ML022380305
| ML022380305 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/29/2002 |
| From: | Pisano L Constellation Nuclear |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 05000410/02-301 05000410/02-301 | |
| Download: ML022380305 (37) | |
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Final Document. Represents the "as administered" written exam on August 2, 2002.
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, SI)
Facility: NMPC U2 Date of Exam: 07129/02 Exam Level: RO Tier K/A Category Points Point Group Total K
K K
K K
K A
A A
A G
1 2
3 4
5 6
1 2
3 4I Emergency &
Abnormal Plant Evolutions 2
4 2
5 4
2 4
2 2
19 3
1 0
2 1
l 1
0 0
4 Tier 8
6
-8
-Z!04!2 3
3 Totals
- 2.
1 2
2 2
2 2
4 3
3 3
4 1
28 Plant Systems 2
2 1
2 2
2 1
2 2
2 2
1 19 3
0 0
0 2 1 0 0 1
0 0
0 4
Tier 4
3 4
6 5
5 5 6
5 6
2 51 Totals
- 3. Generic Knowledge and Abilities Cat I Cat 2 Cat 3 Cat 4 K l3 3
3 4
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4*n IdU Final Document. Represents the "as administered" written exam on August 2, 2002.
Note: 1.
Ensure that at least two topics from every KIA category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by M1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 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.
Systemsievolutions within each group are identified on the associated outline.
- 5.
The shaded areas are not applicable to the categoryltier.
6.*
The generic K/As in Tiers I and 2 shall be selected from Section 2 of the KJA 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 SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
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Final Document. Represents the "as administered" written exam on August 2, 2002.
ES-401l BWR RO Esnilnation OutlineForm ES-401-2 (R&, Si)l Emergency and Abnormal Plant Evolutions - Tier 1/Groun 1 EJAPE X IName I Safety Function K
K K
A A
GKATpcs
- m.
Pit 1
2 3
1 2
G A
oes)ip iw; 295005 Main Turbine Generator Trip 13 X
AK2.04 Knowledge of the interrelations between Main Turbine 3.3 1
Generator Trip and the following: Main generator protection (1) 295006 SCRAM /I X
AK2.06 Knowledge of the interrelations between SCRAM and the 4.2 1
following: Raor power (2) 295009 Low Feactor Water Level 12 X
AA1.01 Ability to operate and/or monitor the following aa they apply to 3.9 1
X Low Reactor Water Level: Reactor feedwater (3) 295014 Inadvertent Reactivity Addition I1 X
X AKI.05 Knowledge of the operational applications of the following 3.7 1
concepts as they apply to the Inadvertent Reactivity Addition: Fuel the=mal limits (43 AAI.07 Abilitý to operate and/or r the fotlowing as they apply to 4.0 1
Inadvertent eactivity Addition: Cold water injection (5) 295015 Incomplete SCRAM 1 1 X
AK2 10 Knowledge of the interrelations between Incomplete SCRAM 2.8 1
and the following: SPDSIERIS/CRIDS/GDS (6)
-95024 High Drywl Pressure/ 5X
.E.A1.19 Ability to operate andvormoitorthe followng asthey apply to 3.3 1
High Drywell Pressure: Containment atmosphere control (7_
295025 High Reactor Pressure 13 X
X EKZ.04 Knowledge of the interrelations between High Reactor Pressure 3.9 1
and the following: ARI/RPT/ATWS(8)
EA1.08 Ability to operate and/or monitor the following as they apply to High Reactor Pressure: RRCS (9) 3.3 I
295031 Reactor Low Water Level 12 X
EK1.03 Knowledge of the operational applications of the following 3.7 1
concepts as they apply to the Reactor Low Water Level: Water level efec on ractor power (10) 295037 SCRAM Condition Present and Power X
EK1.06 Knowledge of the operational a tplications of the following 4.0 1
Above APRM Downscale or Unknown I 1 concepts as Reiy applyto te SCRAM Condtion Present and Power Above APRM Downscale or Unknown: Cooldown effects on reactor power (11) 500000 High Containment Hydrogen Conc. 15 X
X EK3.05 Knowledge of the reasons for the following responses as they 2.9 1
apply to High Containment HydrTn Cone: Operation of wetwe (suppression pool) sprays (12 RO Only 2.1.32 Ability to explain and apply system limits and precautions (13) 3.4 1
K/A Category Totals:
3 4 ]1 4
0*,
o 1GroupPo3tTctal:
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Emergency and Abnormal Plant Evolutions -T"ioer l/Groun 2 tatAPE e
Name I Safety Function r
K 2op lete Loss PoAnts 295001 Partial or Complete Loss of Forced Core X
AA2.05 Ability to determine and e
ntegret the following as the(
17 ply -to Flow Circulation/ 11 & 4Partial or Co mpe Loss of Force Core Flow Circulation Jet pump 29602 ossof ainConensr Vcuu 13Operabilityl(14R0 IVl afoely to Loss of Man Condenser Vacuum Main steam isolation va~r 2.4.4 Ability to.recognize abnormal indications for system operating 4.0 1
pan ram~ente* icen* vel conditions for emergency ann abnormal 295003 Partial or Complete Loss of KC _Pwrl 6
X AKI---*
,=
w.03 Knowledge of the operational applications of tMe floig 2.9 1
oncerptos as theyapyt h Partial or uomplete Loss of AC Rw Une otg/egraded voltge effects on electrical, loads(7 295004 Partial or Complete Coss of
-DCPwr 16
-X AKI.02 Knowledge of the operational applications of the following 3.2 concepts as they apply to the Partial or Complete Loss of DC Pwr.
Redundant D.C. power supplies (18) 295005 Main Turbine Generator Trp X
AA1.05 Ability to operate ancdior monitor the following as they apply to 3.6 1
Main Turbine Generator Trip: Reactor/turbine pressure regulating system (19) 295008 High Reactor Water Level 12 X
HAAi
.06 Ability to operate and/or monitor the following as they apply to 2.8 1
X High Reactor Water Level: HPCS (20)
AAI.07 Ability to operate and/or monitor the following as they apply to High Reactor Water Level: Main turbine (21) RO Only 3.4 1
295013 High Su ppresslon Pool Temp. 15 X
AK2.O1 Knowled e of the interrelations between High Suppression 3.8 1
pool Temp. an e following: Suppression pool cooling (22) 295016 Contrl Room Abandonment 17 X
AEK,.02 Knowledge of the orerats ns f or the folp respongss as they 3.7 1
cnpts a the apply to thetHlg oSunpbn
- Turbine tipl W23 p
295017 High OffSsite Release Rate 1 9 X
AK3.02 Knbowil e of toheaeasons for the following ast*hey aspthey t
- 3.
1 apply to High r
site Release Rater Plant VentilaPon (9
- 24) 295019 Part. or Comp. Loss of eve In sX A.K3.02 Knowledge of the reasons for the following responses as they 3.6 1
EA23.02 Ablin ow de
&mne adntrprtAh followingrepns as they apyt apply t P
P-ara.te Lofs:
Standby air compressor operation (25)e s
2950 Inadverte Cnt.
Isolation 15 & 7 R
2123 Ability to perform specfic system and integrated plant procedur I
duung diferent modes of plant oper ation (2S) 295022 Loss oCRD Pumps /
-I EX AK1.01 KnoWiedge of the operational betweons of the following 3.8 concepts, as they apy toteL ss fCRaumps: Reactor pressure vs.
red. i lseond capela i ngy (27) 295026 High S,,ppression Pool Water Temp. 15 X3F FK1.01 Knowledge of the operational applications, of the follwn 3.0 1
concepts as they, apply to the High Suppression Pool Water Tamp:
Pump NPSH f2 1 295029 High Suppression Pool Water Lee 5X EAI.03uAbility to oprate andfor monitor the following as they apply to 2.9 1
KACtg*ory Pn T
Water Level: RHRoLPC n2n 295030 Low Supp-ion Pool WatLevr x1 x
EK3.03 Knowledge of the reasons for the followin responses as they 3.6 1
apply to Low Suppression Pool Water Level: RC]Coperation (30)
EA2.02 Ability to determine and interpret the following as they apply to
- 3.
1 Low Suppression Pool Water Level: Suppression pool temperatura
.e (31) 2903Hg e.Cont. Area Rad. Levels 1 9 X
EIK2.0,1 Knowledcie of the interrelations between HihSa.Cn Ae Rad. Levelsan an e following: Area radiation monitrnf ytm 3)Rl.
K/~aeor~
ln~oas:I4 2
5 4
2I2 Group Point Total:
I 9
Final Document. Represents the "as administered" written exam on August 2, 2002.
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Final Document. Represents the "as administered" written exam on August 2, 2002.
