at or B- F.6 i 11 urri nat es
- Ms t er pr es s ur e cont roll er f ai 1s high
- 1-RC-PC\'-1455C indicates open
- RCS pressure decreases
NOTE: The crew should stop the ramp
and dilution once immediate actions
have been completed. Note that primary
temperature will continue to increase
until all the dilution water has made it to
the reactor.
crew i dent i fi es annunci at or B- F.6,
PRZR PRESS CINf H GJIPUf.
lB di r ect s cr ew t 0 ent er 1- ftP-44.
RO veri fi es PRZR PCR\S cl osed.
(~
CTI Crew stops RCS pressure Critical Task
decrease: Pr i or t 0 a react or trip on low
pressure
- RO closes 1*RC*~CV.:t4S5Cj
- RO checks rmster pressure
cont roll er cont roll i ng
proper 1y. (~
- RO places master pressure
controller to manual and adjusts to
stabiUze anel restore PRSSU(~.
RO veri fi es PRZR spray val ves
cl osed.
RO veri fi es all PRZR heat er s
energi zed.
RO veri fi es auxiliary spray valve
cl osed.
crew veri fi es PCRVand safet y
val ves cl os ed.
ROverifies RCS pressure stable or
i ncr eas i ng.
SIDNC4 Page 7 Revi si on 0
E\ENf 2: a ven the uni tis at pover and the PRZR pr es sure Il1lS t er cont roll er
fai 1s hi gh, the cr ew W 11 res pond i n accor dance w t h 1- JiP- 44, "loss of
React or 0::l01 ant Syst em Pressure. "
1II\E EXPECIID 1CIl CN I NilRlITCR ~
00 ver if i es RCS pr es sure nor Il1l1
and adj usts sprays or heaters, as
requi red.
US refers to Technical Specifications:
3.4.1A- I:N3 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore
pressure to wthin aIR liIIits
(>2205 ps i g)
3. 4. 13A (RCS Leakage) - 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> s t 0
res t or e 1eakage tow t hi n 1i IIi t s
TS 3.4.11. Tht er IIi nes that PCRV
i soper abl e.
NOTE: WCC will inform the crew
during this time that rods may be
returned to AUTO. (This will restore
auto temperature control and set up for
Event 4.)
CI ew eval uat es Il1l1 f unct i on and
requests a ~rk request and
condi t i on r epor t be s ubIIi t ted.
NOTE: The next event will occur after
the crew has stabilized RCS pressure
and consulted Tech Specs, or at the
direction of the lead evaluator.
SXi~4 Page 8 Revision 0
E\fNf 3: a ven that the uni t is at pov.er and a stearn gener at or level
trans ni t t er has f ai I ed, the cr ew v.i II be expected to respond in accordance
v.i t h 1- ftP- 3, "Loss of Vi t al Ins t r unent at ion. "
TIM: I*>FCIID tCII CN I l'S'IRI.DtR ~
SPD \eri fi ed: (Ini t i al s)
- Innunci at or s F- F2 and F- B2 ar e ill uni nat ed
- "B" Channel III SG level i ndi cat or is readi ng of f - s cal e I ow
- "B" MRV i s r anpi ng open
R:P i dent i f i es annunci at or IF-F2,
SG IB IE\EL ~
R:P identifies "B" MRV is ranpi ng
open.
lB directs entry into l-ftP-3.
Gew i dent i fi es "B" SG level
channel III has failed low
G ew checks redundant
ins t r unent at i on nor nal .
G ew checks SCN£.C par anet er s
nornal. (l'Q
R:P takes nanual cont rol of the
Gew veri fi es fi rst - st age pressure
i ndi cat ions nor nal .
ID ver i fi es s yst em affect ed by
PRZR level channel s nor nal :
- ID veri fi es oper abl e
pressuri zer level channel
selected
- ID veri fi es letdo~ in service
- IDverifies pressurizer level
cont rol in AJID
- ID ver i f i es cont r 01 group
heat er s ar e not t ri pped.
G ew ver if i es bot h t ur bi ne fir st
stage pressure channels nornal.
G ew ver if i es oper abl e channel s
selected for S~
Gew veri fi es that no other
ins t r unent at i on has f ai led.
SID m::: 4 Page 9 Revision 0
E\mf 3: a ven that the uni tis at pover and a stearn gener at or 1evel
t r ansni tt er has f ai 1ed, the cr ew W11 be expect ed tor es pond in accor dance
Wth l-.AP-3, "los s of \H al lnst rutrent at ion. "
11M3 EXPFCIID JCII eN I Ni'IRl.CKR ~
US references technical specifications:
3.3.1 Functions 14 and 15,
Cbndition E - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place
channel in trip
3.3.2_Functions 5b and 6b,
Cbndition D~ 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place
channel in trip
3.3.3 (Function 15) Info action
Gew i dent i fi es 1- MP- 55. 76.
lS inform; V0rk Cbntrol cent er of
failure and requests VR, CR, and
craft assistance.
NOTE: The next event will occur after
the crew has identified the appropriate
MOP, or at the direction of the lead
evaluator.
SID m:: 4 Page 10 Revision 0
E\ENf 4: a ven that the uni t is st ab1 e at pover and pover-range channel N44
has failed high resulting in rods stepping in, t he crew v.i 11 respond in
accor dance v.i t h 1- AP- 4. 3, "Mlfunct i on of Nlcl ear Inst rurrent at i on (Pover
Range). "
TI~ EXPECIID 1CI1 CN I N)'IRlCIffi ~
SPD \eri fi ed: (I ni t i a1 s)
- N 44 i ndi cat es > 120%
- Qmtro1 rods step in at rmxi rrum speed
- RCS pressure and TAVE decrease
NOTE: Verify control rods are in AUTO
before this event.
RO i dent i f i es cont ro1 rods
st eppi ng in.
ROidentifies N 44 f ai 1ed hi gh.
lB directs entry into l-AP-4.3.
CT2 Crew stops control rod movement Critical Task
due to N-44 failure. *Pr i or tor od 1 0- 1 0 insert i on
1i ni t
- Gew veri fi es pover not
i ncr eas i ng:
- ao places rod controlln~All.
- BCP verifies bypass NFRvs in
rmnua1.
Gew veri fi es three pover- range
ins t r urrent soper ab1 e.
Gew ver i fi es uni t in rmde 1.
Gewverifies 1- hour per ni ssi yes
for Tech Spec 3.3.1:
- Function 18b - P-7 pernissive.
