OPERATOR LICENSING EXAMINATION ADMINISTERED ON MAY 7,10-13,1999 AT

395 Pages·2005·16.65 MB·English

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NOTE TO: NRC DOCUMENT CONTROL DESK
MAIL STOP O-5-D-24
VI
FROM: r-k , ) c L*r LICENSING ASSISTANT
TIN LI;" BRANCH_ REGION I
SUBJECT: OPERATOR LICENSING EXAMINATION ADMINISTERED ON
SSS
DN O EA T
'SL--_y c(
DOCKET NWO5r cJ-&2 kv?
rl
OW '_ ` .- I-() - , OPERATOR LICENSING EXAMIINATIONS WERE ADMINISTERED
AT THE REFERENCED FACILITY. ATTACHED YOU WILL FIND THE FOLLOWING
INFORMATION FOR PROCESSING THROUGH NUDOCS AND DISTRIBUTION TO THE
NRC STAFF, INCLUDING THE URC PDR.
K
Item #1
at) FACILITY SUBMITTED OUTLINE AND INITIAL EXAM SUBMITTAL
DSIGNATED FOR DISTRIBUTION UNDER RIDS CODE A070.
b) AS GIVEN OPERATING EXAMINATION, DESIGNATED FOR DISTRIBUTION
UNDER RIDS CODE A070.
Item #2 EXAMINATION REPORT WITH THE AS GIVEN WRITTEN EXMIINATION
ATTACHED, DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE IE42.
AWTD
March 10, 1999
Dear Larry,
Enclosed find the outline for the May 1999 exam for Susquehanna S. E. S. I have also included
20 randomly selected questions from the written exam for your review.
We are in the process of validating the exam parts, so there may be some changes before the
final version is completed.
If you have any questions or comments, feel free to contact me.
Sincerely,
Russell B. DeVore
Facility Susquehanna Date of Exam: 05/10/99 Exam Level: SRO
Tier Group K/A Category Points Point
S. .. ... Total
KiK2K3 K4 K5 K6 Al A2 A A4 G
1 5 5 5 3 5 3 26:
& Abnom 2 .
-3
Plant Tier
S2 2
2. Plant 2 1 2 2r 1 1 1 2 1 1 1 13
Systems Ti3e rI 1 4
Totals 3 2 .4 4 4 4 4 5 3 4 3 40
5 3 4 5 17
ate: Attempt to distribute topics among all K/A Categories: select at least one
topic from every K/A category within each tier.
- ALal poert toit" must match those Weis in the table.
* Select topics fomn many systems: avoid selecting more than two or three KIA
topics from a given system unless they relate to plant-specific priorities.
* Systems/evoiutiors within eah group wer identified on the assocated
outline.
• The shaded areas are not applicable to the category/tier.
S-401BWR
RO Examination Outline
ES-401-1
9u5m0b0e3r # PNaarmtiael or Com-pete Loss of A.C. Power Em KPIr icK --2 a nKdA31 Cto --Aawl2 PGla nt Evolutions -Tier l/Group 1 T I
9955000036 PSCarRtiAalM o r Complete loss of A.C. Power -X1-X. 52 - -. AA1.003 SAShy.Csu.tt e emlesc tnrecmcaale rsglsoianar d s-to assure safe nt shutdown 43.. 5 11
95007 Hgh Reactor Pressure 3.1 1
X AA1.04 Safety/relief valve operation: Plant-Spec-i 4.1 1
95009 Low Reactor Water Level X 2e.m4.1e2e nKcn owopleedrgaeti oonfs g. eneral operating crew responsibilities during
95009 Low eactor Water Level - KI.05 Natural circulation 3.9 1
950110 -HIgh D eli Pirssure - 3.4 1
- - K.1 Downcomer submergence: ark-I 3.4 1
9955001130 HHiigghhS Durypwpreells sPiroens sPuoreo l Temperature _ X X AKK32.. 2 LDi mitinlgl/ shuepart easdsiitoionn csh amber differential pressure: Mark-I&ll 3.5 1
9955001143 HInlia dhv Seurtpepnrte sRseiOacnti vPiotyo lA Tdedmiti onr ature - - - .02 Systems that add heat to the suppression pool 33.98 1 1
95015 Incomplete SC-- -- - -X AAK22.0l2 FRueeal thermra l Imits 44.o2w er 1
95016 Control Room Abandonment X - A2.03 Reactor pressure
95016 Contvol Room Abandonment
29955001237 HRiegfh u Oellfnf- SAitec Rcelnleta$s e Rate X- -AKf - -e A WI RPreomte.cooto io-3ns h uotfd tohwe ng ene pPu bi a c "e-l:4 4. .r I1
95024 Reghelin Prcsse-
" AK2-.0F2u el pool cooling a"- cleanup systeM-
95024
X EA-_SupZpession chamber pressum: Plant-Specific 3.9 1
95025 High Reactor Pressure X rEeKlaItIi.0o3n shSIapfse ty/relief valve tallpipe temperature/pressure
3.8 1
95026 Su ssion Pool High Water Temperature X 2st.e4.p1s . Knowledge of EOP entry con ions and immediate action
95026 Suppression Pool High Water Temperature -- -- _EA2.01 Suppression pool water temperature 44..26 11
High Containment Temperature (Mark Ill
95027 Containment ON
295030 LOWS uppression PoolW ater Level X I JEA2.O1 ssionp ool level
95030 Low Suppression PoolW ater Level X EK3.03 RCIC operation: Plant-Specfc 4.2
95031 Reactor Low Water Level . EK3.04 Steam cooling 3.7 1
SCRAM Condition Present and Reactor 4.3 1
Power Above APRM Downscale or 2.1.- Ability to evaluate plant performance and make operational
95037 Unknown judgments based on operating characteristics, reactor behavior, and
X Instrument Interpretation.
