ML030430588
| ML030430588 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/05/2002 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Scalice J Tennessee Valley Authority |
| References | |
| 50-327/02-301, 50-328/02-301 50-327/02-301, 50-328/02-301 | |
| Download: ML030430588 (36) | |
Text
Draft Submittal (Pink Paper)
SEQUOYAH NUCLEAR PLANT EXAM 2002-301 50-327 & 50-328 DECEMBER 2 -6, 2002
- 1.
Written Exam Sample outlines ra AFr' C4-r'-j t -
I
FROM : SEQUCYPH OPERATOR TRAINING PHONE NO.
Seauoyah Date of Examination:
Exeimination Level (circle one): RQ)
Operating Test Number:
1 Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions AlI
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K Equipment Control
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FROM : SEQUOYAH OPERATOR TRAINING PHONE NO.
Seauoyah Date of Examination:
Examination Level (circle one):
RO Operating Test Number:
I Administrative Describe method of evaluation:
TopiclSubject
- 2. TWO Administrative Questions Atr US.,
A2 Equipment 7/Mr,_.,
p.74' /7tkaw
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o0 Control
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A3 Radiation Control 16 A4 Emergency
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FROM : SEQULYAH OPERPTOR TRAINING PHONE NO.
- 423 843 4339 Sep. 05 2002 02:04PM Pe ES-301 Control Room Systems and Facility Walk-Through Test Outliniorm ES-301-2 Facility:
Sequoyah Date of Examination:
Exam Level (circle one): RO Operating Test No.:
1 B.1 Control Room Systems System / JPM Title Type Code*
Safety Function 150, Flush Unit 1 Blender Piping D, S 1
136, Recovery from SI and Solid Water Conditions D, S, L 3
077-4 A22, Perform DIG Load Test on 1A-A DIG D, S, A' 013 AP%, Transfer to Hot Leg Recirculation D, 8, A, Lv 2
021, Respond to a Failure of PR N-41 D, S 7,-;'
065, Re-establishment of Containment Pressure Control
\\
D, 8 5v/
014 AP, Control Room Inaccessibility 1,I7AL 8
099 AP, Locally Align 1 B-B CCS Pump to Supply B Train D, P, ý,.A 8
085, Isolate RCP Seals, Thermal Barrier, and D, P, R, L (41
Containment following a Loss of All AC Power 201 R AP1, Local Isolation of Charging with Local Control
, Pý L,
2 of Seal Injection Flow L'
"*Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol room, ('S)imulator, (L)ow-Power, (R)CA
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FROM : SEQUOYPH OPERATOR TRAINING PHONE NO.
- 423 843 4339 Sep. 05 2002 02:03PM P6 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:
Seauovah Date of Examination:
Exam Level (circle one): SRO (U)
Operating Test No.:
1 8.1 Conlrol Room Systems System / JPM Title Type Code*
Safety Function 64AP, A ign ECCS Pumps and Containment Spray D, A, S 2
Pumps t_
77-5 AP, Perform DIG Load Test on 1 B-B DIG D, A, S 6
021, Re.spond to a Failure of PR N-41 D, S 7
098, Align cCS Pump 1B-B to Supply B Train Header D
8 209R, Removing Power from Various Components During an Appendix R Fire
- Type C odes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA 0
2%
FROM : SEQUOrYAH OPERATOR TRAINING PHONE NO.
- 423 e43 4339 Sep. 0S 2002 02:11PM P2 Appendix D Scen Facility:
v Scenario No.
Examiners:
Form ES-D-1 Operators:
Op-Test No.:
I Initial Conditions: Plant is at 58% Dower followinq a trip after a refueling outage.
Turnovnr: Increase power to 85%0 A Severe Thunderstorm Warnin in effect for Hamilton and Rhea counties for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. There is increased security du t$anvalidated threats Event Event No.
No Type*
Description 0,-A..r. ernI IIo+nr +fl IC-A I
I oet u
SEW U1C~JI
/
C N
(RO)
C (RO)
I (BOP)
C (BOP)
M (All "B" Containment Spray Pump O0 5
"WK MDAFW Pump COS - 4 A'
"B" MDAFW fails to auto start Phase "A" fails to actuate Start 2n' MFP increase power to 85%
PZR Level Channel falls High
- 3 Atmospheric Relief valve fails open after SGTL T-1-73 ails low M Air system rupture, can be isolated
- 3 S/G Tube Rupture Preinser:
Preinser; Preinser:
Preinsert 2
3 4
5 6
7
-io Outline Form ES-D-1 I
Start 2"d MFP Increase power to 85%
I a *rir* NIItllnA
FROM : SEUCYARH OPERATOR TRAINING PHONE NO.
- 423 e43 4339 Sep. 05 2002 02:02PM P3 Qron,,ndn fliiflins Appendix D Facility:
qeoyah.
Scenario No.:
2 Examiners:
Operators:
Op-Test No.: _
Initial Conditions: Plant is at 100% ower EOL roceeding to a refueling outase.