L) X ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, $1)
Emergency and Abnormal Plant Evolutions - Tier llGroup 3 EJAPE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
Imp.
Poits 1
2_
3 1
2 KATpes
- m.
Pit 295021 Loss of Shutdown Cooling X
AK3.01 Knowledre of the reasons for the following responses as they 3.3 1
tonLoss of Srutdown Cooling: Raising reactor water level (33) 295023 Refueling Acciden-ts 18 X
AK1.03 Knowledge of the operational applications of the following 3.7 1
conceputs as they apply to the Refueling Accidents: Inadvertent cr-iticality (34)RO Only 295035 Secondary Containment High X
EK3.02 Knowled e of the reasons for the following responses as they 3.3 1
Differential Pressure 15 aply to Secondary Containment High Differential Pressure aecondary containment ventilation response (35) 295036 Secondary Containmen*t High X
EA1.03 Ability to operate andfor monitor the following as they apply to 2.8 T
Sump/Area Water Level IS Secondary Containment High Sump/Area Water Level: Radwaste (36)
RO Only KIA Category Point Totals:
1 0
2 1
0 0
Group Point Total:
4
0 on i~u-so -E b-"C fif.
IES-401 BWR RO Examination Ootlin.yorm IlS-401.2 MR S11 Plant Systems - Tier 2/Group I System # I Name K
201001 CRD Hydraulic 201002 RMCS 202002 Recirculation Flow Control 203000 RH/LPCI: Injection Mode 209001 LPCS 2090 02 HPCS 215003 IRM 215004 SRM 215005 APRM I LPRM 217000 RClC x
K K
3 4
X X
x I
- 5 6 X
x 4
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K A
I A
A Final Document. Represents the "as administered" written exam on August 2, 2002.
aI Imp.
Points 3.5 1
K/A Topic(s) foA2 Abinly to (aoredict the impacts of the lowing on the CR
%Hydraulic and bd based on those p nredicions use proceeurs tocorrectcontrol or mitigate the onseueceso ofrse a 0ral conitions or operatio a: Low H accumulator ressure/hi h level 37 R Only A3.01 Ability to monitor automatic oeralions of the tMCS includin: Control rod boc actuation 39 Re Onl K3.
K nowied e othe eo tha a loss or malfunctionof te, eircuton low Control will have on the fol owing:
Recirculation Raow control valve position (40)
K4*.09 Khqwledge of Recirculation Flow Cntrol design eaturegs) and or interlock(s) which provide for the io lowing: Minimum and maximum flow control valve position se it~
K 3.03 Kn owiede of the effect that a loss or malfunc#ion of me RHR/LPCI: Injection Mode wll have on the following: Automatic depressurization logic (42) 2.1.32 Ability to explain and aooty system limits and utons 43) R nl Stto mn automatic or ations ofteLC ndudin: ystemaWflo44a K1.02 Knowledge of the physical connectlons and/or cause-eefect relatonships aetween lPCS and the following:
ýuppression pool (45)
A4.07 Ability to manually operate and/or monitor in ale control room: Une fill pump 48 KI.05 Knowledae of the physical connections and/or cause-effect relationshhia between SLC,;
and the following: RWCU 4 A4.15 Ability to manually operate and/or monitor in trle control room Recrculation pumi EC RPT (48) R Only K4.02 IKnowledo of XIRM design feature(s) and or nterlock sa which grvide r the following: Rea_ or SCRAM signals (49)
A4.04 Abilit to manually opegate and/or monitor in ite control room: SRM drive control switches (50) Re Only K6.07 Knowiedce of effect that a loss or malfuncton of a followino will have on AP PM I -PRMSystem:Fw Converter/3omp)ra'oFlo K2.04 Knowiedae of electIca power supplies to the flloowing: Gland seal conpressor (vacuum pump) (52)
A4.08 Ability to manually operate and/or monitor in the control room: RCIC system flow (51 )
3.2 3.7 3.3 4.2 3.4 3.7 3.5 2.8 3.4 3.9 4.0 3.2 3.2 2.6 3.7
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218000 ADS K5.01 Knowiedge Of the operational implications of tha following concerts as they apply to the ADS ADS logic operation (53)
A3.03 Ability to monitor automatic operations of theADS including: ADS valve acoustical monitor noise (54) 22301 Pimay CTiiTandAuxiiares 2.0 Knolede o eletilal owe K2.09 Knowied eofelectrical
,power Uasi*es)to the olowing: Drywall cooling 15.01 Knowvedge of the operationa t
inmplicatons of ae fel Ioiacnets as they ap pII te the F~i*Iary$%TMT and& ý.A.Juiliaes vacuum obaserraler operation (56) 223002 PCIS/Nuclear Steam Supply Shutoff X
-A1.02 Ability to predict and/or monitor 3.7 1
changes in parameters associated with rdtin the PCIS/Nulela.Steam Supply 290utoff ontrols including: Valvedosures 239002 SRVs X
A2.03 Ability to (.aeredict the impacts of the 4.1 1
following on the.e Vs and ( based on tnose pedicbgris, use procedures to con'ect, con
, or mitigate the consequences of 9brnorta crditions or operations:
- UKopen IR*V (58) 241000 Reactor/Turbine Pressure Regulator x
A1.13 Ability to predict and/or monitor 2.7 1
changes in parameters associated with o pe ng the ReactorrTurbine Pressure Kegulator controls including: Main turbine speed1 (15
- 9) 259001 Reactor Feedwater X
X AIl.01 Ability to predict and/or monitor 3.3 1
changes in parameters associated with operating the.Reaclor FeedwatoerA Syte (60)Isincluding: eedwaterflowprire K6.05 Kniowledge of the effect that a loss or 2.7 1
m~a1f~unction of ail foll0ring wll have on the Reactor Feedwater.
8~monent cooling water (61) 259002 Reactor Water Level Control X
X K6.03 Knowleder of the effect that a loss or 3.1 1
malfuncton of a folowin will have on the Reactor Water Level Con'rol: Main steam flow input (62)
A2.06 Ability to s) predict the impacts of the folowing on the esactor Water Level 3.3 1
Control and (b) based on those p IctJons, use procedures to correct contprl, or mitigate the consequences or those abnormal conditions or oaerations: Loss of Scontrollersignal olut )
264000 EDGsX K6.09 Knowiedge of the effect that a loss or 3.3 1
malfunctxon of am following will have on the EDGs: D.Cpowep r (64)
K/A Category Point Totals:
2 1 2 2
2 1 2 4
3 4
[I Group Point Total:
2e x
3.7 2.7 3.1 Final Document. Represents the "as administered" written exam on August 2, 2002.
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ES-.401 BWR RO Examination OutlineForm ES-401-2 (R8 Sil Plant Systems - Tier 2/Group 2 System # I Name 201003 Control Rod and Drive Mechanism 202001 Reclrculation 204000 RWCU 205000 Shutdown Cooling 214000 RPIS 215002 RBM 256000 Reactor Condensate 262001 AC EMetrical Distri~bution 262002 UPS (ACIDC) 1 -
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A X
A G
X KIA Topic(s)
Imp.
KS.03 Knowledge of the operational 3.3 implications of the following concepts as they apph to the Control Rod and Drive Mechanism: Reactor power control (65)
A3.01 Ability to monitor automatic operations he Control Rod and Drive Mechanism
3.7 including
Control rod position (66) ROOnly A1.10 Ability to predict andfor monitor changes in parameters associated with operating the Recirculation controls including: Recirculation seal purge flows (87)
RO Only A4.06 Ability to manually operate andlor monitor in the control room: System flow (68)
RO On[-,
K1.01 Knowledge of the physical connections and/or cause-effect relationships between Shutdown Cooling and the following: Reactor pressure 691 RO An!..
K4.01 Knowledi e of RPISdefy n featmrm(s) s n
3.0 1
and or interocks) which provied for the llowong: Reed switch locations (70) RO Only2.8 1
A4.03 Ability to manually operate and/or monitor in e o~rtrcl room: Control rod drive T-
~~temperature (71) 3 1
XX A2.01 Ability to(a) predict the impacts of the 2.8 tollowing on the Re C
and b
tho bad on t se proedio s, u sle prceduntro, orrgecthe contr ce of consequences aofa cithons or onditions:
"Witdrawal of cn.ro rod in hg oe region of core (72) 2.4.50 Ability to verity system alarm setpoint 3.3 1
and operate cons: ols idenrfied in the alarm response manual (73) RO Only A21 blit to (a) predict the impacts of the 28 1
followng on t ecor Condensate and (b) baed on 0hs peictions, use poeures to corccontrol, or mitigate the onsequencs oftose abnormal conditions or ope atons:
,igh demineralizer diffierential pressur (74) R~nly 2.6 Points I
I 3.0 1
3.6 1
K KJ3.O1 U
OMwed e of the effect that a loss or 3.5 malfunction of The AC Electrical Distribution will have on the following: Major system loads (75)
A3.01 Abiliy to monitor automatic operations 2.8 of the UPS {AC/DCI including: Transfer from preferred to al8emale source J76) RO Only Final Document. Represents the "as administered" written exam on August 2, 2002.