4.4 1
SCRAM Condition Present and Reactor
Power Above APRM Downsc~le or F_
95037 Unknown
X EK3.03 Lowering reactor water level
4.5 1
953 O X - EK3.02 Systemi solations
00UU Iig containmenit = Mn o-ncentralo nIIII - - 4.2
FrJA Category Point Totals: L15~r
. 3li-$PitTtl
NUREG-1021
Printed on 3/10/99 at 12:51 PM Interim Rev. 8, January 1997
S-401 BWR SRO Examination Outline ES-40'-1
Emerendy dAb, rmal Plant Evolutions - Tier 1/Group
umber# Name m ItK2K31 Ai A2 G KiA Topic(s) I .
Partial or Complete Loss of Forced Core
95001 Flow Circulation X _AK1.02 Power/flow distribution 3.5 1
Partial or Complete Loss of Forced Core
95001 Flow Circulation X AA1.01 Recirculation system 3.6 1
95002 Loss of Main Condenser Vacuum X I -AK2.55 Feedwater system 2.? 1
95004 Partia or Complete Loss of D.C. Power " X AA1.02 Systems necessary to assure safe nt shutdown 4.1 1
2.4.41 Ability to interpret control moom Indicgtions to verify the status
and operation of system, and understand how operator action s and
95005 Main Turbine Generator Trip x directives affect plant and system conditions. 3.8 1
95008 High Reactor Water Level
High Containment Temperature (Mark Irt
95011 Containment ONly)
95012 High Drywell Temperature X A-K2.2 Dr cooling 3.7 1
Partial or Complete Loss of Component
95018 Cooling Water X AK2.02 Plant operations 3.6 1
AA2.02 Status of safety-related instrument ;r system loads (see
95019 Partial or Complete Loss of Instrument Air X AK2.1 - AK2.1. 3.7 1
95020 Inadvertent Containment Isolation X AK3.04 Reactr pressure rep(cid:127)onse 4A 1
95021 Loss of Shutdown Coolin gA1.04 Altem~e heat removal tods . .3.7 1
95022 Loss of CRD Pumps -X ARAeKaIc.0to1r pressure vs. rod Insertion c-a Nlty 3.4 1
95028 Hi D r-ell T unperan X - .. -EKt.01 Reactor water level measurement -3. 1
95029 High Suppression Pool Water Level- X EA2.03 D /containment water level 3.5 1
High Secondary Containment Area 2.2.3 (multi-unit) Knowledge Of the design, procedural, and
95032 Temperature
X operational differences between units. 3.3 1
High Secondary Containment Area
95033 Radiation Levelb X EA1.03 Secondary containment ventilation 3.8 1
Secondary Containment Ventilation High
--
95034 Radiation
Secondary Containment High Differenti
95035 Pressure
Secondary
Containmeft High Sump/Area
95036 Water Level X EA2.02 Water level in the affected area 3.1 1
EK3.04 Actions contained in lhe abnormal pftcedure for plant fire
00000 Plant Fire On Sie X on se 3.4
K/A Category F!intM Totals: 2 jGroupPoint Total:
NUREG-1021
Interim Rev. 8, January 1997
Printed on 3/10/99 at 12:51 PM
ES-401 1WR SRO Examinatlon Outline ES-401-1
u . Plat ystems - Tier 2/G-u I
umber# Name K213 K4 5 K6 A1 A2 A3 A4 G K/ATo c(s Imp. s.