Tumovwr: Commence a4a-ftlant shutdown lAW M. A Severe Thunderstorm Wamin s in effec for Hamilton and Rhea counties for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. There is increased security due-tvaydated threats.
Malf.
M*
Event Tun**
Event Description Set up simulator to IC-12.
c "B" Containment Spray pump S
C "A" MDAFW Pump OOS-/
C C
N (RO)
(RO)
I (BOP)
C (BOP)
(All)
TDAFW pumt fails A.
-, 4;4I Containment Spray Fails to actuate Swap CCP's for maintenance preps Shutdown the plant IAWAOO*,p VCT Level Channel fails High PT3 Fails High *~
MVFRV Controller falls
- 1 & 2 $/G Break I/S Containment
- (N)ormal, (R)eactivity, (I)nstrument, (Cpomponent, (MIjnr, (P)RA, (L)owPower Event No.
pr'einserl Preinseri Preinser' Preinser 1
2 3
I 4
7 a
7 ri1 Qce-ario Outline Fo ES-D-1 T no*
Form ES-D-1 7
FROM : SEQUCYAH OPERATOR TRAINING PHONE NO.
- 423 843 4339 Sep. 05 2002 02:02PM P4 Appendix 0 Scenario Outline Form ES-D-1.
Facility:
Seauovah Examin ars:
Scenario No.:
3 Operators:
Op-Test No.:
1 Initial Conditions: Plant is at 94% power followina a trip after a refueling outase.
Turnover: Increase power to 100%. A Severe Thunderstorm Wamin..is in effect for Hamilton and Rhea counties for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. There is increased security due iwvalidated threats.
Event Malf.
Event Event No.
No.
Type*
Description Set up simulator to IC-9.
Preinsert C
"B" Containment Spray Pump OOS Preinsert C
,A-MDAFW Pump OOS Preinserl C
CCP fails on start Preinsed C
"A" EDG fails to start i
N Transfer Electrical Board 2
R Increase Power to 100%
(RO, 3
I PZR Level channel fails High (RO) 4 C
25 GPM leak on letdown line in Containment (RO) 5 1
s High (BOP) 6 C
Small Break LOCA (All)
- (tJ)ormal, (R)eactivity, (I)nstrument, (u)omponent, kvvuju,,
k
FROM : SEQUEYAH OPERATOR TRAINING PHONE NO.
- 423 843 4339 Sep. 05 2002 02:03PM PS A2ppndix D Scenario Outline Form ES-D-1 Facility:
Seauovah Scenario No.:
4 Examine~rs:______________
Initial Conditions:
Op-Test No.:
1 Operators:
Plant is at 94% power followino a trip after a refueling outage.
I i.k
i.
IL
Tumovir: Decrease power to 85% for a turbine valve test. A Severe Thunderstorm Warning is in nff=rt-frr Rsmilton and Rhea counties for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. I nere is increasec securiw uu-wr validate I threats.
Event Malf.
Event Event No.
No.
Type*
Description Set up simulator to IC-9.
Preinsert C
"B" Containment Spray Pump 00s Preinsert C
"N' MDAFW PumP O0S Preinseri C
"A" RHR Pump Fails Preinseil C
Phase "A" fails to actuate 1
N Place Excess Letdown in Service (Re) 2 R
Decrease power to 85%
3I Tavg Channel fails High (RO) 4 C
Charging Flow Controller Fails to zero 5
I t'Y'fLoop 1 Steam Pressure Channel fails high (BOP),,
6 C
Large Break LOCA Loop 1 (All)
_ _I (N)ormal, (R)eactivity, (I)nstrument, (C)ompoflerlt, (MJor, I9I1A, tLPW rower (Ilnstrument, (C)omponet
- ()ormal, (R)eactivity, 0
1 k '. t, 4 3 5/4 L it I IF-effect fc r Hamilton andRhea counties for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. There is increased securily que M*or, (P')RAJ~,
(L)OW Power
FROM : SEQUCYAH OPERATOR TRAINING ES-401 Faeilty:
Sequoyah Nuclear Plant PHONE NO.
- 423 843 4339 PWR SRO Examination Outline Sep. 05 2002 02:05PM PIO Printed: 09105/2002 Form ES-401-3 Exam Date: 12/02/2002 Exam Level; SRO K/A Category Points Tier Group Point Total KI K2 K3 K4 K5 K6 I Al A2 G3 A4 14 4
4 4
5 3
24
- 1.
2 3
3 3
3 3
1 16 Emnrgency 3
0 0
0 2
0 3
Abnormal Plant Tier Evolutions Totals 8,
7-7" 7
10 4
43/
,2 1
2 2
2 3
1 2
1 2
197.
2 2
I 1
2 1
2 1
2 1
2 17 Plant Sy:*terns4' 3
1 0
0 1
0 0
1 0
0 0
1 4
Tier Totals 4
3 2
5 4
6 2
4ý 2,
5, 40 CatI Cat 2 Cat3 at 4
- 3. Generic Knowledge And Abilities 4
44 5-4 IV Notm: 1. Ensure thatat least two topics from every K/.A category are sampled within each teir (i.e., the "Tier Totals" in each
- 2. 3/A0.
rt~o.s1 Wmiu8H o=%0oiffed in the table.
3, Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4, Systenms/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
- 6. The generic K/As in Tiffs 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category-K/As below 2-5 should be juslified on the
Facility:
Sequoyah Nuclear Plant 117
- A~lI PWR SRlO Examnination Outline Printed:
09/05/2002 Pntornp..noo ond! Ahnolrmai Plant E~volutions - Tier 1 / Group I fE/APE # IE/APE Name I Safety Function jKj I K2 K3 All A2 GC KA Topic Ip 001 Continuous Rod Withdrawal/I X
AKI.03 - Relationship otreactwvity and reactor power 4.0 1
to rod movement 003 Dropped Control Rod / I X 2.4.4 - Ability to recognize abnormal indications for 4.3 system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
015 Reactor Coolant Pump (RCP) Malfunctions /4 X
AK2.08 - CCWS 2.6 1
015 Reactor Coolant Pump (RCP) Malfunctions / 4 X
AA2.07 - Calculation of expected values of flow in the 2.9 1
loop with RCP secured A A 126 - Bnrie acid storage tank 3.3 1
Emergency BorationI /1 029 Anticipated Transient Without Scram (ATWS) / 1 040 1Steam Line Rupture /4 x
x A
bISIJJO - 5reaKerb, rviuyb, AA2.0l - Occurrence and location of a steam line rupture from pressure and flow indications I
A7 I
1
_________________________________I A-4 1 -
+
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r1 1
040 Steam Line Rupture / 4 05 1 LOTs of Condenser Vacuum / 4 i
il P
i j
i AK3.01 - Loss of steam dump capability upon loss of condenser vacuum I
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1 EK1*.06 - BreaKm=,d relays, m dal 13ulunnec A'7 l
£ A,
AK.,01 -Ctonsequences otxr S
£ J*ll
Facility:
Sequoyah Nuclear Plant PWVRSRO Examination Outline Printed:
09/05/2002
-5 M
Emergency and Abnormal Plant Evolutions - Tier 1 1 Group* 1 Form ES-401-3 EtA?!E BI
_E(APENamne I Safety Function
[
IPointsI 069 1 Loss ot Containment Integrity/ 5 A 2.1.14 - Knowledge ot system status criteria which 3.3 1
require the notification of plant personnel.
069 Loss of Containment Integrity / 5 X
AAM.03 - Fluid systems penetrating containment 3.0 1
074 Inadequate Core Cooling / 4 X
EKL.01 - Methods of calculating subocoling margin 4.7 1
074 Inadequate Core Cooling 14 X
EK2.02 - PORV 4.0 1
076 High Reactor Coolant Activity 19 X
AK3.0S - Corrective actions as a result of high 3.6 1
fission-product radioactivity level in the RCS E01 Rediagnosis / 3 X
EA21 - Facility conditions and selection of appropriate 4.0 1
procedures during abnormal and emergency operations EO1 Rediagnosis / 3 X
EA 1.1 -Components, and functions of control and 3.7 1
safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features E04 LOCA Outside Containment 1 3 X
BA2.1 - Facility conditions and selection of appropriate 4.3 1
procedures during abnormal and emergency operations E04 LOCA Outside Containment / 3 X
-K2.2
- Facility's heat removal systems, including 4.0 1
primary coolant, emergency coolant, the decay heat operation of these systems to the operation of the facility 4t-2 ES - 401
Facliy:Seqoyh uclarPlntPWR SRO Examination Outline Printed:
0910512002 Emergency and Abnormal Plant Evolutions -Tier 1 1 Group I Form ES-401-3 K/A Category Totals:
4 4
44 5
3 Group Point Total:
ES - 401 0 3K IE/APE# 0 IAPE Name I Safety Function I KILK2 IK3 lAl 42KIpeascae hc Imp.
Pit E08 Pressurized Titermal Shock / 4 X
EK3.2 - Normal, abnormal and emergency operating 4.0 1
procedures associated with Pressurized Thermal Shock E09 Natural Circulation Operations /4 X
EA2.1 - Facility conditions and selection of appropriate 3.8 1
procedures during abnormal and emergency operations E09 Natural Circulation Operations /4 X
EAI.1 - Components, and functions of control and 3.5 1
safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features ElO Natural Circulation with Steam Void in Vessel X
EK3.1 - Facility operating characteristics during 3.7 1
with/without RVLIS / 4 transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics E12 Uncontrolled Depressurization of all Steam X 2.4.16 - Knowledge of EOP implementation hierarchy 4.0 1
Generators / 4 and coordination with other support procedures.
