ML031190638
| ML031190638 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/01/2002 |
| From: | Wilson F Entergy Nuclear Northeast |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-247/03-301, IP-TNG-02-196 50-247/03-301 | |
| Download: ML031190638 (47) | |
Text
- Entergy EI£
\\.--
u Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
-oRean Point 3 NPP O. Box 308 rucharan. NY 10511 Tel 9 1 36 8000 nyr 76 A1 6: 41 December 20, 2002 IP-TNG-02-196 Operational Safety Branch Division of Reactor Safety United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia Pennsylvania, 19406-1415 Att: Mr. R J Conte SENIOR REACTOR AND REACTOR OPERATOR INITIAL EXAMINATION -
INDIAN POINT STATION, UNITS 2 AND 3
Dear Mr. Conte,
In accordance with your letter of November 21, 2002, please find attached the examination outlines for the Indian Point Energy Center Reactor Operator and Senior Reactor Operator initial examinations.
If you have any questions, please contac
- r. Bill Altic at (914) 788-2629 for Unit 2, Mr.
Steve Joubert at (914) 788-2973 for Unit or me
) 788-2904.
Sincerely,
-Frank Wilson Superintendent - Operations Training Indian Point Energy Center
Review Comments for Exam Outline IP#2 LOIT exam Requested addition of one critical task to Scenario #1, "Manual reactor trip" although safety significant not really discriminating. After trip of second feed pump the operators must note reactor didn't trip and just push 2 buttons. It should be very obvious after trip of second feed pump that reactor should have tripped.
RO, admin JPM A.3, replace this is only GET level - although borderline acceptable try to come up with somethigRoore discriminating for making a licensing de gon.
4
/e HiA d Ah Consider whether JPMs S3 and S4 should be sequenced.
RO, admin JPM A.1.b review with other examiners to determine if really discriminating -
take partial logs and identify 3 Out of spec readings CST level, Cont Air Temp, 21 Accum pressure.
Ensure written SRO only question # 76 is written at the SRO level.
Indian Point Unit 2 & 3 2003 NRC Written Examination Written Examination Outline Methodology The written examination outline was developed using an electronic random outline generator. The application was developed using Visual Basic code, relying on a true random function based on the PC system clock. The random generator selects topics in a Microsoft Access Database containing Revision 2 of the PWR K&A catalogue. The selected data is then written to a separate data table.
The following topic area was deleted for generation of the March 2003 NRC ROISRO written examination:
System 025: Ice Condenser. The facilities do not have an Ice Condenser system The process used to develop the outlines is as follows:
System 025 above was suppressed prior to generation For Tier 1 and Tier 2 generic items, only the items required to be included on the NRC supplemental suppression guidance document are included in the generation process NO other topics or items were suppressed Outline is generated for all topics with KA importance >=2.5 25 potential SRO topics are randomly selected from Tier 1 AA2 and required generic items, Tier 2 A2 and required generic items, and Tier 3 generic items For RO/SRO outlines, the potential SRO 10CFR55.43(b) exam topics (Generic, Tier 1 and Tier 2 A2's) are randomly and automatically selected. The remaining topics are then randomly selected for either both exams or the RO exam, until all required topics are entered.
For RO/SRO outlines, the resulting examination outline will contain 75 or less common topics.
o For the IP2 and IP3 examination, topics numbered 72 -100 on the far right column of the outlines are the SRO only or RO only selected topics.
Numbers 1-71 are common topics. The numbers correspond to the planned test item numbers on the subsequent examination.
o Initial review of the SRO outline indicates that approximately 7 of the 29 SRO only topics may not be suitable for IOCFR55.43(b) test item development.
o To ensure that the minimum number of 10CFR55.43(b) topics can be developed, some common topics may have to be split into job-specific test items or some SRO only outline items may have to be changed to more suitable 10CFR55.43(b) topics and appropnately documented as required.
Indian Point Unit 2 & 3 2003 NRC Written Examination Written Examination Outline Methodology Written Outline selected topic disposition:
Topic may be accepted as is.
KA topics could be potentially duplicated due to the application write process.
If a KA topic is duplicated on an outline, it is manually removed and randomly replaced. No justification provided.
- ALL other rejected topics are listed on ES-401-10 with justification, including topics selected to replace the rejected item, and method of selection.