P-Q NJf UT since >lO%pover
- Function 18c - P- 8 perni ssi ve.
P- F1 v.i 11 be UT si nce <30 %
pover
- Function 18d - P-lO perni ssi ve.
P- rn v.i 11 be UT since >10%
SID~4 Page 11 Revision 0
~4: a ven that the uni t is stable at pover and pover-range channel N44
has fai I ed hi gh resul t i ng in rods st eppi ng in, the crew w.11 respond in
accor dance w. t h 1-..AP- 4. 3, "MI f unct i on of Nlcl ear I us t r ummt at i on (Pover
Range) . "
1l~ EJalInID tCII CN I 1'S1Rl.CI(R ~
RO pi aces N 44 i n trip. N:>rrml event
- N44 is selected on Cbnparator
Channel Thfeat
- N 44 i s def eat ed on Rod St op
Bypass
- N44 is defeated on tpper
section
- N 44 i s def eat ed on Lover
section
- Cbnt rol pover fuses are
reIIDved.
Gew verifies/selects N43 on the
N 16 panel.
G ew checks react or pover gr eat er
than 5% and reIIDves conput er
poi nt s from scan.
Gew not i fi es cherri st ry N44 input
to a..cMl is umel i abl e.
US reviews Technical Specifications:
3.3.1 Functions 2a, Cbndi t i on D
and 3a and 3b, Cbndi t i on a
requi re channel t 0 be pi aced i n
t rip w t hi n 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> s .
Q7IR wll be required once per 12
hour s men pover i s >50% Info
act i on onl y.
G ew ver i f i es N 44 pI aced in trip
w t hi n 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> s .
RO veri fi es Tave and Tref rmtched
w t hi n 1. 5°F.
NOTE: If asked about method for
restoring Taveffref, booth will ask for
suggestion and agree with whatever
sU22ested.
Gew adj ust s Tave/Tref, as
requi red.
NOTE: Crew may leave control rods in
manual. Booth will agree with whatever
they recommend.
SID m::: 4 Page 12 Revision a
~4: G ven that the uni tis s t abl e at pover and pover - range channel N44
has failed high resulting in rods stepping in, the crew w 11 respond in
accordance wth l-AP-4.3, "Mlfunction of NIclear Instrurrentation (Pover
Range). "
1lT\E EXPPCIID ICJ1 eN I l\S1Rl.CfCR ~
G ew det er ni nes i f rod cont r 01
should be placed in AUnJ
lS report s fai 1ure to V0rk Gmt r~l
cent er and r eques t s VR, rn, and
craft assistance.
NOTE: The next event will occur after
the crew places N-44 in trip, or as
directed by the lead evaluator.
SID m::: 4 Page 13 Revision 0
EVENT 5: a ven that the uni tis at pover, and the rmi n gener at or vol t age
r egul at or has f ai 1ed, t he cr ew W11 be expect ed tor es pond i n accor dance w t h
1- N!- 26, "Loss of Min Gnerator \bl tage Qmtrol. "
1I~ ~OCIID ICll CN I 1'S1Rl.ITCR ~
SPD \eri fi ed: (I ni t i al s)
- Itmunci at or s K- m and K- C1, and K-O ill urri nat e
- Gner at or out put voltage increases
RP i dent i f i es annunci at or K- m,
INI 1FR A H.D FCRJ N:i
lS di rect sent ry i nt 0 1- N!- 26.
RP i dent i f i es gener at or out put
voltage and MVARS increasing wth
MVst abl e.
RP places voltage regulator
control sw tch to CFF.
Q ew not i f i es s ys tern oper at or .
lS request s V0rk Cbnt rol cent er
super vi sor to inform t he CM:C of
the f ai 1ur e and to i ni ti at e VR and
CR
NOTE: The next event will occur after
the crew has stabilized the plant, or at
the direction of the lead evaluator.
S){J~ 4 Page 14 Revision 0
- E'\FNf 6/ 6a: a ven that the uni t is at po~r and indications exist of a SG
tube leak and a #1 seal fai 1ure on an ReP, t he crew \\i 11 be expect ed to
res pond i n accor dance \\i t h 1- fiP- 5, "lhi t 1 Radi at i on Mni t od ng Sys t eIll " 1-
fiP-24, "St earn Gner at or Tube leak," 1- E- 0, "Reactor Trip or Safety
Injection," and l-fiP-33.1, "ReP Seal Fai 1ure. "
TIM: EXPECIID ICll CN INnRl.CKR~
SPD \eri fi ed: (I ni t i al s)
- I-M-RI-191, "B" SG N 16, in ..AI ert
- I'llnunci at or :& CO i 11 uni nat ed
- I'llnunci at or :& CO r efl as hes
- Indications of increasing leakage on all N16 RM
- Olar gi ng flow slow y increases
- Later: I'llnunci at or s C- GI and C- G5 ill uni nat e
- "X' ReP seal 1eakoff fl ow i ndi cat i on is pegged hi gh
RO' ffP i dent i f i es annunci at or :&
CO, N 16 RAJ) rEf.
G ew i dent i f i es an ..AI er t al ar rn on
I-M-RI-191, "B" SG rmi n stearn i ne
N 16 r adi at i on nDni t or.
NOTE: US may not immediately break
off an operator to address l-AP-5. AP-
24 steps are on followin2 pa2e.
lB di rect sent ry i nt 0 1- fiP- 5, "lhi t
1 Radi at i on Mni t or i ng Sys t em "
and! or 1- fiP- 24, "St earn Gner at or
Tube leak. "
STA i s not i f i ed to eval uat e SG AP-5 steps
1eak rat e trend dat a.
NOTE: If crew requests HP to perform
local radiation surveys on the MS lines,
HP will inform the crew that contact
readings on the "B" MS line are slightly
elevated.
lB notifies the cps ~nager or
cperations ~nager Ch ChI 1 (CMQ.
G ew nDni t or s r adi at i on on N 16
trend r ecor der and det er ni nes
leakage is increasing.
Gew i dent i fi es i ncreasi ng
r adi at i on on rmi n stearn i ne header
N 16 r adi at i on nDni t or.
lB di r ect s cr ew to i ni t i at e the 1-
fiP- 5 at t achrrent for nDni t or i ng
prirmry to secondary leakage, and
ent er 1- fiP- 24.