614 High Containment Pressure / 5 X
EK1.3 - Annunciators and conditions indicating signals, 3.6 1
and remedial actions associated with the High Containment fressure 24 LB fD tA Wi Mi CD (S
-n U
-3 Facility:
Sequoyah Nuclear Plant
Facility:
Sequoyah Nuclear Plant ES -401 PWR SRO Examination Outline Printed:
09105t2002
_n M
Einer~enev and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-3 EIAPE # f EAPE Name f Safety Function (Ki1$YC 0 AlA2I G I KA Topic limp. pits 009 Small Break LOCA / 3 X
EK 1.01 - Natural circulation and cooling, including 4.7 I
reflux boiling 022 Loss of Reactor Coolant Makeup /2 X
AA2.01. - Whether charging line leak exists 3.8 1
02-5 Loss of Residual Heat Removal System (RHRS) / 4 X
AA2.06 - Existence of proper RIIE overpressure 3.4" 1
protection 025 Loss of Residual Heat Removal System (RHRS) 14 X
AK2.05 - Reactor building sump 2.6 1
027 Pressurizer Pressure Control (PZR PCS) Malfumction X
AA2.04 - Tech-Spec limits for RCS pressure 4.3 1
/3 027 Preurize Pressure Control (PZR PCS) Malftinction X
AKI.02-Expansion of liquids astemperatume increases 3.1 1
/3 037 Steam Generator (SIG) Tube Leak /3 X
AK3.03 - Comparison of makeup flow and letdown 3.3 1
flow for various modes of operation 037 Steam Generator (SIG) Tube Leak ! 3 X
AAI1 1 - PZR level indicator 3.3 1
038 Steam Generator Tube Rupture (SGTR) / 3 X
EK3,08 - Criteria for securing RCP 4.2 t
058 Loss ofDC Power] 6 X
AK3.01 - Use of do control power by ED/Gs 3.7 K
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Facility:
Sequoyah Nuclear Plant RS - dOl E(APE #
060 PWR SRO Examtination Outline Printed:
09/05t2002
-q El*merwenev an~d Abnormal Plant Evolutions - Tier 1 1 Group 2.
E I
I Group
[
E/APE Name I Safety Function Accidental Gaseous Radwaste Release / 9 KI ho2 x I K3 A1 AS G KA Topic AK2.02 - Auxiliary building ventilation system Form E*
Imp.
ji 3.1 S-401-3 061 Area Radiation Monitoring (ARM) System Alarms I X
AK2.01 - Detectors at each ARM system locatin 2.6*
1 7
E03 LOCA Cooldown and Depressurization /4 X
EK 1.3 - Annunciators and conditions indicating signals, 3.8 1
and remedial actions associated with the LOCA Cooldown and Depressurization E03 LOCA Cooldown and Depressurization / 4 X
EA 1.2 - Operating behavior characteristics of the 3.9 1
facility E05 Loss of Secondary Heat Sink / 4 X
EA1.3 - Desired operating results during abnormal and 4.2 1
emergency situations E 16 High Containment Radiation / 9 X 2.4.41 - Knowledge of the emergency action level 4.1 1
thresholds and classifications.
I V711 K/A Category Totals:
3 3
3 3
3 1
Group Point Total:
16 2
m m
0 C
X I
U o -0 0
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m Z P
-4 CA]
U mo
PWR SRO Examination Outline Printed:
09/05/2002 Facility:
Seqttoyah Nuclear Plant Uunprotuev and Abnormal Plant Evolutions - Tier 1 /Group 3 E/APE #
EI/APE Name I Safety Function 056 Loss of OffisitePower6 Et5 Containnent Flooding 5 EI5 Containment Flooding 15 E
4 en
- r P
Al A2 I I
I I J IK I
K G 1 KA Topic AA2,13 - Reactor coolant temperature, pressure, and PZR level recorders EA2. I - Facility conditions and selection of appropriate procedures during abnormal and emergency operations EKI.I - Components, capacity, and function emergency systems Group Point Total:
KIA Category Totals:
1 0
0 0
2 0
PC AOl Form ES-401-3 4 Amcl 45 3
19,,li I
I
PWR SRO Examination Outline Printed:
09/05/2002
_n Facility:
Sequoyah Nuclear Plant Plant Systems-Tier 21 Group I Form ES-401-3 (n
TK K5(2 lim-p. po jr,,nl..f n N rnne K
K 14 15 16 1Al A2 A3 1AL4 1G 'KATeOLc Points 5ys**IM iK IK3 I...
1
[
0 30 V S30 001 Control Rod Drive System I1 X
K3.01 - CVCS 3.0*
1 0
001 Control URd Drive System / I X
K5,30 -Effects of fuel burnout on reactivity in 3.1 1
m "0
003 iReactor Coolant Pump System X
AOA.03 - RCP motor stator winding temperatures 2.6 1b7 (RCPS) /4 7
004 Chemical and Volume Control System X 24.1 - Knowledge of EOP entry conditions and 4.6 1
(cVCS) / 1 immediate action steps.