Rod Control and Informnation System
21005 (RCIS)
Ai.'01 Recirculation
pump speed: BWR-2, 3, 4,
202002 Recirculation Flow Control System X 5,6 3.2 1
203000 RHR/LPCI: Injecion Mode (Plant specifIc) x I 2.03 Initiation hoic 2.9 1
206000 High Pressure Coolant Injection System X K5.05 Tuotbne speed control: BWR-2, 3, 4 3.3 1
20000 'l~h Pressure C.oolant. Injection System___X-- BKW6.0R9- 2,C 3o,n 4d ensate storage and transfer system: 3..5. 1
207000 Isolation (Emergency) Condenser --
209001 Low Pressure Cure Spray System X Condensate storage tank: Plant-Specific 3.1 1
-1(.01
209002 Htgh Pressure C.d.e Spray System (HpC$)
rK3.01 Ability to shutdown the reactor In certain
211000 Stendby Liquid Control SytGem X conditions 4.4 1
211000 Starf Liquid Control System X A2.01 PumP trip. 3.8 1
2.1.12 Ability to aply technical specifications
212000 Reactor Protection System X for a system. 4.0 1
12000 Reactor Protection System -- I I A2.19 Partial system act,'ation (half-SCRAM) 3.9 1
2.2.26 Knowledge of refueling administrative
15004 Source Range MOnitor (SRM) System X requirements. 3.7 1
Average Power Range Monitor/Local
215005 Power Range Monitor System x A1.07 APRM (gain adjustment factor) 3.4 1
16000 Nuclear Boiler Instrumentation x K3.24 Vessel level moniftidng 4.1 1
Reactor Core Isolation Cooling System
17000 (RCIC) X A4.01 RCIC turbine speed 3.7 1
Reactor Core Isolation Cooling System
17000 (OCIC) X A3.01 Valve operatIon 3.5 1
18000 Automatic DepreSsurizaqton System X K2.01 ADS logic 3.3 1
18000 Automatic Depressurization System X K5.01 ADS logic operation 3.T 1
Primary Containment System and
223001 APruixmilaiaryri eCs ontainment lsolation K4.05 Single falures wil not Impair the function
23002 SystemVNuclear #team Supply Shut-Off X ability of the system 3.1 1
RHRILPCI: Containment Spray System
001 Mode
39002 Relief/Safety Valves X-.-- - - K5.06 Vacuum _e-arakteior n 3.0 1
NUREG-11021
Interim Rev. 8, January 1997
Printed on 3/10/99 at 12:51 PM
S-401
BWR SRO Examination Outline
ES-401-1
Na e P la nt m s - T i er-Gro u- I_
ume#K
Reactor/Turbine ssum egulating K K 4R5 6 Al A T d3-' K/A Tic
41000 Sstem Ip P s
X K6.20 Main generator
3.0 1
59002 Reactor Water Level Control System A4.10 Setpoint down reset controls: Plant
X S"cific
c---2.9 1
1000 Sta Gas Treatment System x K1.06 Hgh Pressure cooant Injection system:
2001 A.C. Electrical Distribution Plant- precifsc 3.1 1
X A1.05 Breaker lPneu
3.5 1
90020A14 000E ene nG ent Automatic starting of compressor and
emergency gnerator
egry n==5 3.1 1
eno ar nin: '. oLo
___o~Pflt~j
NUREG-1021
Printed on 3/10/99 at 12:51 PM Interim Rev. 8, January 1997
BWR BRO Examination Outline
ES-401 -1
=1Plant tsro Rod -Tieru Srous 2
umberN ameKI K2K3jK_ K6jA1A2jT-24Gj
_ VATZ fts .
K4c.04 scramming control rods with Inopenratuive
11000012 CRoenatcrtoolr RMoadn Duarilv Ce oHnyUdtrraoulSlics eSmys tem X ix 1 1 vSaClvReAsM) solenoid valves (back-up SCRAM 3.6 '1
- -Ki .01 Control rdd rve hydraulic syse .