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263000 DC Electrical Distribution x
x K2.01 Knowledge of electhical power sUlies to the following: Major D.C. loads A1.01 Ability to predict and/or monitor changes in parameters associated with operating the DC Electrical Distribution nI ncluading:.
Batry 3.1 2.5 27l00ffgaa
- 6.
ntee of the effect that a loss or 3.4 1
malfuncton owill have on the Offgas: Fuel cladding integrity (79) RO Only 286000 Fire Protection x
K3.01 Knowledge of the effect that a loss or 3.2 1
malfunction of the Fire Protection will have on the following: The ability to detect fires (80) 290003 Control Room HVAC x
5.01 Knowledge of the operational 3.2 1
implications of the following concepts as they apply to Control Room HVAC: Airbome contamination (e g. radiological, toadc gas, smoke) control (81) RO Ony y 300000 Instrument Air K4.01 Knowledge of Instrument Air design 2.8 1
featuregsa and or intelock( wch provide for the folowing: Manuallautomatictransfers of control (82) RO Only 400000 Component Cooling Water X
K1.02 Knowledge of the physical 3.2 1
connections an Cor cause-effect relationships between Component Cooling Water and the following: Loads cooled by CCWS (83)
K)A category Poin: Totals:
I I2 I
!2 2
2 1
Group Point Total:
]
19 Final Document. Represents the "as administered" written exam on August 2, 2002.
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System 0 /Name K
K K
K K
K A
A A
A G
KIA Topic(s)
Imp.
Points 1
2 3
4 5
B 1
2 3
4 233D00 Fuel Pool Cooling and Cleanup X
K4.06 Knowledge of Fuel Pool Cooling and 2.9 1
Cleanup design featurefs) and or interocl(s) which provide for the following: Maintenance of adequate pool level (84) R, Only 234000 Fuel Handling Equipment X
K5.05 Knowledge of the operational 3.0 1
implications of the following concepts as they apply to the Fuel Handling Equipment:
--uel orientation (85) 288000 Plant Ventilation X
K4.03 Knowledge of Plant Ventilation 2.8 1
Systems design feature(s) and/or interlocks which proide for the following: Automatic starting and stopping of fans (86)
X A2.02 Ability to (a) predict the impacts of the 3.6 1
following on the Reactor Vessel Internals and (b) based on those predictions use proceaures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Overpressurization transient KIACategory Point Totals:
o 0 Jo 2t1
[0 Io i 0 Io 0
G(7p Poi4Total:
Plant-Specific Priorities System I Topic Recommended Replacement Reason Points for...
Tier 2 Group 2 290003 K5.01 Tier 2 Group 2 290003 K6.04 An appropriate question can not be developed.
1 HVAC Fire system is manual valves.
Tier 3 Common Generic 2.2.11 Tier 3 Common Generic 2.2.34 Anapproprate question can not be developed.
I Genenc Fundamentals level of knowledge.
Tier 2 Group 1 259001 A1.01 Tier 2 Group 1 259001 K5.02 An appropriate question cannot be developed.
I Generic F-undamentas level of knowledge.
"Tier 2 Group 1 217000 A4.08 Tier 2 Group 1 215005 K4.08 An appropriate question can not be developed.
1 Replace Fwith RCIC operation question because of higher operational significance.
Plant-Specific Priority Total: (limit 10) 4 Final Document. Represents the "as administered" written exam on August 2, 2002.
ES 401 BWR RO Examination OutlineForm ES-401-2 (R8, SI)
Plant Systems - Tier 2Iimuo :3 D.,.
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I I Final Document. Represents the "as administered" written exam on August 2, 2002.
14~2 ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5 (R8, Sl)
Facility:
NMPC U2 Date of Exam:
07/29/02 Exam Level: RO Category KIA #
Topic Imp.
Points Conduct of 2.1.10 Knowledge of conditions and limitations in the facility 2.7 1
Operations license (88) RO Only 2.1.14 Knowledge of system status criteria which require the 2.5 1
notification of plant personnel (89) 2.1.31 Ability to locate control room switches, controls and 4.2 1
indications and to dete rmine that they are correctly reflecting the desired plant lineup (90)
Total 3
Equipment 2.2.12 Knowledge of surveillance procedures (91) 3.0 1
Control 2.2.28 Knowledge of new and spent fuel movement procedures (92) 2.6 1
RO Only 2.2.11 Knowledge of the process for controlling temporary 2.5 1
1changes (93)
E Total 3
Radiation 2.3.2 Knowledge of facility ALARA program (94) RO Only 2.5 1
Control 2.3.9 Knowledge of the process for performing a containment 2.5 1
purge (95)L 2.3.11 Ability to control radiation releases (96) 2.7 1
Total 3
Emergency 2.4.18 Knowledge of the specific bases for EOPs (97) 2.7 1
Procedures/
Plan 2.4.27 Knowledge of fire in plant procedure (98) 3.0 1
2.4.32 Knowledge of operator response to loss of all annunciators 3.3 1
(99) 2.4.35 Knowledge of local auxiliary operator tasks during 3.3 1
emergency operations including system geography and system implications (100)
Total 4
Tier 3 Point Total (RO) 13 In 1 A E*t
John Caruso - ES401-'10 final as administered..o.
Page ES401 Record of Rejected K/As Form ES-401-10 (R8, SI)
Tier I Randomly Selected Reason for Rejection Group K/A Vanous One out of KlAs in KAs not applicable to Nine Mile Point unit Z design per E:-401
.l.o Attached NUREG 1123 TIER 1 and GENERIG KAs Non-system GEKNENRIC NA statements suppressed per NRC Suppresswon Guidance Letter, 'Clanhcaton ot Guidance Regarding the TIER 2 Elimination of Inappropriate Knowledge and Abilities (K/A) on Written Operator Licensing Examinations' and ES-01 D.1.b Vanous
<2.5 Importane Rating wi inp nce rating less than 2.5 will no see dunng random generation per FtS-4u1 U.1.0 TIROU 214000721-02 Randomly reselected K4.01, to avoid double ijopardy With A4.03. K4.02 is similar to A4.03.
?./GROUP 2 RO ONLY TIEKR 215002 2.4.49 Randomly reselected a..
, 2.4.49 is not applicable, due to no Immediate perator Actons RoRX atNMPC-U2 2/GROUP 2 ROONLY 2TIR 233000 K2.02 Randomly reselected K4.06, K2.02 is not applieble, Spent Fuel Pool COOiing System contains its' own system pumps.
2/GROUP 3 RO ONLY TIER 211000K1.0 Randomly reselected K1.05, K1.07 is not applicable to Nine Mile Point Unit 2 design. SLS system injects through the HPCS sparger 2/GROUP 1 inside the downconer.
SRO/RO TiER 239002 A2.04 Randomly reselected A2.03, dud-to over-sampling WADS logic when compared with sampingin an 2/GROUP 1 SRO/RO The following are Changes made tow enexamo mes rintia outlnes mi.
eseaso enfi on orm 401-and 401-2 Written Outlines.
TIER 290003 K6.04 290003 K5.01 An appropriate question can not be developed. HVAC Fire system is manual valves.
2/GROUP 2 RO ONLY TIER 3 Common Generic Genedc 2.2.11 An appropriate question can not be developed. Generic Fundamentals level of knowledge.
RO/SRO 2.2.34 TIER 259001 K5.02 259001 A1.01 An appropriate question can not be developed. Genenc Fundamentals level of knowledge.
2/GROUP 1 (RO)
TiER 2/GROUP 2 (SRO)
RO TIER 1/
500000 EA1.05 500000 EK3.05RO selected, unable to write question to onginal K/A for RO position Group 1 Final Document. Represents the "as administered" written exam on August 2, 2002.