004 Ce-mical and ýVolume Control System X
A3.07 - SIG level and presure 3.3 1
C3 Chm ica l a
nd Volu me C nrlS se (CVCS) 11 m
013 Engineered Safety Features Actuation 2.4.47 - Ability to diagnose and recognize 3.7 1
7 System (ESFAS) 12 trends in an accurate and timely manner utilizing the appropriate control room reference material.
N)j 013 Engineered Safely Features Actuation X
K4.01 - S1S reset 4.3 1
m System (ESrAS) / 2 I
017 In-Core Temperature Monitor (ITM)
X K6.01 - Sensors and detectors 3.0 1
System / 7 022 Containment Cooling System (CCS) /
X K2.01 - Containment cooling fans 3.1 1
5
-d 025 Ice Condenser System /5 X
+K5.02
- Heat transfer 2.8*
1 It)
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FROM : SEOUOYAH OPERATOR TRAINING ct 0 a 0 I 2
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PHONE NO.
- 423 843 4339 Sep. 05 2002 02:09PM P18
PWR SRO Examiuation Outline Printed:
0905l002 0
0 plants Sstems -Tier 21/Gru2 Form ES-401-3 r
rK 2
2A 1Inp IA% Inooif VX K6.19 -HPULPI systems (Mode*
change) 3 1
0 I0 Pressure, high and 1o 3.6 1
_u x-i X2.47 -Ability to iagvinose and real43.7 1
0
-D Z
Xr2..6s Ailit to aupraite and asselymeanner management role during plant transients and zm upset conditions.
0 XC K6..07 - Core prtcincacltr32*
1 ru X
to A3
-x lto s i ee e r adings*
P 2"---*
- and actual parameter value 1- -
- 4.
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M (fo3 X
~
~A1,02
- Water level In therfi ein MI anal 3._P.
m CD Q
A3 to N
i-0Ri "13 Ri "Oi No I
FROM : SEQUOYAH OPERATOR TRAINING PHONE NO.
- 423 843 4339 Sep. 05 2002 02:14PM P3 N
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Facility:
0 0
Sequoyah Nuclear Plant 01522 Plant Form ES-401-3 Plant Systems - Tier 21 Group 3 F
Iý
, IWI VqVAVI IC6 ~AtIA2IA3IA4iG KA To1tcC
_ytmigouitN~*...]-
X-l i2.1.10 - Knowledge of conditions and Ip
~it x 2.1 ork and3.9 1
-3 Pressurizer Relief TnIulch Tank I
-U Sytmssrz RieTaJQnhan' limitations in the facility license.
X Al anaiigpec tank water level 3.1 1mo Pressuirizer Relief TanW~enhIfc Ta DI0 SI0"I within limits System (PRTS) 15 0
Component Cooling Water System X
K4.02 - Operation of tie surge t including
.7 (CCWS) the associated valves and controls Instrment Air System (IAS)
X Group Point Total:
4 0
K/A Category Totals:
1 0
0 1
0 0
1 a
0 0
1 P
y-OD Co Q
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m CD
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Generic Knowledge and Abilities Outline (TirS3)
Printed: 09/0512002 PWR SRO Examination Outline Facility Sequoyah Nuclear Plant K(
KATopic Form ES-401-5 Imp.
Points Conduct of Operations 2.1.7 Ability to evaluate plant performance and make operational judgments based on 4A I
operating characteristics, reactor behavior, and instrument interpretation.
2.1.10 Knowledge of conditions and limitations in the facility license.
3.9 1
2.1.22 Ability to determine Mode of Operation.
3.3 1
2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.
3.1 1
Category Total:
4 Equipment Control 2.2.4 (multi-unit) Ability to explain the variations in control board layouts, systems, 3.0*
1 instrumentation and procedural actions between units at a facility.
21,9 Knowledge of the process for determining if the proposed change, test or experiment 3.3 1
increases the probability of occurrence or consequences of an accident during the change, test or experiment.
2.2.11 Knowledge of the process for controlling temporary changes.
3A, 1
2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and 3.7 1
safety limits.
Category Totab 4
Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.
3.0
-1 2.3.2 Knowledge of facility ALARA program.
2.9 1
23-3 Knowledge of SRO responsibilities for auxiliary systems that are outside the control 2.9 1
room (e.g., waste disposal and handling systems).
2.3.9 Knowledge of the process for performing a containment purge.
3.4 1
2.3.11 Ability to control radiation releases.
3.2 1
Category Total:
5 1
Generic Category 0 ":9
Generic Knowledge and Abilities Outline (Tier 3)
Printed: 0910512002 71 PWR SRO Examination Outline Form ES-401-5 M
n SSenuoy'ah ul a Plant C[
KAIMP.
roLinS STopic Generic Category KA Emergency Procedtres/Plan 2.4.4 Ability. to recognize abnormal indications for system operating parameters which are 4.3 1
0 entry-level conditions for emergency and abnormal operating procedures.
2 m
24.33 Knowledge of the process used track inoperable alarms.
2.8 1.D
[a imlmnain
- 3.
1 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementaion.