SID m:: 4 Page 15 Revision 0
E\-fNf 6/6a: a ven that the uni t is at po~r and indications exi st of a SG
tube leak and a #1 seal fai 1ure on an RCP, the crew VIi 11 be expected to
res pond i n accor dance VIi t h 1- JiP- 5, "lhi t 1 Radi at i on Mni t or i ng Sys t elI} " 1-
JiP-24, "St earn Gner at or Tube Leak, " 1-&0, "React or Tri p or Safet y
Ini ection, " and l-JiP-33. 1, "RCP Seal Failure. "
1lt.E EXPH:1ID 1Cll CN I mIRJ.ntR REMRI ver if i es PC eIrer gency bus ses
ener gi zed.
Q-ew checks if SI has act uat ed.
Q-ew checks if SI is requi red.
(~
lS di r ect s trans it i on to 1- ES- O. 1.
Q- ew i ni t i at es IIDni t or i ng of
cr i tical safety function status
trees.
- K> checks RCS Tave st abl e at or
trending to expected value.
OCP adj ust s AFWfl ow as requi red
SIDm: 4 Page 16 Revi si on 0
E\oENf 6/6a: a ven that the uni tis at pover and i ndi cat ions exi s t of a sa
tube I eak and a #1 seal f ai lure on an KP, the cr ew wII be expect ed t 0
respond in accordance w t h 1- /JP- 5, "lhi t 1 Radi at i on Mmi tori ng Syst em" 1-
/JP- 24, "St earn Gmer at or Tube Leak," 1- E- 0, "React or Tr i p or Saf et y
I ni ect ion," and 1- /JP- 33. 1, "KP Seal Fai lure. "
NOTE: After AFW flow has been
adjusted, "A" Rep will seal leak will be
inserted, it has a 3-minute time delay.
RO i dent i f i es annunci at or s G GI Thes e al ar m star t the 5-
KP lA B- C SEAL J..F..AK H FLO.V and IIi nut e t i ner for cr 3
G 05, KP lA B- C SI¥Ff SEAL \WER
lDIP.
RO identifies "I\' KP seal leakoff
flow is pegged hi gh.
lS di rect screw to ent er 1- /JP-
33.1.
G ew det er IIi nes RCP nus t be
tri pped:
Checks seal delta P <200 psid
CR
OOIH of t he f oil ow ng
Seal I eakoff fl ow >5. 9 gpm
AN)
G GI U T and VAI.1 D bas ed on:
- Seal return terrperature
- Lover radial bearing
t errper at ur e
- Paraneters on other RCPs
- Ther rml bar r i er t errper at ur e
- Seal delta P
- KP vibes/current
- ~Ita T betveen Seal Return
and lover radial bearing
- Change i n oc:s rms s f I ow
bal ance par anet er s : PRlR level
decrease, Charging flow
increase.
SIDNC 4 Page 17 Revi si on 0
E\ENf 6/6a: G ven that the uni t is at pover and indications exi st of a SG
tube I eak and a #1 seal fai I ure on an KP. the cr ew w II be expect ed t 0
res pond in accor dance w t h 1-.*"PP- 5. "lhi t 1 Radi at i on Mni tori ng Syst em" 1-
JiP- 24, "St earn Cbner at or Tube Leak, " 1- Er 0, "React or Tri p or Safet y
Ini ect ion," and l-JiP- 33.1, "KP Seal Fai lure. "
TIM: EXPlDID ICII CN I~~
CT3 Crew isolates affected Reactor Critical Task
Coolant Pump sealleakoff *RCP should be tripped and
seal leakoff valve should be
- frew t ri ps uN OCP.-l
- frew cl os-es l-GlH:\L 13091\ #~ i ni t i al wthin
closed
seal
five ninutes of
fai lure.
sea.} 1eakoff val ve once t he "!{
KP i.ndicates stoB .'.
- Gewcloses spray valve l-R:::-
PC\'-1455A
18 report s seal fai lure to V0rk
Gmtrol center and requests ~
rn, and craft assi st ance.
18 announces continuation of ES-
0.1.
NOTE: The following steps are from 1-
AP-24. The US may assign one of the
operators to continue in this procedure
while directing the other operator in the
EOPs.
NOTE: The crew may not have
identified which SG was leaking before
the reactor trip. This may take lIP
assistance with surveys or samples.
I dent i fy rupt ured sa AP-24 steps
Checks SG i'R level 1 ncr eases
H gh radi at i on on SG st earn i ne RM
(170/171/172 located behind LVV
panel)
H gh r adi at i on on SG bl OwlOWl RM
( 122/ 123/ 124)
H gh act i vi t y on any SG s anpl e
Local cont act r eadi ngs .
PI aces "B" SG PCRV set poi nt at
1005 psig and verifies it is
cl osed.
a oses "B" MTv.
I ni t i at es at t achrrent for M\H
\erifies SG Bl OwlOWl N are
cl osed.
SIDNC 4 Page 18 Revi si on 0
EVFNf 6/6a: G ven that the uni t is at pover and indications exist of a SG
tube leak and a #1 seal failure on an RCP, the cr ew VIi. 11 be expect ed t 0
res pond i n accor dance VIi. t h 1- Pf'- 5, "lhi t 1 Radi at i on Mmi tori ng Syst elI}." 1-
Pf'-24, "St earn Omer at or Thbe Leak," 1- E- 0, "React or Tri p or Safet y
I nj ect ion," and 1- Pf'- 33. I, "RCP Seal Fai 1ure. "
TIM: EXPEaID ICIl CN INnRlITCR~
Mmi tors "B" SG 1evel and isolates
PFWfl ow vhen 1evel is >11%
Tht er IIi nes that ai r ej ect or s do
not need to be diverted to
cont ai mrent .
Ilrects securing high capacity ED
and has turbine building surrp
purrps stopped.
Contacts IF for turbine surrp
purrpi ng r equi r eIrent s.
His aux stearntransferred to lhit
2.
NOTE: The next event will occur once
the Rep is stopped and auxiliary feed
flow has been throttled, or as directed by
the lead evaluator.
SXJNC4 Page 19 Revi si on 0
E\ENf 7: a ven that the uni t is shut doWl f 011 ow ng a react or t rip, and
indications exist of a SGIR, the crew w II be expected to respond in
accor dance w t h 1- B- 0, "Reactor Trip or Safety Inj ection, " and 1-&3, "Steam
Gmer at or Tube Rupt ure.