-7 o! A74A. stI I
f* JUi~I II I
Mu~v -
r0-,,,-
i*aus I11 aouminlstereo.ooc SRO/RO 500000 2.1.28 500000 2.1.32 selected, unable to write question to original K/A TIER 1/
Group 1 SRO/RO 295022 AK2.02 295002 2.4.4, selected SRO original K/A overlap with RO outline when selected as a common TIER 1/
Group 2 SRO/RO 295029 EK1.01 295005 AAi.05 SRO made into common reselected to K/A applicable to both RO and SRO TIER 11 Group 2 RO TIER 1/
295036 EK2.02 RO 295021 AK3.01 ROoriginal K/A not applicable at NMPC 2 reselected to new K/A Group 3 SRO/RO 215002 A2.04 215002 A2.01 better match to question TIER 2/
Group 2 RO TIER 1/
295030 EA2.01 295030 EA2.02better match to question Group 2 SRO TIER I/ Group 2 SRO/RO 264000 K6.05 264000 K6.09better match to question TIER 2/
Group 1 RO TIER 2/
204000 A4.05 RO 204000 A4.06 RO better match to question Group 2 SRO/RO 288000 K3.05 288000 K4.03 better match to question TIER 2/
Group 3 SRO TIER 295013 AK3.02 SRO 295013 2.1.12 SRObetter match to question 1/ Group 1 SRO TIER 295012 2.4.49 SRO 295012 AK2.02 SROunable to write appropriate LOD 1/Group 2 500000 EA1.05 Now on SRO only 295029 EA1.03 RO Now common 295020 2.1.23 R5 Now common The following chanoes were made after exam submittal. Changes resulted from NRC review of the initial written submittal and facility rework to address the NRC comments.
SRO Tier 3 21.13 Deselected 2.1.13 due to potential security procedure concern. Randomly selected 2.1.27. This was a system purpose KA and inappropriate for SRO only ouestion. Deselected 2.1.27 and randomly se ected 2.1.9. Developed SRO only question which was rejected by Chief Examiner. Deselected 2.1.9 and randomly selected 2.4.30. Developed new question for 2.4.30for ROonly Question 86.
RO TIER 201002 K3.01 215005 K6.07 randomly selected. Unable to write acceptable question for original KA. Change to 215005 16.07 resulted in SRO 2/GROUP 1 Tier2 Group 1 total points equals 24 instead of23 and SRO Tier 2 Group 2 equal 12 points instead of 13 This is allowed by Form EE SRO TIER 401-1. Rev a Supp t. Note 2. (Allowance to be + or - 1, due to required changes).
21GROUP 2 RO TIER 295017 AK3.04 295017 AK3.02 randomly selected. Unable to wrte acceptable question after multiple attempts for original KA 1/GROUP 2 SRO TIER 1 GROUP 1 Final Document. Represents the "as administered" written exam on August 2, 2002.
S................. IJ;=T* qlI týr---
Jo°lin Caruso - ES-40 *- 0dO fia as administered.doc Pag3 Final Document. Represents the "as administered" written exam on August 2, 2002.
FI f-, W-S.N il Ii; UI.'aý F-orm ES-401-1 CR8. S11 avvr% SROr -xaminazion uUtline Facility:
NMPC U2 Date of Exam:
07/29/02 Exam Level:
SRO KIA Category Points K
1 2
K 3
- 1.
1 5
4 3
Emergency &
Abnormal Plant Evolutions 2
3 2
3 Tier 8
6 6
Totals I
2 2
K K
K A
4 5
6 1
. I-5 3 1 3
2 A
A AIG 2
3 4
4-7 5
3 7
2 Point Total 26 17 43 24 2
1 1
1 1
11 2
1 0 11 2
12 3
0 0
0 1
1 0
1 T0 1
4 I ier Totals 4
3 5
3 4
4 2
3 6
40 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge and Abilities 17 3_4 4
6 Final Document. Represents the "as administered" written exam on August 2, 2002.
Tier I
IT Group
- 2.
Plant Systems 0 QM
=Q-Afl4 lI o%-l~.
IB U
I-orm !*5-401-1 (RS. Sl 3
3
John Caruso -
4S-0-1-1-SOfi~
as' adm~iniste-red8-d3 Final Document. Represents the "as administered" written exam on August 2, 2002.
..
..
Pý_F Note: 1.
Ensure that at least two topics from every KIA category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 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.
Systems/evolutions within each group are identified on the associated outline.
- 5.
The shaded areas are not applicable to the categoryltier.
6.*
The generic K/As in Tiers 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 SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
v, u-j i
J ill It:If d dU~ll llI.I[Lr
.]U.U0C ES-401 BWR SRO Esamination OutlineForm ES-401-1 (R8, St)
Emergency and Abnormal Plant Evolutions -Tier 1/Group I EIAPE # 1 Name I Safety Function K
K K
A A
G KIA Topic(s)
Imp.
Points 1
2 3
1 2
295003 Partial or Complete Loss of AC Pwr 16 X
AK1.03 Knowledge of the operational applications of the following 3.2 1
concepts as they apply to the Partial or 'onplete Loss of AC Pwr Under voltage/degraded voltage effects on electrical loads (1) 295006 SCRAM /1 XX AK2.0 Knowledge of the interrelations between SCRAM and the 4.3 1
following: Reactor power (2)
AA2.04 Ability to determine and interpret the following as they apply to SCRAM: Reactor pressure (3) SRO Only 4.1 1
295007 High Reactor Pressure /3 X
AA2.03 Ability to determine and interet the following as they apply to 3.7 1
High Reactor Pressure: Reactor water level (4) SROny p
To 1
295009 Low Reactor Water Level 12 X
AA1.O1 Abilityato operate and/or monitor the following as they apply to 3.9 1
_LOW Reactor Water Level Reator feedwater (5) 295013 High Suppression Pool Temp./ 5 X
AK2.01 Knowledge of the interrelations between High Supression 3.7 1
Pool Temp. and the following: Suppression pool cooling (6) 2.1.12 Knowledge of surveillance procedures (7) SRO Only 3
295014 Inadvertent Reactivity Addition/ 1 X
X AK1.05 Knowledge of the operational applications of the following 4.2 1
concepts as they apply to the Inadvertent Reactivi Addition: Fuel thermal limits (8)
AA1.07 Ability to operate and/or monitor the llowng as they apply to 4.1 1
295015_____Incomp ____ete ___SCRAM _______1_
Inadvertent Reactivity Addition Cold waler injection (10) 295015 Incomplete SCAM/-I X
AK2.10 Knowledge of the interrelations between Incomplete SCRAM 3.0 1
and the following: SPDS/ERIS(CRIDStGDS (11) 295016 Control Room Abandonment /7 X
AK3.02 Knowledge of the reasons for the following responses as they 3.8 1
apply to Control Room Abandonment: Turbine trp (12) 295017 High Off-site Release Rate 19 X
AK3.02 Knowledge of the reasons for the following responses as they 3.5 1
apply to High Off-site Release Rate Plant Ventilaton Systems (13) 295023 Refueling Accidents / 8 X
X AA2.05 Ability to determine and interpret the following as they apply to 4.6 1
Refueling Accidents: Entry conditions of emergency plar(14) SRO Only 2.4.30 Knowledge of which events related to system operations/status 3.6 1
should be reported to outside agencies (15) SRO Only 295024 High Drywell Pressure 15X EAI.19 Ability to operate and/or monitor the fol lowing as theyapply to 3.4 1
High Drywell Pressure: Containment atmosphere control (16) 295025 High Reactor Pressure / 3 X
EK2.04 Knowledge of the interrelations between High Reactor Pressure 4.1 1
and the following: ARI/RPT/ATWS (17)
EA1.08 Ability to operate and/or monitor the following as they apply to High Reactor Pressure: RRCS (18) 3.7 1
295026 Suppression Pool High Water Temp. 15 X
X EK1.01 Knowledge of the operational applications of the following 3.4 1
concepts as they apply to the High Suppression Pool Water Temp Pump NPSH (1 )
2.2.22 Knowledge of limiting conditions for operations and safety limits 4.1 1
(20) SRO Only X
I x
I Fld,,
of the-reasns th 295030 Low Suppression Pool Water Level / 5 apply to Low Suppression Pool Water Level: R0C operation (21)
EA2.02 Ability to determine and interpret the following as they apply to Low Suppression Pool Water Level. Suppression pool temperature (22) 3.9 1
Final Document. Represents the "as administered" written exam on August 2, 2002.
r 04 U a 3.7 I
'" p' E¢John Caruso - LS-401-1 *IO tinal as aciminsterea.aoc Final Document. Represents the "as administered" written exam on August 2, 2002.
ry
'4 I 295031 Reactor Low Water Level 12 X
X EKI.03 Knowledge of the operational applications of the following 4.1 1
concepts as they apply to the Reactor Low Water Level: Water level effects on reactor power (23) 2.1.33 Ability to recognize indications for system operating parametrs 4.0 1
which are entry-level conditions for technica spea caitons SRO Only 295037 SCRAM Condition Present and Power X
EK1.06 Knowledge of the operational applications of the following 4.2 1
Above APRM Downscale or Unknown 1 concepts as they apply to the SCRAM Condition Present and Power Above APRM orenscale or Unknown: Cooldown effects on reactor power (25) 500000 High Containment Hydrogen Cone. 15 X
X EAI.05 Ability to operate and/or monitor the following as theyap t
3.3 1
High Containment Hydrogen Cone.: Wetwelt sprays (26)
O 3.3y 2.1.32 Ability to explain and apply system limits and precautions (27) 3C5 1
KIA Category Totals:
5
,4 3
5 4
5 Group Point Total:
26 ES 1 -1 SRO final as administered.doc
Page 5 Jo n Carus 'o - Eý -401-f SRO~
fta asa in-istere
. o ES-401 BWR SRO Examination OutlineForm ES-401-1 (RS, SI)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 EIAPE X I Name I Safety Function K
K K
A A
G K/A Topicis)
Imp.