3.1 A >
2.4.5 Ability to prioritize and interpret the significance of each annunciator or alarm-3.6 1
47 Category Total:
4 G eneric Total:
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FROM : SEQUCIYAH OPERATOR TRAINING ES-01 PHONE NO.
- 423 843 4339 PWR RO Examination Outline Sep. 05 2002 02:15PM PG Printed; 09/05/2002 Form ES-40 1-4 rFsi3 itv:
Sequoyah Nuclear Plant Exam Date: 12/02/2002 Exam Level: RO K/A Category Points Ti er G~roup K!I-K2K314 K5 K(6 AlI A2 A3G Point Total a
1 4
3 4
3 2
0 16/
1, Err ergency 2
3 5
3 4
1 1
17 Alnormal Plant 3
1 1
1 0
0 0
3 E% olutions Totals 8
9 8
I336 Tier 1
2 2
1 3
2 2
3 2
2 2
23.1
- 2.
1 Pat 2
2 22 2 2
2 2
2 2
1 20 /
Plant ystms 3
0 1
2 0
0 2
1 0
Totals 5
4 4 4
74 4
4 7
5 5
3 51 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 3
3 3
4 13, NTote: 1. Ensure thatat least two topics from every K/A category are sampled within each teir (i.e., the "Tier Totals" in each
- 2. U ~,aWitAs¶ hpeat?&ftnPsoýZ'cVcifled in the table.
- 3. Select topics irom many systems; avoid selecting more than two or three K/A topics from a given system Unless
- 4.
me p are identified on the associated outline.
- 5. The shaded areas are not applicable to the category /tier,
- 6. The generic K/As in Tiues I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
7, On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals ftr each system and category. K/As below 2.5 should bejustified on the
PWR RO Examtination Outline Printed:
09/05/2002 AnJ 2*
Emergecne and Abnormal Plant Evolutions - Tier I t Grouo I EWAE 9 E/APE Name.' Natety inaction
~.lfiU2ji A I A) PCA 'fnkj 005 Inoperable/Stuck Control Rod /I1 X
AA2.01 - Stuck or inoperable rod from in-core and 3.3 1
ex-core NIS, in-core or loop temperature measurements 015 Reactorcoolant Pump tRCP) Malfunctions T4 AK2.08 - CCWS 2.6 1
024 Emergency Boratiom/l X
AAI.26 - Boric acid storage tank 3.3 1
027 Pressurizer Pressure Control (PZR PCS) Malfunction X
AKI.02 - Expansion of liquids as temperaamre increases 2-8 1
/3 040 Steam Line Rupture/ 4 X
AKI.01 - Consequences ofvrS 4.1 051 Loss of Condenser Vacuum / 4 X
AK3.01 - Loss of steam dump capability upon loss of 2.8*
1 condenser vacuum 067 Plant Fire on Site / 9 X
AA2.17 - Systemsthat may be affected by the fire 3.5 1
068 Control Room Evacuation I S X
AK2.07 - ED/G 3.3 1
069 Loss of Containment Integrity 15 X
AA1.03 - Fluid systems penetrating containment 2.8 1
1<
Facility:
Sequoyah Nuclear Plant SS-401 Form ES-401-4 I
Facility:
Sequoyah Nuclear Plant PWR RO Examination Outline Printed:
09/05/2MM ES - 401 0
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K/A Category Totass:
4 3
4 3
2 0
Group Point Total:
16 U)
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PWR RO Examination Outline Facility:
Sequoyah Nuclear Plant Emergency and Abnormal Plant Evolutions - Tier I / Group 2 Printed:
09/05(2002 Form ES-401-4 E/APE N E/APE Name s aaty Function
' KITn 001 Continuous Rod Withdrawal I1 X
AKI,03 - Relationship of reactivity and reacorpower 39 1
to rod movement 009 Small Break LOCA / 3 X
EK I.01
- Natural circulation and cooling, including 42 1
reflux boiling 025 Loss of Residual Heat Removal System (RHRS) / 4 X
AK2.05 - Reactor building sump 2.6 1
029 Anticipated Transient Without Scram (ATWS) I 1 X
EK2.06 - Breakers, relays, and disconnects 2,9" 2
037 Steam Generator (S/G) Tube Leak / 3 X
AK3.03 - Comparison of makeup flow and letdown 3.1 1
4 flow for various modes of operation 037 Steam Generator (S/G) Tube Leak / 3 X
AA I1 I - PZR level indicator 3.4 1
038 Steam Geaerator Tube Rupture (SGTR) /3 X
EK3.08 - Criteria for securing RCP 4.1 1
058 Loss of DC Power.6 X
AK3.01 - Use of do control power by ED/Gs 3.4*
1 059 Accidental Liquid Radwaste Release 19 X
AA2.05 - The occurrence of automatic safety actions as 3.6 1
a result of a high PRM system signal 060 Accidental Gaseous Radwaste Release / 9 X
AK2.02 - Auxiliary building ventilation system 2.7 ES - 401 Is) m 0
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Facility:
Sequoyah Nuclear Plant ES -401 PWR RO Examination Outline EII Name i Saieky Funiviou
!U_
___ __I_
__ __ __ __To_
_Imp. Po°ints 061 Area Radiation Monitoring (ARM) System Alarms/
X AK2.0 - Detectors at each ARM system location 2.5*
1 7
E01 Rediagnosis / 3 X
BALI - Components, and lnctions of control and 3-1 safely systems, including instr*mentation, signals, interlocks, failure modes, and automatic and manual features E01 Rediagnosis 13 X 2.2,25 - Knowledge of bases in technical specifications 2.5 1
for limiting conditions for operations and safety limits.