1If\E FJa?JnID ICIl CN I Ni1RlCIrn. ~
SPD \eri fi ed: (I ni t i al s)
- liB" SG level increases unexpectedly
- Pressuri zer 1evel and pressure decreases unexpectedly
Gewobserves indications that the
SG tube 1eak has v.or s ened.
lB directs entry into l-E-O.
RC.Y B:P ver i f Y react or t ripped.
IlP ver i f i es t ur bi ne t rip.
RO ver i f i es IC errer gency bus s es
ener gi zed.
NOTE: l-AP-24 is no longer applicable
once SI has been actuated.
Gew mmuall y act uat es SI.
B:P verifies feedvater i sol at ion:
- MR\S closed
- MRB\S cl osed
- ~in feed ~ closed
- St andby MP i n PIL
- ~in feed punps tripped
- NFP discharge ~ closed
- SG BD N cl osed.
Gew veri fi es phase A i sol at ion:
- ~nually initiates Phase A
- I ni t i at es It t achrrent to veri fy
i sol at ion.
IlP verifies AFVVpurrps are
runni ng, as r equi red.
Gew veri fi es SI purrps are
runni ng.
G ew checks if rmi n steam i nes
shoul d be i sol at ed.
G ew ver i f i es SI fl ow
IlP verifies AFVVflow
SIDNC4 Page 20 Revi si on 0
EWNf 7: a ven that the unit i s shut doWl foIl ow ng a react or trip, and
indications exist of a S~ t he crew w II be expect ed to respond in
accor dance w t h 1- E- 0, "Reactor Trip or Safety Injection," and 1-&3, "Steam
Gner at or Thbe :&1pt ure.
TII\E EXPECIID ICTI CN I Ni1RI.I:TCR ~
RO checks RCS average t enper at ur e.
RO checks pr es sur i zer PCR\S and
spray val ves.
- PCR\S cl osed
- Spray valves closed
- Pi: leas tone PCRV block val ve
open.
RO checks ReP t rip and char gi ng
punp reci rc cri t eri a:
Subcool i ng < 25°F. (tq
CI ew checks SO; not f aul ted. (YES)
CIew checks SG tubes not r upt ur ed.
(tq
lB directs transition to l-E-3. ,
RO checks ReP t rip and char gi ng E-3 steps
punp r eci r c cr iter i a:
Subcooling < 25°F. (tq
CIew i dent i fi es "B" SG as the
rupt ured SG
NOTE: Crew may have closed I-FW-
MOV-IOOB earlier in the scenario. SG
level >11 %.
SXJm=4 Page 21 Revision 0
EWNf 7: G ven that the uni t is shut doWl follow ng a react or trip, and
i ndi cat ions exi st of a SGIR, the cr ew wll be expected to respond in
accor dance w t h 1- E- 0, "React or Tri p or Safety Injection," and I-B3, "Steam
Gmer at or Thbe ~pt ur e.
TIl\E EXPEI:TID PCII eN I Ni1RI.CICR ~
CT4 Crew isolates ruptured SG by Critical Task
performing/directing the * .Mis t be done before a
following: trans i t ions t 0 1- EC'A 3. 1, SGIR
w t h Los s of React or Cool ant,
- Il:P adj us t s "B" SG PCRV
Subcooled Recovery ~sired,
set poi nt at 1050 PSIG
becorres necessary
- Il:P checks "B" SG PCRV cl osed
- Crew iititiat& attaclmient for MsW
isolation local' actions
- 00 checks decay heat reI ease
val ve cl os ed
- Il:P verifies "B" SG bl OwlOWl
val ves cl osed
- BOP closes "B"-SG MSTV and
bypass valv~
- BOP closes ~':MOV.100B:;Vh~J!
"B" SG level >11 %.
Q ew i ni t i at es at t achrrent for
t urbi ne bui 1di ng act ions.
- 00 checks PRZR. PCRvs and block
val ves.
- Po~r available t 0 PCRV block
valves
- PCRvs cl osed
- Pi 1east one PCRV block val ve
open.
- Il:P checks i nt act SG level s:
- Level in at I east one SG >11%
- Cont rol 1evel bet~en 23 and
50%
00 reset s bot h t r ai ns of SI.
SIDm2 4 Page 22 Revision 0
E\ENf 7: a ven that the uni tis shut doWl foIl oVli ng a react or t rip, and
i ndi cat ions exi st of a SGIR, the cr ew VIi 11 be expect ed tor es pond in
accordance Vlith l-E-O, "Reactor Trip or Safety Injection," and 1-&3, "Steam
Gnerator Tube ~pture.
11 M: EXPECIID ICII eN
CIew ~l i gns ai r ej ect ors to
cont ai rurent :
- CIew reooves fuses fromPE RM
- RO reset s phase A
- CI ew pI aces Condens er PE di ver t
to cont ai rurent SI res et
s VIi t ches to RESEr
- CI ew ver i f i es val ve a1 i gnrrent :
1- S\'-1\'- 102- 1 open, 1- S\'-1\'- 103
open, and 1- S\'-1\'- 102- 2 cl os ed.
- CIewopens st earn supp1 y to ai r
ej ect or s, 1- PS- FCV-- 100A and
100ft
Bl' est ab1 i shes I At 0 cont ai nrrent :
- verifies an air corrpressor is
supp1 yi ng IA
- ver if i es 1- I A-1\'- 102A and 102B
are open.
CIew veri fi es fl ow from liB" SG
i sol at ed:
- Procedure step 3 corrp1ete
- Pt t achrrent 7 corrp1 et e through
step 3
- ~pt ured SG pressure >350 psi g.
NOTE: Either or both of the following
SI signals may need to be blocked at this
or a subsequent time. This is a
continuous action step.
SIDNC 4 Page 23 Revision 0
E\ENf 7: a ven that the uni tis shut doWl follow ng a react or trip, and
i ndi cat ions exi st of a SGIR, t he crew w 11 be expect ed to respond in
accordance wth 1-E-0, "Feactor Trip or Safety Injection," and I-Pr3, "Steam
Gmer at or Thbe Rupt ur e.
- 00 checks i nt er lock blocks and
blocks SI signal s W1en r equi red.
Clleck PRZR pressure 1ess than
1950 psig IF so then:
\erify P-Gl is UT, if NJf
then:
PI ace bot h Low PRZR
pressure SI
block sw t ch in BI...aK
\er i f y P- Gl U T
ELSE
Clleck P- F3 U T
IF so then: *
Clleck P- G3 U T, i s NJf then:
PI ace bot h H gh St earn Fl ow SI
block sw t ches
in BI...aK
\eri fy P-G3 UT
ELSE
Cont i nue w t h next st ep.