Points 1
2 3
1 2
295002 Loss of Main Condenser Vacuum 13 X
X AK3.05 Knowledge of the reasons for the following responses as they 3.4 1
aoly to Loss of Main Condenser Vacuum Main steam isolation valve 2.4.4 Ability to recognize abnormal indications for system operating 4.3 1
parameters which are entry-level conditions for emergency and abnormal operating procedures (29) 295004 Partial or Total Loss of DC Pwr1 6 X
X AK1.02 Knowledge of the operational applications of the following 3.4 1
concepts as they apply to the Partial or Complete Loss of DC Pwr.
Redundant D.C. power supplies (30)
AA2.01 Ability to determine and interpret the following as they apply to 3.6 1
Partial or Total Loss of DC Pwr. Cause of partial or complete loss of D.C. power (31) SRO Only 295005 Main Turbine Generator Trip 13 X
X AK2.04 Knowiedge of the interrelations between Main Turbine 3.3 1
Generator Trip and the following: Main generator protection (32)
AA1.05 Ability to operate and/or monitor the following as they aoply to Main Turbine Generator Trip: Reactor/turbine pressure regulating 3.6 1
system (33) 295008 High Reactor Water Level 12 X
AA1.06 Ability to operate and/or monitor the following as they apply to 2.8 1
I High Reactor Water Level: HPCS (34) 295012 High Drywell Temperature 15 AK2.02 Knowledge of the interrelations between HIGH DRYWELL 3.7 1
TEMPERATURE and the following: Drywall cooling (35) SRO Only 295019 Partial or Total Loss of Inst. Air/
X AK3.02 Knowledge of the reasons for the following responses as they 3.4 1
apply to Part. or Comp. Loss of Inst. Air. Standby air compressor operation (36) 295020 Inadvertent Cont. Isolation / 5 & 7 X
2.1.23 Ability to perform specific system and integrated plant procedures 4.0 1
during different modes of plant operation (37) 295021 Loss of Shutdown Cooling 14 X
AA2.02 Ability to determine and interpret the following as they apolv to 3.4 1
Loss of Shutdown Cooling: RHRlshutdown cooling system tow (38)
SRO Only 295022 Loss of CRD Pumps II X
AKI.01 Knowledge of the operational applications of the following 3.4 1
concepts as they apply to the Loss of CR0 Pumps: Reactor pressure vs.
rod insertion capablirdy (39) 295029 High Suppression Pool Water Level 1S X
X EK1.01 Knowledge of the operational applications of the following 3.7 1
concepts as they apply to the High Suppression Pool Water Level:
Containment integity40) SRO Only EA1.03 Ability to operate and/or monitor the following as they apply to High Suppression Pool Water Level: RHR/LPCI (41) 295032 High Secondary Containment Area X
X EA2.03 Ability to determine and interpret the following as they apoly to X 4.0 1
Temperature 15 High Secondary Containment Area Temperature: Cause o hig area temperature (42) SRO Only 2.2.25 Knowledge of bases in technical specifications for limiting 3.7 1
conditions for operations and safety limits (43) SRO Only 295035 Secondary Containment High X x
[
EK3.02 Knowledge of the reasons for the following responses as th Differential Pressure/5 apply to Secondary Containment High Differential Pressure Secondary containment ventilation response (44)
KlACategoryPointTotals:
i3I I3 13 1
3I Group Point Total:
17 ES-401BWR SRO Examination OutlineForm ES-401-1 (RS, S1)
Plant Systems - Tier 2/Group I Final Document. Represents the "as administered" written exam on August 2, 2002.
SIonn,aruso - 1::*-4UI-1 -)KU Tinal as aaministered.doc System # /Name K
K IK K
K K
A A
A A
G KIA Topic(s)
Imp.
Points 1 2 3
4 5
6 1
2 3
4 202002 Recirculation Flow Control X
X K3.06 Knowiedce of the effect that a loss or 3.7 1
malfunction of the Recirculation Flow Control will have on the following:
Recrculation flow control valve pbsition (45)
K4.09 Knowled e of Reclrculation Flow Control design reature.s) and or interlock(s) 3.4 1
which provide tor the fol owing: Minimum and maxi Mum I!oi control valve position setpont(6 203000 RHRLPCh Injection Mode K13.03 Knowledge of the effect that a loss or 4.3 1
malfuncton of the RHR/LPCh: Injection Mode will have on the following: Automatic depressunization logic (47) 209001 LPCS X
A3,04 Ability to monitor automatic opertons 3.6 1
of the LPCSinduding: System flow (48) 209002 HPCS X
X K1.02 Knowiedge of the physical 3.5 1
connections an or eause-elTed relationships r atween HPCS and the following.
ppresson pool (49)
A4.07 Abily to manually operate and/or monitor n te control room: Une fill pump 2.8 1
(50) 211000 SLC X
X K1.05 Knowledge of the physical 3.6 1
connections and/or caus-ffrelationshiss between SLCand the following: RWCU (51) 2.1.32 Abili to ex an and aDDysystem lmits and prhcastibns (52) SRO Only 3.8 1
255A RX 6.07 Knowedge of the effect of a loss or 3.3 1
malfuncton of Ise following will have on APRMILPRM System: Flow Converter/Comparator (69) 2.1.32 Ability to explain and stem limits and precautions (54) SRO Only 3.8 1
217000 RCIC K204 Knowlede of electrical ower 2.6 1
supplies to the ollowing: Glendsa pressor (vacuum pump) (55)
A4.08 Ability to manually opreteandlor 3.6 1
monitor in the control room: RCIC system flow (53) 218000 ADS X
X K5.01 Knowledge of the operational 3.8 1
implications of e following concepts as they apply to the ADS ADS logic operation (56)
A3,03 Ability to monitor ajitomatic oerptions 3.8 1
of the ADS including: AD valve a ustical monitor noise (57)
X X
K2.09 Knowledge of electhcal power 2.9 1
223001 Primary CTMT and Auxiliaries supplies to the rolloving: Drywell cooling fans (58)
K5.01 Knowledoe of the operational 3.3 1
implications of the follo.ino concepts as they apply to the Primary CTM and Auxillanes vacoum breaker/resef operation (59) 223002 PCIS/Nuclear Steam Supply Shutoff X
A1.02 Ability to predict and/or monitor 3.7 1
han es in parmtr soitdwt oiern thP NulearStealnSpply 6loff controls incuding Valve closures 60 g___
Final Document. Represents the "as administered" written exam on August 2, 2002.
Pagle 6
SuJoh..*iU-nu iUi ru final as aaminsterea.aoc Final Document. Represents the "as administered" written exam on August 2, 2002.
PaQe 7 '
239002 SRVs x
X A2.03 Ability to (aLpredict the impacts of the 4.2 1
following on the bRvs and (b) based on those predictions, use procedures to correct, controlr or mitioate the consequences of those abnormal conditions or operations:
Stuck open SRV (61) 4.0 1
2.4.9 Knowted= e symptom based EOP mitigation strategies (82)SRO Only 241000 ReactorfTurbine Pressure Regulator X
A1.13 Ability to predict and/or monitor 2.7 1
crangs in parameterassociated with opera ng the Reacto urbine Pressure Regulator controls including: Main turbine speed (63) 259002 Reactor Water Level Control X
X K6.03 Knowledge of the effect that a loss or 3.1 1
malfunction of the followino will haye on the Reactor Water Level Conrrol: Main steam flow input (64)
A2.06 Ability to (a) predict the impacts of the fpllowin onthe eactor Water Lvel 3.4 1
Contro-and (b) based on those predicons, use procedures to correct, coPntrl, or mitigate the consequences of th*se abnormal conditions or o erations: Loss of controller signal output (
262001 AC Electrical Distribution X
K3.01 Knowledge of the effect that a loss or 3.7 1
malfunction of the AC Electrical Distribution will have on the following: Major I--system loads (66) 264000 EDGX K6.09 Knowledge of the effect that a loss or 3.5 1
realn of the following will have on the EDGe: D.C. power (67)
/A CategoryPoint Totats:
2 2j3 1
3 2
2 2
2 2
3 1 Group Point Total:
24 I
CN-1 A
.lUll L.ý dr utu-0-o-4U I-I or-tu final as aaminisierea.aoc ES-40i UBR SROU Examination OutlineForm ES-401-I (R8, SI)
Plant Systems - Tier 2/Group 2 System # I Name K
K K
K K
K A
A A
A G
K/A Topic(s)
Imp.