Identification of Plant Specific Priorities:
Focus on PSA or plant events.
Attempt to spread across Tier 1 and Tier 2 Philosophy is to replace or substitute for:
o lower priority topics.
o topics that will be difficult to develop a valid written test item.
o topics that are heavily weighted unnecessarily as a result of the random generation process.
For the IP2/1P3 examination, a common written examination outline was developed. Plant Specific Priorities were added in accordance with PSA information that was reasonably common to both of the units.
Indian Point Units 2 & 3 Operating Examination Plant Specific Priorities Plant Specific Analysis (PSA) high importance items were intentionally included in the IP2 and IP3 operating examinations.
Scenario events:
Loss of Feed (IP2 & IP3)
ATWS (IP2 & IP3)
LOCA (IP3)
SGTR (Backup scenario for IP2 and IP3) (Also plant event)
Loss of all AC Power (IP3)
Each of the scenarios considered transients, (ie., turbine trip failure), operator actions (manual reactor trip, emergency boration), and equipment failures (safeguards actuation failures), that were important to plant safety for both Indian Point units.
JPMs:
At least one high importance operator action is included in each section of the JPM walkthrough.
Simulator - Depressurize RCS after SGTR In-Plant - Align City Water Cooling to Charging Pumps By the nature of the examination, each event or task has some relevance to the plant specific analysis. The events above were specifically selected due to their overall importance.
ES-401 PWR SRO Examination Outline Form ES-401-3 Facility:
Indian Point Units 2 & 3 Date of Exam:
3/8/2003 Exam Level:
SRO l
K/A Category Point Point Tier Group K
K K
K K
K A l A A
A G
Total l1 2
3 4
5 6
1 2
3 4
1 4
1 4
6 8
1 24 Emergency &
2 1
1 1
4 4
5 16 Abnormal Plant 3
0 0
1 0
1 1
3 Evolutions Tier Totals 5
2 6
10 13 7
43 1
1 0
1 2
2 2
2 2
2 4
1 19
- 2.
2 3
2 2
2 1
0 0
1 1
1 4
17 Plant
-t Systems 3
0 0
0 0
0 0
0 2
1 0
1 4
Tier 4
2 3
4 3
2 2
5 4
5 6
40 Totals 4
2 3
3 2
5 4
6 4
- 3. Generic Knowledge and Abilities 3Cat Cat 2 Cat 3 Cat 4 1
Note:
- 1.
Ensure that at least two topics from every K/A 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 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 SRO license level, and the point totals for each system and category. K/A's below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
Page 1 of 14 NUREG-1021, Revision 8, Supplement 1
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 EIAPE#/Name / Safety Function KI K2 K3 Al A2 G
Number K/A Topic(s)
Imp.
000001 / Continuous Rod Withdrawal / 1 X
M1.05 Ability to operate and / or monitor the following as they apply to 4.2 57 the Continuous Rod Withdrawal: Reactor trip switches.
000003 / Dropped Control Rod / 1 X
AK2.05 Knowledge of the interrelations between the Dropped Control 2.8 58 Rod and the following: Control rod drive power supplies and l_
_ _logic circuits.
000005 / Inoperable/Stuck Control Rod / 1 X
AK1.03 Knowledge of the operational implications of the following 3.6 41 l
_concepts as they apply to the stuck rod: Xenon transient.
000011 / Large Break LOCA / 3 X
EA1.01 Ability to operate and monitor the following as they apply to a 3.8 61 Large Break LOCA: Control of RCS pressure and temperature to avoid violating PTS limits.
W/E04 / LOCA Outside Containment / 3 W/EO1 & E02 / Rediagnosis & SI Termination /3 X
EK3.2 Knowledge of the reasons for the following responses as they 3.9 62 apply to the (Reactor Trip or Safety Injection/Rediagnosis):
Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection/Rediagnosis).
l 000015 / 17 RCP Malfunctions / 4 X
Ml.22 Ability to operate and/or monitor the following as they apply to 4.2 52 the RCP malfunctions: RCP seal failure/malfunction BW/E09; CE/Al 3; W/E09 & El 0 / Natural Circ. / 4 X
EK3.1 Knowledge of the reasons for the following responses as they 3.6 42 apply to the (Natural Circulation Operations): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
BW/E09; CE/Al 3; W/E09 & El0 / Natural Circ. /4 X
2.4.50 Emergency Procedures/Plan: Ability to verify system alarm 3.3 90 setpoints and operate controls identified in the alarm response I
.manual.