Rod Sequence Control System (Plant
1004 S2pci) sy-tem
Rod Worth Minimizer System (RWM)
01006 (Plant Specific) A2.05 Oul of sequence rod movement; P
X Spec(Not-DWR6)
3.5 1
02001 Recirculation System Ro.08 Recirculation flow mismatch: Plant
X Specific
04000 Reactor Water Cleanup System 3.4 1
X- A3.03 Response to system isolations 3.6 1
Shutdown Cooling System (RHR Shutdown
5000 COollingMode)
14000 Rod Position Information System------3.3 X K3.02 Reactor water level: Plant-Specific- 3.3 1
15002 Rod BRock Monitor System 1
X K6.06 LPRM detectors: I-R-Y,-4, 3 3T 1
15003 Intermediate Range Monitor (IRM) System X _AV4e.0ri7fi cation of proper functioning/
R IR/LPCI: Torus/Supp es on Pool "---- X operability 3.6 1
• ,
19000 Cooling Mode
R RILPCI: Torus/Sujppression Pool Spray
30000
Mode
34000 FuelH andling Eqiuipment
39003 MSIV leakage Control System - X K5.02 Fuel handln eq !nItn terlocks 3.7 1
Main Turbine Geterator and Auxiliary -________________
45000 Systems
X A1.07 First stage turbine pressure 2.8 1
59001 Reactor Feedwater System
2002 Uninterruptable Pow r S A.C./D.C.--"
713 000 000 D- O.Cg .aEs leS cytrs it ce am l D ls tr i b ut o - - - - - -ii --- -- - - --- --- -- - - - -- --- - 1f2o . 1r .a1 2sy sAt eboili.t y to apply teo hnical specifications 4 .0 1
72000 Radiation Monito-(cid:127) ino ystem I for syste-.--._-_
I K4.01 Redunda
86000 FIrPe rotection Stem - 2.8 1
9000 3 C o ntr H VA Ct - -K P4l.a0n3t protection 38 1
00000 Inistrumfent AirS tern
ASI_
Component Coonng Watersystem
00000 (CCWS ) n : T7 _ _ _ _ _ _ _ _ _ _
! up ta
_,',
)o -T 7 M
NUREG-1021
Printed on 3/10/99 at 12:51 PM Interim Rev. 8, January 1997
ES-401
BWR MRO Examination Outline
ES-401-1
,,, ___ __.__Plant 5?stnfs - Tier GrouD 3,.
umber# Name K1 K2 K3 K4 K5 KW All A A4 G " 1rATopic(s) Imp s.
01003 Control Rod and Drive Mechanism
X A4.02 CRD mechanism position: Plant-Specific 3.5 1
K4.01 Primary containment isolation: Mark
15001 Traversing In-Core Probe x I&II(Not-BWRI) 3.3 1
33000 Fuel Pool Cooling and Clean-up
9001 Main and Reheat Steam System X K6.02 Plnt 3.2 1
6000 Reactor Condensate Syste-(cid:127)
8000 Radweete
188000 Plant Ventilation Systtems
RFea0c0to2r Vessel Intemanls
A A2.05 Ex.eeding therm8 limits I2
IWA egory PolTOtals: J 1 roupPoint Iotal: 4
. ,/- = I - --
NUREG-1021
Interim Rev. 8, January 1997
Printed on 3/10/99 at 12:51 PM
ES-401 Generic Knowledge and Abilities Outline (Tier 3) ES-401-5
Exam
Facility Smquhum- Date: May 10, 1999 Level: SRO
Category KA # KA Topic Imp. Points
Conduct of Operations 2.1.9 Ability to direct personnel activities inside the control room. 4.0 1
2.1.12 Ability to apply technical specifications for a system. 4.0 1
2.1.12 Ability to apply technical specifications for a system. 4.0 1
Knowledge of system status criteria which require the notification of
2.1.14 plant personnel. 3.3 1
2.1.21 Ability to obtain and verify controlled procedure copy. 3.2 1
__ _ota
_ _____5
Equipment Control 2.2.13 Knowledge of tagging and clearance procedures. 3.8 1
.14 fthe pr for making . 3.0 1
2.2.23 Ability to track limiting conditions for operations. 3.8 1
Total 3
Knowledge of 10 CFR 20 and relae facility radiation control
Radiation Control 2.3.1 requirements. 3.0 1
2.3.2 Knowled of fJL"c ALAftA program. 29 1
Knowedgeof radiation exposure limilts and contam ination control,
2.3A isible levels in excess of thse authrized. 3.1 1
Ability to perform procedures to reduce excessive levels of radiation
2.3.10 and guard against personnel exposure. 3.3 1
4
Total
Emergency Procedures 2.4.25 Knowledge of fire protection procedures. 34 1
Ail to take action, called for in the facility energency plan,
and Plan 2.4.36 kncldin (if requhl;u tiny or acting as emergency coordinator. 4.0 1
Knowledge of the SRO's responsibalties in emergency plan
2.4.40 ,, ,,entation. 4.0 1
Knowledge of the emergency action level thresholds and
2.4.41 classifications. 4.1 1
Ability to perform without reference to procedures those actions tha
2.4.49 require immediate operation of system coprnents and controls. 4.0 1
Total 5
Tier 3 Target Point Total (RO/SRO) 17