Points 201001 CRD Hydraulic X
2.4.4 Ability to recognize abnormal 4.3 1
indications for system operating prameters which are entry-level conditions or emergency and abnormal operating procedures (681 SRO Only 2140 RPIS X
A4.03 Abiliy to manually operate and/or 2.7 1
monitor in te control room: Control rod drive temperature (70) 215002 RBM X
A2.01 Ability to (a)predict the impacts of the 3.5 1
following on the RBM and (b) based on those predictions, use procedures to correct contro, or mitigate the consequences of those abnormal conditions or operatioa:
Withdrawal of control rod in high power region of core (71) 215003 IRM K4.02 Knowledge of IRM design feature(s) 4.0 1
and or rntedocets) whch oroviae for the 2olowing: Reacor SCRAM signals (72) 234000 Fuel Handling Equipment X!K5.05 Knowledge of the operational 3.7 1
implications of the following concepts as they apply to the Fuel Handling Equipment I
I
-ues orientation (73) 259001 Reactor Feedwater X
X K6.05 Knowledoe of the effect tat a loss or 2.7 1
malfunction of ole following will have on the Reactor Feedwater. Component cooling water (74)
A1.01 Ability to predict and/or monitor changres in parameters associated with 3.3 1
operat'Ing the.Reactor Feedwfatoer/ ystm c t(75)
Is including: Feedwater w sur 263000 DC Electrical Distribution X
X K2.01 Knowledge of electrical power 3.4 1
(*olies to ts e following: Major D.C. loads A1.01 Ability to predict and/or monitor 2.8 1
changes in parameters assodated with operating the DC Electrical Distribution controls including: Battery charging/discharging rate (77)
X K3.01 Knowledge of the effect that a loss or 3.4 malfunction of the Fire Protection will have on the following: The ability to detect fires (78) 3.6 1
2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies (79) SRO Only 400000 Component Cooling Water X
KI.02 Knowledge of the physical 3.4 1
connections and/or cause-effect relationships between Component Cooling Water and the following: Loads cooled by CCWS (80)
KfA Category Point Totals:
1 2I I 1 1 [1 [
r 0
[2 I Group PointTotal:
1 Final Document. Represents the "as administered" written exam on August 2, 2002.
P:lnA U Pnn*_ R *t
I onn Caruso - E:4u1-1 SR-O. final as administered.doc System # IName K
K K
K K
K6 A1 A2 A3 A4 G
KIATopic(s)
Imp.
Points 1
2 3
4 5j 201003 Control Rod and Drive Mechanism X
K5.03 Knowledge of the operational 3.4 1
implications of the following concepts as Drheyapply to the Control Rod,rand hv Me.hanism: Reactor power control (81) 233000 Fuel Pool Cooling and Cleanup X
2.4.4 Ability to recognize abnormal 4.3 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures (82) SRO Only 288000 Plant Ventilation X
K4.03 Knowledge of Plant Ventilation 2.9 1
Ss tems design featureas) and/or inYerlocks which proide for the following:
Automate starting and stopping of tans 1_
(83) 290002 Reactor Vessel Internals X
A2.02 Ability to (a) predict the impacts 3.9 1
of the following on tne Reactor Vessel Internals and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or
_____Category
__PointTotals:
__1_0 ogrations: Overprassunzation transient KIA Category Point Totals:
a 0
0 1
1 0
0 1
0 0
1 Group Point Total:4 Plant-Specific Priorities System I Topic Recommended Replacement for...
Reason Points Tier 3 Common Generic 2.2.11 Tier 3 Common Generic 2.2.34 An appropriate question can not be developed. Generic Fundamentals level of knowledge.
Tier 2 Group 2 259001 A1.01 Tier 2 Group 2 259001 K5.02 An approprlate question can not be I
developed. Generic Fundamentals level of knowledge.
Tier 2 Group 1 217000 A4.08 Tier 2 Group 1 215005 K4.08 An appropriate question can not be 1
developed. Replaced with RCIC operation question because of higher operational significance.
Plant-Specific Priority Total (limit 10):
3 Final Document. Represents the "as administered" written exam on August 2, 2002.
ES-401 WR SKU asamination Outlinerorm E-401-1 (RS, S1)
Plant Systems - Tier 2IGrouo 3
CJah r
Ciuisf
ý j-ý
-i
-Is E4O1 Fmbjjem dir c
a ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Facility:
NMPC U2 Date of Exam:
07129102 Exam Level: SRO Category K/A #
Topic Imp.
Points Conduct of 2.1.6 Ability to supervise and assume a management role during 4.3 1
Operations plant transients and upset conditions (85) SRO Only 2..4 Knowledge of system status criteria which require the3.
1 notification of plant personnel (87) 2.1.31 Ability to locate control room switches, controls and 3.9 1
indications and to determine that they are correctly reflecting the desired plant lineup (88)
Total 3
Equipment 2.2.12 Knowledge of surveillance procedures (89) 3.4 1
Control 2.2.17 Knowledge of the process for managing maintenance 3.5 1
activities during power operations (90) SRO Only 2.2.23 Ability to track limiting conditions for operations (91) SRO 3.8 1
Only 2.2.11 Knowledge of the process for controlling temporary 3.4 1
changes (92)
Total 4
Radiation 2.3.8 Knowledge of the process for performing a planned gaseous 3.2 1
Control radioactive release (93) SRO Only 2.3.9 Knowledge of the process for performing a containment 3.4 1
purge (94) 2.3.10 Ability to perform procedures to reduce excessive levels of 3.3 1
radiation and guard against personnel exposure (95) SRO Only 2.3.11 Ability to control radiation releases (96) 3.2 1
Total 4
Emergency 2.4.18 Knowledge of the specific bases for EOPs (97) 3.6 1
Procedures/
Plan 2.4.22 Knowledge of the bases for prioritizing safety functions 4.0 1
during abnormal/emergency operations (98) SRO Only 2.4.27 Knowledge of fire in plant procedure (99) 3.5 1
2.4.30 Knowledge of which events related to system 3.6 1
operationlstatus should be reported to outside agencies (86)
SRO Only 2.4.32 Knowledge of operator response to loss of all 3.5 1
annunciators(100) 2.4.35 Knowledge of local auxiliary operator tasks during 3.5 1
emergency operations Including system geography and system implications (9)
Total 6
Tier 3 Point Total (SRO) 17 Final Document. Represents the "as administered" written exam on August 2, 2002.
(
(
NRC Comments on Written Exam Question 1Unsats Comment
Response
IKA Change Enclosed R02 E
Cue
_x R04 Error in Justification section x
R015 U
Didn't understandB _& D distractors Modified stem and distractors.
IX R019 U
Borderline KA match Wrote new question R020 Setpoint Setpoiont Question Wrote new question X
RO23 U
Partial correct answer.
Modified distractors IX R024 i U A, B, an-d/C* are imp~lausible Replaced KA and wrote new question Y
X distractors i
R028 E
X R038 U
LOD, non dirscriminating Replaced KA and wrote new question Y
x R042 "U C & D implausible Added explanation as to plausibility X
R043 U
KA Mismatch Wrote new question 1X R044 U
'Math problem, minutia iWrote new question iX RP51 U
LOD, non dirscriminating Replaced KA and wrote new question.
Y X
Modified again after the first new question was similar to a JPM RO61 U
LOD, Basic system knowledge Replaced KA and wrote new question X
R062 U
,C & D implausible
!Rewrote, then rewrote again. Changed A
"total" steam flow to "one" transmitter R070 U
Green Full In light OFF is Changed to Process Computer indication X
implausible.
__'1 R083 E
'Words missing in stem Fixed lX R093
!E "A" is general-in nature and could be Fixed x
change of intent Fixed R095 U
!LOD 1 Fixed by removing specific values RP98
- E Plausibility of B,C and D?