E03 LOCA Cootdown and Depressurization /4 X
EK 13 - Annunciators and conditions indicating signals, 3.5 and remedial actions associated with the LOCA I Cooldown and Depressurization E03 LOCA Cooldown and Depressurization /4 X
EA 1.2 - Operating behavior charteristic of the 3.7 1
facility E04 LOCA Outside Containment / 3 X
EK2.2 - Facility's heat removal systems, including I8 1
primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility E05 Loss of Secondary Heat Sink/ 4 X
EAU.3 - Desired operating results during abnormal and 3.8 1
emergency situations 0
K/A Category Totals:
3 5
3 4
1 I
Group Point Total:
17 2
Emergency and Abnormal Plant Evolutions-tier I IGroup 2 Form ES-401-4 Printted.
09IM52002 2:
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PWR RO Examination Outline Facility:
Sequoyah Nuclear Plant Printed:
091O52002 Form ES-401-4 Emergency and Abnormal Plant Evoludols - Tier I /1 I I IA, I ALIr IIA Tnnw-operation of these systemns to the operation of the 3La 1
PWR RO Examination Outline Prited: 09/05/2002 Facility:
Sequoyah Nuclear Plant Plant Syses-Ter2IGon1 Form ES-401-4 Sys/mv # system i ivoiuioun rnaPn 001 ControlRodDrive System/1 X
K3.01 - CVCS 29*
1 001 ControK5odDriveSystem/1 X
KS.30-Effects of fuel burnout onre ivityin 2.9 1
the core 003 Reactor Coolant Pump System X
K4.02 - Prevention of cold water accidents or 2.5 1
(RCPS) / 4 transients 003 Reactor Coolant Pump System X
A1.03 - RCP motor stator winding temperatures 2.6 1
(RCPS) /I4 004 Chemical and Volume Contr olSystem X
A3.07 - S/G level and pressure 33 1
(CVCS) /I 013 Engineered Safety Features Actuation X
K4.01 - SIS reset 3.9 1
System (ESFAS) 112 015 Nuclear Instrumentation System /7 X
A2.03 - Xenon oscillations 3.2 1
017 In-Core Temperature Monitor (ITM)
X K6.01 - Sensors and detectors 2.7 1
System 1/7 022 Containment Cooling System (CCS) J X
K2.01 - Containment cooling fans 3.9*
1 5
022 Containment Cooling System (CCS)/
X 2 A.27 - Knowledge of fire in the plant 3.0 1
5 procedure.
Fce Condenser System / $
[K5.02 - Heat transfer 2.6*
I ES - d.ll 0 at 025 X
I
Facility:
Sequoyab Nuclear Plant PWR HO Examtination Outline Printed:
09/05/2002 3d 0i a.
hystem i *Ivrnutiuuu Nrun Ice Condenser System 15 Kfl I/ u A IWA; Plant Systemisa
- tier 2O Group I W6 At A2 1A3 A4 IG IIA Topic X 12.2.13 - Knowledge of tagging and clearance Procedurs.
Form ES-401-4 3.6 points 056 Condensate System (4 X
KI.03 - MvW 2.6*
1 056 Condensate System (4 X
A2.04 - Loss of condensate pumps 2.6 1
059 Main Feedwater (MFW) System / 4 K
K1.04 - S/GS water level control system 3.4 1
/
059 Main Feedwater (MFW) System f4 --
X A4.01 - MFW turbine trip indication 3.1*
1 061 Auxiliary / Emergency Feedwater X
K2.01 - AFW system MOVs 3,2" 1
(AFW) System / 4 061 Auxiliary / Emergency Feedwater X
K6.01 - Controllers and positioners 2.5 1
(AFW) System / 4 068 Liquid Radwaste System (LRS)/9 X
-A3,02
-Automatic isolation 3.6 1
068 Liquid Radwaste System (LRS) / 9 X
K4.01 - Safety and environmental precautions 3.4 1
1 for handling hot, acidic, and radioactive liquids 071 Waste Gas Disposal System (WGDS)
X A1.06 - Ventilation system 2.5 1
/9 071 Waste Gas Disposal System (WGDS)
"X A4,26 - Authorized waste gas release, 3.1 1
1 /9 conducted in compliance with radioactive gas discharge permit 2
ES-401 I
I ISSysEv #I 025 I
Sep. 05 2002 02:19PM P14 FROM : SEQUCYAH OPERATOR TRAINING eq i
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Cd el eq t
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ut PHONE NO.