NOTE: If steam dumps are available the
RO will need to transfer to Steam
Pressure mode (and go to BYP INTK if
P-F4 LIT). These steps are attached to
back of scenario.
CT5 Crew initiates RCS cooldown: Critical Task
- O"ew det erni nes requi red CEIC *0" ew nus t rmi nt ai n adequat e
tenperature based on ruptured subcooling to avoid transition
SG pressure. to 1-ECA3. 1
- ROIBOP dump.s steam'~
- 00 verifies c:ETCS < required
tenperature.
- RO.ocP stop durrpi ng steam
NOTE: Scenario may be terminated
after crew completes cooldown, or as
directed by the Lead Evaluator.
SID m::: 4 Page 24 Fevi si on 0
PlUHl.RE REv.
c:per at i ng Pr ocedur e 1- CP- 2. 1, "lhi t St art up from Mde 2 to Mde 87
1."
Pbnor rml Pr ocedur e 1- .AP-44, "Los s of .React or Cbol ant System 19
Pressure. "
Pbnor rml Pr ocedur e l-.AP- 4. 3, "Mlfunct i on of NIcl ear 18
Ins t r u~nt at i on (Pover Range)."
Pbnor rml Pr ocedur e l-.AP- 3, "Loss of \1 t al Instru~ntation. " 22
Pbnor nal Pr ocedur e l-.AP- 26, "Fai 1ur e of Mi n Gner at or \bl t age 9
.Regul at or H gh. "
Pbnor nal Pr ocedur e l-.AP- 24, "St earn Gner at or Tube Leak. " 20
Pbnor nal Pr ocedur e l-.AP-33.1, ".React or Cbol ant Punp Seal Fai 1ure. " 13
Emr gency Pr ocedur e l-E-O, ".React or Tr i p or Safet y I nj ect ion. " 36
Emr gency Pr ocedur e 1- E- 3, "St earn Gner at or Tube RIpt ur e. "23 23
St at i on Innunci at or .Response Procedures. NA
Glide and .Ref er ence Thcu~nt PI - M 5000, "HIrmn Perforrmnce. " 1
IN'Q Gli del i ne for TeaIrnOrk and Il agnost i c Skill Thvel op~nt : Jan. 1988
T .~~ ~~ ~
IN'Q P£::AD 07- 002 Si lUll at or Tr ai ni ng Gli del i nes Jan. 2007
SIDm: 4 Page 25 .Revision 0
iXITKH\INf 1 - SI MlAItR CPERtmR S CThPUIm PIU:RAM
iXITKH\INf 2 - SCFN\RI 0 PERF~ CBTH:TI \ffi
iXITKH\INf 3 - SI MlAItR PERF~ DXf~I-EEf (las t page of s cenar i 0) *
SID m.:: 4 Page 26 Revi si on 0
ATIIQMNf 1
SI MIA1t:R CPFRATCR S CThFUIFR PlURAM
SIDm: 4 Page 27 Revi si on 0
SIMULATOR OPERATOR'S COMPUTER PROGRAM
SXGNRC4
Initial conditions
1. Recall Ie 164
2. Ensure Tave, Tref (550- 560), PDIT 1evel, and \Cf 1eve1 are se1 ect ed on trend
recorders.
3. PI ace a VR Imgnet on 1- rn RI - 128.
4. Set rods on PCS to 140 st eps on D bank.
5. l-CP-2.1 filled out to correct step.
6. React i vi t y pI an avai 1abl e.
7. Rackout breaker for 2-CGP-IAand verify 2-CGP-IB running. Oose U2_CC_ll,
U2_CC_4.
PRELOADS PRIOR TO SCENARIO START
CINllICN Ml.RNTI eN 0vmRI IF! EIC
Let doW! r ad mmi tor Malfunction:
failure RM207, Sever i t Y = - 1
Failure of aut 0 t ur bi ne Malfunction:
trip TID3
SCENARIO EVENTS
E\fNf Ml.RNTI eN 0vmRI IF! <IMIN OOI eN)
1) lhi t ranp NOTE: The next event will occur once the crew has ramped
approximately 5 %.
2) PRZR Imster pressure Malfunction:
cont roll er f ai 1ur e 1Q9, 1:£1 ay t i Ire = 5, Ranp = 5, Severity = 2, Trigger
=2
NOTE: wee will inform the crew during this time that rods
may be returned to AUTO.
NOTE: The next event will occur after the crew has stabilized
RCS pressure and consulted Tech Specs, or at the direction of
the lead evaluator.
SID m::: 4 Page 28 Revision 0
3) "B" SG level Malfunction:
trans IIi t t er f ai 1ur e FW106, Thl ay t i Ire = 5, Ranp = 5, St op = - 1, Tr i gger =
3
NOTE: The next event will occur after the crew has reviewed
TS, or at the direction of the lead evaluator.
4) Pover-range channel NOTE: Verify control rods have been returned to AUTO
I V fai I ure before inserting this event.
Malfunction:
N 0204, Thl ay t i Ire = 5, Ranp = 0, Sever it y = 1,
Tri gger = 4
NOTE: If asked about method for restoring Taveffref, ask
for suggestion and agree with whatever is suggested.
NOTE: The next event will occur after the crew stabilizes unit
and places N-44 in trip, or as directed by the lead evaluator.
5) MJ \R Fai 1 ure Malfunction:
EL09, Thl ay t i Ire = 5, Ranp = 35, Sever it y = 50,
Tri gger = 5
NOTE: If called, can report that no abnormalities can be seen
at the VR panel.
NOTE: The next event will occur after the crew stabilizes the
plant, or as directed by the lead evaluator.
SID r<<: 4 Page 29 Revision 0
6) St earn gener at or tube Malfunctions:
leak requiring RC2402, ~lay ti~ = 5, Ranp = 300, Severity = 1.0,
shutdow"iX' ReP seal Tri gger = 6
leak
NOTE: Put in trigger 25 after crew has transitioned to ES-O.l
and throttled AFW.
Rel201, ~lay ti~ = 180, Ranp = 5, Severity = 100,
Tri gger = 25
NOTE: lIP surveys should take approximately 5 minutes.
Chemistry samples should take approximately 30 minutes.
NOTE: lIP will initially inform the crew that there is
increasing radiation in contact readings on the "B" MS line.