Rewrote and made open reference X
SRO38 U
Modified stem and justification section X
SR086 U
Replaced KA and wrote new question Y
x SR095 IE Fixed X
Page 1 of 2
(
V
(
RO 96
- When RO 24 was replaced, it became a
!X
!duplicate with 96. Wrote new 96 RO Cat A Admin Exam Item Comment iResponse
!Outline Change? Enclosed JPM A. 1.2!
Redundent with JPM A.4 and non-
/Changed Outline. Replaced JPM with 2 Y
X
!discriminating open reference questions (A.1.1, A.1.2 JPM A.4 Remove reference to EPP-04 in Fixed
.X Initiating Cue JPM A.2 Needs to be Safety Related Fixed. Spent Fuel Pool Cooling Pump X
component JPM A.3 lObtain more readable copy of the
!Obtained an electronic copy X
survey map SRO Cat A Admin Exam JPM A. 1.2 Provide 3D Monicore printout for
'Done evaluation and determining MAPLHGR is out of spec JPM A.3.1 Remove cue to make candidate IDone X
determine the appropriate action Cat B JPMs JPM 2 Make step 4 Pass/Fail Done X
JPM 3 Make step 12 Pass/Fail
ýDone X
JPM 4 Make step 9 Pass/Fail. Removed Done X
two cues for additional operator I
monitoring system delta flow timers JPM 6 Make step 3 Pass/Fail
- Done X
JPM 7 Make step 4 Pass/Fail Done p
X JPM 8 Make step 4 Pass/Fail. Swap TS Done X
step, which is out of sequence.
JPM1 Made open-ing cii X
I M ade openin circuit breakers Pass/Fail t
Page 2 of 2
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ES-401 Record of Rejected KIAs Form ES-401-10 (R8, SI)
Tier Randomly Selected Reason for Rejection Group K/A Various Line out of K/As in K/As not applicable to Nine Mile Point Unit 2 design per ES-401 D.1.b Attached NUREG 1123 TIER 1 and GENERIC K/As Non-system GENERIC K/A statements suppressed per NRC Suppression Guidance Letter, 'Clarification of Guidance Regarding the TIER 2 Elimination of Inappropriate Knowledge and Abilities (K/A) on Written Operator Licensing Examinations' and ES-401 D.l.b Various
<2.5 Importance Rating All K/As with Importance rating less than 2.5 will not be selected during random generation per ES-401 D.1.b TIER 214000 K4.02 Randomly reselected K4.01, to avoid double jeopardy with A4.03. K4.02 is similar to A4.03.
2/GROUP 2 RO ONLY TIER 215002 2.4.49 Randomly reselected 2.4.50, 2.4.49 is not applicable, due to no Immediate Operator Actions for RBM at NMPC U2 2/GROUP 2 RO ONLY TIER 233000 K2.02 Randomly reselected K4.06, K2.02 is not applicable, Spent Fuel Pool Cooling System contains its' own system pumps.
2/GROUP 3 RO ONLY I
TIER 211000 K1.07 Randomly reselected K1.05, K1.07 is not applicable to Nine Mile Point Unit 2 design. SLS system injects through the HPCS sparger 2/GROUP 1 inside the downcomer.
SRO/RO TIER 239002 A2.04 Randomly reselected A2.03, due to over-sampling of ADS logic when compared with sampling in 218000 and 203000.
2/GROUP 1 SRO/RO The following are changes made to written exam outlines after initial outline submittal. These are also identified on Form 401 1 and 401-2 Written Outlines.
TIER 290003 K6.04 290003 K5.01 An appropriate question can not be developed. HVAC Fire system is manual valves.
2/GROUP 2 RO ONLY TIER 3 Common Generic Generic 2.2.11 An appropriate question can not be developed. Generic Fundamentals level of knowledge.
RO/SRO 2.2.34 TIER 259001 K5.02 259001 A1.01 An appropriate question can not be developed. Generic Fundamentals level of knowledge.
2/GROUP 1 (RO)
TIER 2/GROUP 2 (SRO)
RO TIER 1/
500000 EA1.05 500000 EK3.05 RO selected, unable to write question to original K/A for RO position
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(-'-"hr i
I I
SRO/RO 500000 2.1.28 500000 2.1.32 selected, unable to write question to original K/A TIER 1/
Group 1 SRO/RO 295022 AK2.02 295002 2.4.4, selected SRO original K/A overlap with RO outline when selected as a common TIER 1/
Group 2 SRO/RO 295029 EK1.01 295005 AA1.05 SRO made into common reselected to K/A applicable to both RO and SRO TIER 1/
Group 2 RO TIER 1/
295036 EK2.02 RO 295021 AK3.01 RO original K/A not applicable at NMPC 2 reselected to new K/A Group 3 SRO/RO 215002 A2.04 215002 A2.01 better match to question TIER 2/
Group 2 RO TIER 1/
295030 EA2.01 295030 EA2.02 better match to question Group 2 SRO TIER 1/Group 2 SRO/RO 264000 K6.06 264000 K6.09 better match to question TIER 2/
Group 1 RO TIER 2/
204000 A4.05 RO 204000 A4.06 RO better match to question Group 2 SRO/RO 288000 K3.05 288000 K4.03 better match to question TIER 2/
Group 3 SRO TIER 295013 AK3.02 SRO 295013 2.1.12 SRO better match to question 1/Group 1 SRO TIER 295012 2.4.49 SRO 295012 AK2.02 SRO unable to write appropriate LOD 1/Group 2 500000 EA1.05 Now on SRO only 295029 EA1.03 RO Now common 295020 2.1.23 RO Now common The following changes were made after exam submittal. Changes resulted from NRC review of the initial written submittal and facility rework to address the NRC comments.
SRO Tier 3 2.1.13 Deselected 2.1.13 due to potential security procedure concern. Randomly selected 2.1.27. This was a system purpose KA and inappropriate for SRO only question. Deselected 2.1.27 and randomly selected 2.1.9. Developed SRO only uestion which was ejectedby Chief Examiner. Deselected 2.1.9 and randomly selected 2.4.30. Developed new question for 2N.430 for SRO only Question 56.'"
RO TIER 201002 K3.01 215005 K6.07 randomly selected. Unable to write acceptable question for original KA. Change to 215005 K6.07 resulted in SRO 2/GROUP 1 Tier 2 Group 1 total points equals 24 instead of 23 and SRO Tier 2 Group 2 equal 12 points instead of 13. This is allowed by Form ES SRO TIER 401-1, Rev 8 Supp 1, Note 2. (Allowance to be + or - 1, due to required changes).
2/GROUP 2
/
V4*i
RO TIER 295017 AK3.04 295017 AK3.02 randomly selected. Unable to write acceptable question after multiple attempts for original KA l/GROUP 2 SRO TIER 1 GROUP 1 RO TIER 259001 K6.05 259001 K6.01 randomly selected. Unable to write acceptable question after multiple attempts for original KA 1/GROUP 1 SRO TIER 2 GROUP 2 I
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ES-401 NMP #2 7/02 EXAM Written Examination Review Worksheet 1
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
7 Q#
LOK LOD 7
(F/H)
(1-5)
Stem Cues T/F Cred.
Partial Job-Minutia
- /
Back-Qx SRO U/E/S Explanation Focus Dst.
Links ward KA 1
F 2
S 2
F 2
x E
Power and press. emphasized in the stem which cues correct answer also highlight in the stem MSIV. Licensee reformatted the stem.
3 H
3 S
4 H
2 S
5 F
2 S
6 H
2-3 S
7 H
3 5
8 H
2 S
9 H
2 S
set point question - okay in limited number 10 F
2 Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1.
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2.
Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (i.e., clues, specific determiners phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
More than one distractor is not credible.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4.
Check the appropriate box if a job content error is identified:
The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
- 4.
The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
The question requires reverse logic or application compared to the job requirements.
- 5.
Check the appropriate box if the sampled question does not match the approved K/A or an SRO-only question is not at the SRO level.
- 6.
Based on the reviewer's judgment, is the question as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 7.
For an "U" ratin s, at a minimum, ex lain how the A endix B s chometric attributes are not bein met.
ES-401 2
Form ES-401-9
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD 1
-II1 (F/H)
(1-5)
Stem Cues T/F Cred. lPartial Job-Minutia
- /
Back-Q U/E/S Explanation Focus 1
IDist.
I Link units ward KA O I 11 H
3 S
Verify for all RO EOP question on the exams that this is required knowledge for an RO at your facility. We discussed that beyond the identification of entry conditions and EOP bases it is not RO level knowledge interpret and apply the EOPs given a set of conditions. The licensee verified that the Ros had appropriate EOP learning objectives to test these areas.