- 423 843 4339 CA
PWVR RO Examination Outline Printed: 09/05/2002 Facility:
Seqioyah Nuclear Plant 3r 1---I I
W7 Irc K4 5
II 1KA Topic I
point 006 Emergency Core Cooling System J
A 1.07 - Pressure, bigh and low 3.3 1
(ECCS) 1 2 S'006' Emergency Core Cooling System X
K6.19 - HPI/LPI systems (mode change) 3.7 1
(ECCS) /2 010 Pressurizer Pressure Control System -
X A2.02 - Spray valve failures 3.9 1
(PZR PCS) /3 012 Reactor Protection System f 7 X
K(6.07 - Core protection calculator 29 1
012 Reactor Protection System / 7 X
K2.01 - RPS chanmels, components, and 3.3 1
interconnections "016 Non-Nuclear Instrumentation System X
KI.01 - RCS 3.4*
1 (NNIS) /7 016 Non-Nuclear Insbtumentation System X
A3.02 - Relationship between meter readings 2.9*
1 O(MNS) 1 7 and actual parameter value 029 Containment Purge System (CPS)] 8 X
Al 02 - Radiation levels 3.4 1
035 Steam Generator System (S/GS) /44 --
X K5.01 - Effect of secondary parameters, 3.4 1
pressure, and temperature on reactivity 039 Main and Reheat Steam System X
+
4 K3.04 - MFW pumps 2.59 1
(MRSS) 1 4 039 Main and Reheat Steam System-
-5
- Bases for RCS coodovn limits 2.7 1
S(MRSS)/
4 Form ES-401-4 ES - 401 P lantO Syxams inatio Otlnen 2*
9o/02.
FROM :SEQUCYPH OPERATOR TRAINING PHONE NO.
- 423 843 4339 SeP. 05 2002 02: 20PM PIG 00
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PWR RO Examination Outline Printed:
09/05r2002 Facility:
Seqnoyah NuclearPlant Plant Sytm ir2Gop Form ES-401-4 O K/A Category Totals:
1 0
1 2
0 0
2 1
1 0
0 Group Point Total:
ES - 401 rY/v
- LY~
ata_
1l INS1(3K 4 KSK6 1
A A A314I KA Topic Imp.
Points 007 Pressurizer Relief TauklQuench Tank X
I Al.01 - Maintaining quench tank water level 2.9 1
System (PRTS) 15 within limits 00G Component Cooling Water System
'x K4.02 - Operation of the surge tank, including 2.9 1
(CCWS) / 8 the associated valves and controls 00$
Component Cooling Water System X
A2.04. PRMS alarm 3.3 1
(CCwS) / 8 034 Fuel Handling Equipment System X
K4.02 - Fuel movement 2.5 1
(FHES) /8 034 Fuel Handling Equipment System X
A 1.02 - Water level in the refueling canal 2.9 1
(FliES) / S 078 InstrumentAir System (/AS) / 8 X
K 1.01 - Sensorair 2.8*
1 078 Instrument Air System (AS) f S 19 K3.03 - Cross-tiecd units 3.0 1
103 Containment System / 5X A3.01 - Containment isolation 3.9 1
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Generic Knowledge and Abilities Outline (Tier 3)
Printed: 09/0512002 0
M PWR RO Examination Outline Form ES-491-5 Facility:
Sequoy Nucla Plant aImp.
roWto Generic CategoryKA KA
- 6.
pa
-ny, dra Codcto Oeatos2.1.16 Abilit to operate plant phone, paging system, and two-way radio.
2m91) 2a 2.124 Ability to obtain and interpret station electrical and-mechanical drawings.
2.8 1
0 2.1,31 Ability to locate control room switches, controls and indications and to determine that 4,2 1
tey rflecting he plant iep they are correctly reflecting the desired plant lineup.
M category Total:
3 7
"C)
Equipment Control 2.2.4 (molti-unit) Abilit to explain the variations. In corutrol" bo' lyussses 2.S instrumentation and procedural actions between units at a facility.
2w0 2.211 Knowledge of the process for controlling temporary changes.
2.5 1
2,2.26 Knowledge of refueling administrative requirements.
2.5 Category Total:
3 Radiation Control 2.3.9 IKnoledge of the process for perxforming a containment purge.
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 2.9 OD 23_0Aility to pefr rcdrlaa frdain n ur gis personnel exposure.
2.3.11 Ability to control radiation releases.
U)
Category Total:
3 Emergency Procedures/Plan 2.4.4 Ability to recognize abnormal indications for sys-tem operating parameters which are 4°0 1
]
entry-level conditions for emergency and abnormaal operating procedures.
2.4.5 Knowledge of the organization of the operating procedures network for normal, 2.9 1
I abnormal, and emergency evolutions.
3 2.4.20 Knowledge of operational implications of SOP xwanings, cautions, and notes.
3.3 2A4.39 KnowledgeoftheO'3.3 1,
Catego ryTotal:
4 oU Generic Total:
13 IM
"-U co