NOTE: The next event will occur after the crew throttles AFW
and has secured the "A" RCP, or at the direction of the lead
evaluator.
7) SGIR Update tube leak using trigger 7:
INF RC2402 (7 5) 50 60
Remote Function:
ML57, ~l ay t i ~ = 120, Ranp = 60, Val ue = 0, Tri gger
= 15
NOTE: Scenario may be terminated after the RCS cooldown
has been completed, or as directed by the Lead Evaluator.
SIDNC 4 Page 30 Revi si on °
SID m:: 4 Page 31 Revision 0
SI MlATCR RBJ.Wl PI CAll CN EXtW:N\TI CN
G ven equi ptrent f ai 1ur es and oper at i onal sit uat ions, oper at e t he pI ant in
accor dance Wt h Techni cal Speci f i cat ions to br i ng the uni t to a s af e
condition, using applicable procedures, and applying effective tea~rk,
connunication, and diagnostic skills.
<DmI C PFRFffiM>NE CBT H:TI \ffi
A Ihring shift operations the shift rrnnager wll take a conservative course
of act ion, es peci all y vhen uncer t ai n condi t ions exi s t, vhen deal i ng w t h
core cooling or heat sink availability, prirrnry system and containtrent
integrity, and reactivity control associated wth plant evolutions.
R Ihring shift operations the shift rrnnager wll provide overall crew
guidance by prioritizing and integrating the actions of the shift crewin
accor dance w t h adni ni st r at i ve pr ocedur es.
C Ihring shift operations each crew rrenber wll partIcIpate in a team
effort that resolves conflicts, provides input into the teamdecision and
connunicates all the necessary inforrrntion to enhance tea~rk in
accor dance w t h adni ni st r at i ve pr ocedur es.
D Ihri ng shi ft operat ions t he Shift Techni cal Mvi sor w 11 independent 1y
assess events and based on those assessrrents rrnke recorrnrndations to the
crew regarding nitigation strategy.
SIDr<<: 4 Page 32 Revision 0
EVENT 1 PERFORMANCE OBJECTIVES
EVENT GOAL: a ven that the uni tis at approxi rmt el y 22% pover and it is
desired to increase reactor pover, the crewwll ranp the
uni tin accordance w t h 1- CP- 2. 1, "lhi t St art up Mde 2 to
Mde 1."
NORTH ANNA SPECIFIC TASKS:
ro05 ill ut e the KS usi ng the bl ender.
CRITICAL TASK:
NA
SID m:: 4 Page 33 Revision 0
EVENT 2 PERFORMANCE OBJECTIVES
EVENT GOAL: G yen the uni tIS at pover and the PRZR pr es s ur e Il1lS t er
cont roll er fai 1s hi gh, t he crew w 11 respond in accordance
w t h 1- AP-44, "Loss of React or Cbol ant Syst em Pressure. "
NORTH ANNA SPECIFIC TASKS:
R534 Respond to a loss of react or cool ant syst em pressure.
S70 Eval uat e conpl i ance wt h t echni cal s peci f i cat ions.
CRITICAL TASK:
See next page
SJGNC 4 Page 34 Revi si on 0
cr St at enrnt :
Qew stops ~ pressure decrease.
Safety Significance:
Failure to close the PCRVand spray valves under the postulated plant
condi t ions cons tit ut es ni s - oper at i on or i ncor r ect cr ew per f or rmnce vhi ch
II
leads to degradation of any barrier to fission product release. II In this
case, the ~ fission-product barrier can be restored to full integrity
sirrply by closing the PCRVand spray valves. Therefore, failure to close
the PCRVand spray valves also represents a "dernmstrated inability by
the cr ew tot ake an act i on or conbi nat i on of act ions that wml d pr event a
chall enge t 0 pI ant s af et y. II
valid indication of pressure decreasing by the presence of various
annunciators, indication of PCRVand spray valves open, and ~ pressure
i ndi cat i on decreasi ng.
Perforrmnce Indicator:
RO rmnuall y cl os es PCRV and spr ays val ves .
Feedback:
~ pressure decrease stopped.
WD Reference:
E- 0 - Backgr ound Thcunrnt.
Gmdi t ions:
Pri or to recei vi ng an aut ormt i c react or t rip on low pressure.
SIDm: 4 Page 35 Revision 0
EVENT 3 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at pover and a stearn gener at or level
transrritter has failed, the crewwll be expected to respond
in accordance wth l-PI'-3, "LDss of Vital Instrurrentat i on. "
NORTH ANNA SPECIFIC TASKS:
R626 Respond to a stearngenerator vater level control channel failure.
S70 Eval uat e conpl i ance w t h t echni cal speci f i cat ions.
CRITICAL TASK:
NA
SIDm: 4 Page 36 Revision 0
EVENT 4 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that the unit is stable at pover and pover-range
channel ~44 has failed high resulting in rods stepping in,
t he crew W11 respond in accordance Wt h 1- PI'- 4.3,
"Ml funct i on of NIcl ear I nst runent at i on (Pover Range)."
NORTH ANNA SPECIFIC TASKS:
R713 Perform the imrediate operator actions in response to a rmlfunction of
pover - range nucl ear i ns t r unent at ion.
S70 EYaluate conpliance wth technical specifications.
CRITICAL TASK:
See next page
S)G~4 Page 37 Revision 0
cr St at errent :
Q-ew takes act i on to st op rod rrot i on and st abi 1i ze the uni t.
Safety Significance:
Cbre reactivity is not under control of the operator due to the failed
cont r 01 channel. "I tis expect ed that the oper at or W11 at t enpt tot ake
nanua1 actions to correct for anona10us conditions during pover
oper at ion. "
Indication of a failed pover range ~.
Cbnt i nuous i nWlr d cont r 01 r ad rrot i on wt h TA\E and 1RFF nat ched.
Perfornance Indicator:
RO pI aces r ad cont r 01 i n nanua1.
Feedback:
Rod rrotion stops.
WD Reference:
Nme.
Cbndi t ions:
Pr i or t 0 a rod 10- 10 i ns er t i on Ii ni t.
SID m::: 4 Page 38 Revision 0
EVENT 5 PERFORMANCE OBJECTIVES
EVENT GOAL: a ven that the uni tis at pOYer, and the mi n gener at or
vol t age r egul at or has f ai 1ed, the cr ew w. 11 be expect ed to
respond in accordance w.th l-AP-26, "Loss of Min Gnerator
\bl t age Gmt rol. "
NORTH ANNA SPECIFIC TASKS:
R675 Respond to a failure of min generator voltage regulator high.