12 F
2 S
13 F
2 S
14 H
3 S
15 F
2 X
U "B&D" distractors do not appear to be plausible at 8.5" hg Vac - how do we get inventory loss? Modified stem and distractors 16 F
2 S
17 F
3 S
18 H
3 S
19 F
2 X
U licensee agreed. Wrote new question 20 F
1-2 U
set point question okay in limited numbers. However, LOD is very low does not discriminate. Licensee replaced with an acceptable bank question.
21 F
2 S
22 H
3 S
23 F
3 X
X U
The question asks about method for tripping the turbine - "C" presents the same method for tripping the Main turbine looks to be partially correct. Modified distractors.
24 H
2 X
U Distractors not plausible. How would you get a power excursion in either case even if you blew down first. Why would the MSIVs close on a reactor scram. Need to explain why these are plausible. Licensee replaced question.
25 F
1-2 S
set point okay in limited number 26 F
2 S
27 H
3 S
28 H
2 X
E why would a broken tailpipe necessarily improve NPSH - it depends on where the break ? Modified distractor.
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
Q#
LOK LOD
,o (F/H) (1-5)
Stem ICuesiT/Fi' red. Partial Job-IMinutia
- / ABack-IQ~I U/E/S Explanation Focus Dist.
Link junits [ward KA Ony.
29 H
2 S
30 F
2 S
- 1.
LOK (F/H)
- 2.
LOD (1-5)
Stem Focus
- 3. Psychometric Flaws Cues T/F Cred.
t17 Partial Job-
- 4. Job Content Flaws Minutia
- 5. Other
- /IBack-IQ~ j.SRO
- 6.
U/E/S
- 7.
Explanation Lin units I
-A I~
2 I
I1 31 H
3 S
32 H
3 S
33 F
2 S
34 H
3 S
35 H
3 S
36 H
3 S
37 H
2 S
38 F
1-2 X
U Distractors do not appear to be credible also LOD is borderline doesn ot discriminate too basic. Licensee agreed. Replaced question 39 H
2 S
40 F
2 S
41 F
2 S
42 H
2 X
U Distractors do not appear to be credible especially "C&D". Explained why distractors are plausible 43 F
2 X
U not in LPCI mode. Licensee agreed will replace. Question replaced.
44 F
1-2 X
U This doesn't test plant knowledge only the ability to perform a simple math problem. Replaced question.
45 F
2 S
46 H
2 S
47 F
2 S
48 F
2 S
set point question okay in limited number.
49 F
2 S
50 H
2 S
I
ES-401 4
Form ES-401-9
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws 5, Oth/er
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
Stem Cues T/F Cred. Partial Job-Minutia
- /
Back-Qs SRO U/E/S Explanation Focus Dist. IJ Link I
]unitsjward K/A Ontly 1
51 F
1-2 X
U Knowing # of inputs is minutia - not important to safe operation of the IIIII_
plant. LOD borderline. Replaced question 52 H
3 S
53 H
3 S
54 H
3 S
55 F
2 S
electrical supply okay in limited #
56 H
2 S
57 F
2 S
58 F
2 S
59 F
2 S
60 H
3 S
61 F
1-2 U
Borderline LOD system purpose question - does not discriminate.
Replaced question 62 H
3 X
E "C&D" don't appear plausible. Changed stem 63 H
3 S
64 H
3 S
65 H
3 S
66 H
2 S
67 H
2 S
68 H
3 S
69 H
3 S
70 H
2 X
E "A&C" not credible distractors. Revised stem and distractors I I plausible if don't understand system operatioin.
NUREG-1021, Revision 8, Supplement 1
ES-401 5
Form ES-401-9 1
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws 5, Other
- 6.
- 7.
Q#
LOK LOD I
I (F/H)
(1-5)
Stem Cues T/F Cred. Partial Job-Minutia
- /
Back-Qi SR0 U/E/S Explanation Focus I
Dist.
Link units ward KA Only 71 H
2 S
72 H
2 S
73 H
2 S
74 H
3 S
75 H
3 S
76 F
3 S
77 F
3 S
78 H
3 S
79 H
2 S
80 H
2 S
81 H
2 S
82 F
2 S
83 F
2 S
see minor editorial comments for stem 84 H
3 S
85 F
2 S
86 H
3 S
87 H
2 S
88 F
2 S
89 F
2 S
90 H
3 EL_
S
NUREG-1021, Revision 8, Supplement I ES-401 6
Form ES-401-9
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 7.
Q#
LOK LOD 1TII (F/H)
(1-5)
Stem ICues T/F Cred. PartialJob-Minutia
- /
Back-U/E/S Explanation FocusJ _
Dist.
Link units ward IA Oty 91 F
2 S
92 H
3 S
good question 93 F
2 E
"A" could be agrued that it could result in a change of intent - too general - revise distractor to make more specific.
94 F
2 S
95 F
2 X
E With the stated pressure limitations stated in the stem-the answer I_
II apears to be obvious. Modified stem to make less leading 96 F
2 S
97 F
2 S
98 F
2 X
S?
Distractors don't appear plausible. Licensee will verify if plausibe.
Rewrote stem 99 F
2 S
100 H
3 S
3RO H
2 S
provide all of TS sect. 3 H
3 S
H 3
S 4
H 3
S 5
H 2
S 20 H
2 S
24 H
3 S
ý6 H
3 S
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws 5, Other
- 6.
- 7.
Q#
LOK LOD (F/H)
(1-5)
Stem ICues T/F Cred. Partial Job-Minutia
- /
Back-Q RO U/E/S Explanation 31 H
3 S
35 H
3 S
Okay if give entire TS section 3 if give on this section it would be like a direct lookup.
38 H
2 X
E "B&C" distractors don't seem credible. Have you lost secondary containment? And why would starting SBGT be plausibel? Revised stem and provided more justification for distractors.
o0 F
2 S
42 H
2 S
43 H
3 S
52 H
2 S
54 H
3 S
32 H
3 S
38 H
3 X
S Is "A" partially correct? Licensee agreed to make sure this is not correct by checking other procedures.
79 H
3 S
32 H
3 S
35 F
3 S
36 F
3 U
Current security requirements and NRC regulations/guidance would not allow this - verify acceptable with security officer. Please document a document changes request and enter into your corrective action program. Licensee replaced question.
)0 F
3 S
)I H
3 S
)3 H
3 S
)5 H
3 X
X E
"C&D" distractors don't appear credible. Licensee revised the stem to place RP supervisor In the stem and ask who besides the RP supv.
Is required to authorize.
)8 H
3 S
OPERATING EXAM COMMENTS:
RO, Al JPM, Perform a refuel floor evac. - Replace this JPM. Although, the task is important to safety - it doesn't discriminate for making a licensing decision, also this is redundant to the A.4 task in the sense it is another notification task. Replaced JPM with 2 new questions.
RO, A.2 JPM, Develop clearance for Hot Water Heating Pump, is not a safety significant pump? Please select a safety significant pump and have the candidate determine the blocking and tagging points and indicating the valves, and breaker required positions and tagging that would be required - forms not required? Also do not provide prints have candidate locate correct prints. Replaced with new JPM on safety significant component.
RO, A.3.1 question, Radiation Wok permit question. What is the highest rad level on the survey map? Get a clearer easy to read survey map for the exam.
RO, A.4 JPM, Perform required actions for injured and contaminated person. Have the CSO determine what procedure to use. Cue As CSO make required notifications. Initiating cue revised as suggested to make less leading.
SRO, A.1.2 JPM, Determine TS actions when in Single Loop. Step #3 don't cue MAPLHGR is OOS provide printout and let candidate determine OOS.
SRO, A.3 JPM, Initiating cue should be less leading, e.x. Take appropriate actions to ensure personnel safety.
Initiating cue revised as suggested to make less leading.
Asked licensee why the Admin. JPM that was planned for Radwaste Discharge Authorization was replaced. They had indicated on their Summary of Changes Following Initial Outline submittal that it was replaced because it was too difficult to administer. This has been used on many exams and is a good task so we agreed to discuss this further during prep week and for them to show why this determination was made. Determined to be too complex to administer for testing purposes also after initial licensing the SROs are provided additional supervisory training on performing this function.
JPMs - some critical steps were not marked as critical. The following steps will be revised to critical steps: JPM #2, step 4; JPM #3, step 12; JPM #4, step 9; JPM #6, step 3; JPM #7, step 4; JPM #8, step 4.
Scenarios - Critical Tasks in 8 of 10 cases do not meet the criteria established in NUREG 1021, Appendix D, section D.1.c, Measurable Performance Indicators. For example, in most cases no guidance is provided for when or by what point must the action be taken to be considered a failure. The licensee agreed with the comment and revised the CTs to provide further additional performance acceptance criteria.