000024 / Emergency Boration / 1 X
AA2.04 Ability to determine and interpret the following as they apply to 4.2 43 the Emergency Boration: Availability of BWST.
000026 / Loss of Component Cooling Water / 8 X
AK3.03 Knowledge of the reasons for the following responses as they 4.2 44 apply to the Loss of Component Cooling Water: Guidance and actions contained in EOP for Loss of CCW/nuclear service water.
000029 / Anticipated Transient w/o Scram / 1 X
EA2.02 Ability to determine or interpret the following as they apply to 4.4 91 ATWS: Reactor trip alarm.
000040 (BW/E05; CE/E05; W/E12) / Steam Line X
AK1.06 Knowledge of the operational implications of the following 3.8 46 Rupture - Excessive Heat Transfer / 4 concepts as they apply to Steam Line Rupture: High-energy steam line break considerations.
000040 (BW/E05; CE/E05; W/E12) / Steam Line X
EA1.2 Ability to operate and/or monitor the following as they apply to 3.7 47 Rupture - Excessive Heat Transfer / 4 the (Uncontrolled Depressurization of all Steam Generators):
Operating behavior characteristics of the facility.
l NUREG-1021, Revision 8, Supplement 1 Page 2 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE #Name
/ Safety Function IK K2 K
l2 T
K3 lA A2 G
N hlumber K/A Topic(s)
I Imp.
l CE/All1; W/E08/ RCS Overcooling - PTS / 4 X
EA2.1 Ability to determine and interpret the following as they apply to 4.2 92 the (Pressurized Thermal Shock): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
000051 / Loss of Condenser Vacuum / 4 X
AA1.04 Ability to operate and / or monitor the following as they apply to 2.5 48 the Loss of Condenser Vacuum: Rod position.
l 000055 / Station Blackout / 6 X
EA2.01 Ability to determine or interpret the following as they apply to a 3.7 49 Station Blackout: Existing valve positioning on a loss of instrument air system.
l 000057 / Loss of Vital AC Elec. Inst. Bus /6 X
AK3.01 Knowledge of the reasons for the following responses as they 4.4 50 apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.
000059 / Accidental Liquid Radwaste Rel. / 9 X
AA2.02 Ability to determine and interpret the following as they apply to 3.9 93 the Accidental Liquid Radwaste Release: The permit for liquid radioactive-waste release.
000062 / Loss of Nuclear Service Water /4 X
AA2.01 Ability to determine and interpret the following as they apply to 3.5 51 the Loss of Nuclear Service Water: Location of a leak in the CCWS.
000067 / Plant Fire On-site / 9 000068 (BW/A06) / Control Room Evac. /8 000069 (W/E14) / Loss of CTMT Integrity / 5 X
AA2.02 Ability to determine and interpret the following as they apply to 4.4 94 the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity.
000074 (W/E06 & E07) / Inad. Core Cooling / 4 X
EK1.05 Knowledge of the operational implications of the following 3.2 53 concepts as they apply to the Inadequate Core Cooling:
Definition of saturated liquid.
000074 (W/E06 & E07) / Inad. Core Cooling / 4 X
EK1.3 Knowledge of the operational implications of the following 3.9 54 concepts as they apply to the (Degraded Core Cooling):
Annunciators and conditions indicating signals, and remedial actions associated with the (Degraded Core Cooling).
000074 (W/E06 & E07) / Inad. Core Cooling / 4 X
EA1.2 Ability to operate and/or monitor the following as they apply to 3.7 55 the (Saturated Core Cooling): Operating behavior characteristics of the facility.
BWIE03 / Inadequate Subcooling Margin /4 4 000076 / High Reactor Coolant Activity / 9 X
AA2.02 Ability to determine and interpret the following as they apply to 3.4 56 the High Reactor Coolant Activity: Corrective actions required for high fission product activity in RCS.