CRITICAL TASK:
NA
SID m:: 4 Page 39 Revi si on 0
EVENT 6 PERFORMANCE OBJECTIVES
EVENT GOAL: G ven that the uni tis at pover and i ndi cat ions exi s t of a
SG tube 1eak and a #1 seal fai 1ure on an RCP, t he crew W11
be expect ed tor es pond in accor dance wt h 1- JiP- 5, "lhi t 1
Radi at i on ~ni t or i ng Sys t em" 1- JiP- 24, "St earn Qner at or Tube
Leak," 1- E- 0, "React or Tr i p or Safet y I nj ect ion," and 1- JiP-
33. 1, "RCP Seal Fai 1ure. "
NORTH ANNA SPECIFIC TASKS:
RI85 Perform the imrediate operator actions in response to a reactor trip or
s af et y i nj ect ion.
R533 Respond to a reactor coolant purrp seal failure.
S70 ~aluate corrpliance wth technical specifications.
CRITICAL TASK:
See next page
SID m:: 4 Page 40 Revision 0
cr St at errent :
G ew i sol at es af f ect ed React or Cbol ant Punp seal 1eakoff .
Saf et y Si gill f i cance:
"... an indication of a failure of the #1 seal in any RCP v.ith controlled
seal leakoff requires pronpt action to secure the leakoff path as soon as
is practical and in no case longer than five ninutes after seal leakoff
exceeds the high flowalarmsetpoint. Failure to isolate the affected
RCP seal leakoff in a tirrely rnmner rmy subject the RCP shaft, lover
radial bearing, and seals to high tenperature conditions ~ich could lead
to prermture failure of the rermining seals, failure of the lover radial
bear i ng, and var pi ng of t he RCP shaf t. ... "
Indication and annunciation of:
- PffectedRCP#1 seal IPless than200psid
ill
- valid indication of #1 seal leakoff greater than alarrnsetpoint.
Perforrmnce Indicator:
- G ew stops af f ect ed RCP (once react or i s t ripped) .
- Gewcloses affected RCP #1 seal leakoff valve (once loop flow
indicates affected RCP is stopped).
Feedback:
Indi cat i on of:
- decr eas i ng or zer 0 fl ow for loop v.i t h affect ed RCP
- affected RCP seal leakoff valve closed.
WD Ref er ence:
Wst i nghouse RCP vendor rmnual - addendum #3.
Cbndi t ions:
Wthin 5 ninutes of seal leakoff exceeding alarrnsetpoint.
SXJm= 4 Page 41 Revision 0
EVENT 7 PERFORMANCE OBJECTIVES
EVENT GOAL: Oven that the unit is shutdoWl followng a reactor trip,
and i ndi cat ions exi s t of a SGIR, the cr ew w II be expect ed
tor es pond i n accor dance w t h 1- E- 0, "React or Tr i p or Safet y
I nj ect ion," and 1- E- 3, "St earn ~ner at or Tube RIpt ur e.
NORTH ANNA SPECIFIC TASKS:
R18? Identify and isolate a ruptured stearngenerator.
R759 Cbol doWl the React or Cbol ant Syst em duri ng t he response to a st earn
generator tube rupture.
CRITICAL TASK:
See Follow ng Pages
SID m::: 4 Page 42 Revision °
cr St at errent :
Gewisolates flowto/fromruptured SG
Safety Significance:
Failure to isolate the ruptured SGcauses a loss of differential pressure
betv.een the ruptured SGand the intact SO;. lpon loss of differential
pressure, the crewnust transition to a contingency procedure that
constitutes an incorrect perforrmnce that "... necessitates the crew
taking corrpensating action ~ich corrplicates the event nitigation
strategy... "
Indication and annunciation of:
- Increasing SGvater level and radiation; and
- a reactor trip; and
- a s afet y i nj ect ion.
Perforrmnce Indicator:
RJ> adj ust s rupt ured SG PCRV set poi nt at 1050 PSI G
RJ> checks r upt ur ed SG PCRV cl os ed.
00 checks decay heat reI ease val ve cl osed.
RJ> checks "H' SG bl OwlOWl t rip val ves cl os ed.
RJ> cl os es r upt ur ed SG MnV and Bypas s val ve.
ID RJ> di rect s an auxi I i ary oper at or to I ocall y cl ose 1- M- 57, St earn t 0
the Terry Turbine from "B" SG
RJ> cl oses 1- FWMJl-100R
Feedback:
Indi cat i on of:
- stable or increasing pressure in the ruptured SG
- decreasing or zero feedvater flow rate to the ruptured SG
WD Reference:
E- 3 Backgr ound.
Cbndi t ions:
Isolate before a transition to HJ\3.1 occurs.
SID r<<: 4 Page 43 Revision 0
cr St at errent :
(} ew i ni t i at es K:S Cbol dOWl.
Safety Significance:
Failure to establish and rmintain the correct K:S tenperature during a
SGIR 1eads to a trans it i on from E- 3 to a cont i ngency pr ocedur e, Wli ch
constitutes an incorrect perforrmnce that "... necessitates the crew
taking conpensating action ~ich conplicates the event rritigation
strategy.... "
Pr ocedur all y di r ect ed by E- 3.
Perforrmnce Indicator:
m OCP dunps stearn
Feedback:
I ndi cat i on of stearn fl ow rat e gr eat er than zer o.
Indication of K:S tenperature decreasing
CR
I ndi cat i on of K:S t enper at ur e 1es s than tar get t enper at ur e.
"WG Reference:
E- 3 Backgr ound.
Cbndi t ions:
(}ew rmi nt ai ns adequat e subcool i ng.
SXJNC 4 Page 44 Revi si on 0
Scenario Performance Datasheet
E\ENf 1: G yen that the uni t is at approxi Imt el y 22% pov.er and it is desired
t 0 i ncr eas e react or pov.er, the cr ew VIi 11 r anp t he uni t in accor dance Vlith 1-
CP- 2. 1, "iliit St art up Mlde 2 to Mlde 1."
SPD \er i fi ed: (I ni t i al s)
- Reactor pov.er increases
- Turbine pov.er increases
- Tavg/ Tr ef i ncr eas e
- Gmer at or out put increases
E\ENf 2: G yen the uni t is at pov.er and the PRZR pr es sure ImS t er cont roll er
fai 1 s hi gh, the crew VIi 11 respond in accordance VIi t h 1- ftP-44, "lDss of
React or Cool ant Syst em Pressure. "
SPD \er i f i ed: (I ni t i al s)
- Innunci at or B- E6 ill uni nat es
- Mster pressure controller fails high
- 1- RC- PC\'- 1455C i ndi cat es open
- RCS pressure decreases
E\ENf 3: G yen that the uni t is at pov.er and a steam gener at or 1evel
trans ni t t er has f ai 1ed, the crew VIi 11 be expect ed tor es pond i n accor dance
VIi t h 1- ftP- 3, "lDss of Vi tal Inst rurrent at ion. "
SPD \er i fi ed: (I ni t i al s)
- Innunci at or s F- F2 and F- B2 ar e i 11 uni nat ed
- "B" Cllannel III SG 1evel i ndi cat or is reading off-scale low
- "B" MRV i s r anpi ng open
E\ENf 4: G yen that the uni t is stable at pov.er and pov.er-range channel N44
has f ai 1 ed hi gh res ul t i ng i n rods s t eppi ng in, t he crew VIi 11 respond in
accor dance vi t h 1- ftP-4. 3, "Ml f unct i on of Nlcl ear Ins t r urrent at i on (Pov.er
Range). "
SPD \eri fi ed: (I ni t i al s)
- N 44 i ndi cat es > 120%
- Cont rol rods step in at Imxi Inlrn speed
- RCS pressure and TAVE decrease
E\ENf 5: G yen that the uni t is at pov.er, and the md n gener at or vol t age
r egul at or has f ai 1ed, the cr ew vi 11 be expected to respond in accordance wth
1- ftP-26, "los s of Mi n Gner at or \bl t age Cont r 01 . "
SPD \eri fi ed: (I ni t i al s)
- Innunci at or s I(. B4 and I(. C7, and 1(.0 ill uni nat e
- Gner at or out put voltage increases
SID m:: 4 Thte _ Revi si on 0
E\ENf 6: G ven that the uni t is at pover and indications exist of a sa tube
I eak and a #1 seal failure on an RCP, the cr ew wll be expected to respond in
accor dance w t h 1- J>P- 5, "Ihit 1 Radi at i on Mmi t or i ng Sys t eIll " I-J>P- 24, "Steam
Gmer at or Tube Leak, " 1- &0, "React or Tri p or Safet y I nj ect ion," and 1- J>P-
33. 1, "RCP Seal Fai lure. "
SPD \er i f i ed: (I ni t i al s)
- I-M>-RI-191, "B" sa N 16, in PJ ert
- l'llIlUnci at or K 05 ill uni nat ed
- Innunci at or K 05 refl ashes
- Indications of increasing leakage on all N16 RM
- Ch~rging flowslowy increases
- Later: Innunci at or s G G1 and G (J) ill uni nat e
- "I\' RCP seal I eakoff fl ow i ndi cat i on is pegged hi gh
E\ENf 7: G ven that the uni t is shut doro follow ng a react or t rip, and
i ndi cat ions exi st of a SGIR, t he crew wll be expected to respond in
accor dance w t h 1- & 0, "React or Tr i p or Safet y I nj ect ion," and 1- & 3, "Steam
Gner at or Tube Rupt ure.
SPD \er if i es: (I ni t i al s)
- "B" sa level increases unexpectedly
- Pressuri zer level and pressure decreases unexpectedly
SIDNC4 Thte _ Revision °
PLACING THE BLENDER IN THE DILUTION MODE OF OPERATlON 1-GOP-8.3.1
,.' RelliSiol) .5
D9ntini9n COIVTINUOU,S USE Page 1 of 1
North Anna Power Station
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PLACING THE BLENDER IN THE ALTERNATE DILUTION MODE OF OPERATION 1-GOP-S.3.2
Ra\ll&lol\ 5
Dqlniniqa CON11,VUOUS USE Psge 1 (If 1
North Anna Power Station
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NUMBER PROCEDURE TITLE REVISION
23
1-E-3 STEAM GENERATOR TUBE RUPTURE
PAGE
12 of 44
ACTION! EXPECTED RESPONSE RESPONSE NOT OBTAINED
13. INITIATE RCS COOLDOWN: (Continued)
o b) Verify Condenser Steam Dumps - b) Manually or locally dump steam from
AVAILABLE intact SGs at maximum controllable rate
using:
1) Transfer Condenser Steam Dump to o * SG PORVs
Steam Pressure Mode:
o a. Put both Steam Dump Interlock
- Decay Heat Release Valve:
switches to OFFiRESET
o b. Put Steam Dump Controller to a. Locally open isolation valve(s) for
MANUAL NON-RUPTURED SG(s) to Decay
Heat Release Valve:
o c. Put Mode Selector switch to o * 1-MS-19, A Steam Line to
STEAM PRESS 1-MS-HCV-104 Non-Return
Valve
o d. Verify or reduce Steam Dump o * 1-MS-S8, B Steam Line to
demand to zero 1-MS-HCV-104 Non-Return
Valve
o e. Put both Interlock switches to o * 1-MS-96, C Steam Line to
ON 1-MS-HCV*104 Non-Return
Valve
o b. Locally open 1-MS-20, Decay Heat
Release Valve Upstream Isolation
Valve.
o c. Open 1-MS-HCV-104, Decay Heat
Release Valve.
(STEP 13 CONTINUED ON NEXT PAGE)
NUMBER PROCEDURE TITLE REVISION
23
1-E-3 STEAM GENERATOR TUBE RUPTURE
PAGE
13 of 44
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
13. INITIATE RCS COOLDOWN: (Continued)
IF no intact SG is available, THEN do the
following:
o * Use faulted SG
o * GO TO 1-ECA-3.1 , SGTR WITH LOSS
OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED,
STEP 1.
o 2) Verify Panel P-F4, STM DUMP o 2) Momentarily place both Steam Dump
COOLDOWN VLV AVAILABLE - LIT InUk Switches in BYP INTK, as
required during cooldown.
o Verify Panel P-F4 - LIT.
o 3) Raise Steam Dump Controller
demand and Dump steam to
Condenser from intact SGs at
maximum controllable rate
o c) Core exit TCs - LESS THAN REQUIRED o c) Continue RCS cooldown.
TEMPERATURE
o Do NOT proceed with Step 13d until core
exit TCs less than required temperature.
o d) Stop RCS cooldown
o e) Maintain core exit TCs - LESS THAN
REQUIRED TEMPERATURE