BW/A02 & A03 / Loss of NNI-X/Y / 7 K/A Category Point Totals:
4 1
4 6
8 1
Group Point Total:
24 NUREG-1021, Revision 8, Supplement 1 Page 3 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE #I Name /Safety Function KI K2 K3 Al A2 G
Number K/ATopic(s)
Mp.
Q#
000007 (BW/E02 & El 0; CE/E02) / Reactor Trip -
X 2.1.14 Conduct of Operations: Knowledge of system status criteria, 3.3 95 Stabilization - Recovery / 1 which require the notification of plant personnel.
l BW/A01 I Plant Runback / 1 BW/A04 / Turbine Trip / 4 000008 / Pressurizer Vapor Space Accident / 3 X
AK2.02 Knowledge of the interrelations between the Pressurizer Vapor 2.7 59 Space Accident and the following: Sensors and detectors.
000009 / Small Break LOCA /3 X
EA1.18 Ability to operate and monitor the following as they apply to a 3.2 60 l__._._._small break LOCA: Balancing of HPI loop flows.
BW/E08; W/E03 / LOCA Cooldown - Depress. /4 X
EA1.02 Ability to operate and/or monitor the following as they apply to 3.9 96 the (LOCA Cooldown and Depressurization): Operating behavior characteristics of the facility.
W/E1 1 / Loss of Emergency Coolant Recirc. / 4 X
EK1.2 Knowledge of the operational implications of the following 4.1 99 concepts as they apply to the (Loss of Emergency Coolant Recirculation): Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).
000022 / Loss of Reactor Coolant Makeup / 2 X
M1.08 Ability to operate and/or monitor the following as they apply to 3.3 63 the Loss of Reactor Coolant Pump Makeup: VCT level.
000025 / Loss of RHR System /4 X
AA2.07 Ability to determine and interpret the following as they apply to 3.7 64 the Loss of Residual Heat Removal System: Pump cavitation.
000027 / Pressurizer Pressure Control System X
AA2.15 Ability to determine and interpret the following as they apply to 4.0 45 Malfunction / 3 the Pressurizer Pressure Control Malfunctions: Actions to be taken if PZR pressure instrument fails high.
000032/ Loss of Source Range NI / 7 000033 / Loss of Intermediate Range NI /7 X
AA2.10 Ability to determine and interpret the following as they apply to 3.8 97 the Loss of Intermediate Range NI: Tech Spec limits if both IR channels have failed 000037/ Seam Generator Tube Leak / 3 X
2.2.22 Equipment Control: Knowledge of limiting conditions for 4.1 98 operations and safety limits.
000038 / Steam Generator Tube Rupture / 3 X
EK3.01 Knowledge of the reasons for the following responses as they 4.3 69 apply to the Steam Generator Tube Rupture: Equalizing pressure on primary and secondary sides of ruptured SG 000054 (CE/E06) / Loss of Main Feedwater / 4 X
2.4.2 Emergency Procedures/Plan: Knowledge of system setpoints, 4.1 65 interlocks, and automatic actions associated with EOP entry conditions 000054 (CE/E06) / Loss of Main Feedwater / 4 X
2.2.25 Equipment Control: Knowledge of bases in technical 3.7 72 specifications for limiting conditions for operations and safety limits.
BW/E04; W/E05 / Inadequate Heat Transfer -
Loss of Secondary Heat Sink / 4 I
I I
.I.
NUREG-1021, Revision 8, Supplement 1 Page 4 of 1 4
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 EIAPE #Name i Safety Function KI K2 K3 Al A2 l
Number K/A Topic(s)
Imp.
l 000058 / Loss of DC Power / 8 X
AA2.03 Ability to determine and interpret the following as they apply to 3.9 67 the Loss of DC Power: DC loads lost, impact on ability to operate and monitor plant systems 000060 / Accidental Gaseous Radwaste Rel. / 9 000061 / ARM System Alarms / 7 X
MA1.01 Ability to operate and/or monitor the following as they apply to 3.6 68 the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation.
W/E16 / High Containment Radiation / 9 000065 / Loss of Instrument Air / 8 X
2.1.2 Conduct of Operations: Knowledge of operator responsibilities 4.0 66 during all modes of plant operation.
CE / E09 / Functional Recovery K/A Category Point Totals:
1 1
1 4
4 5
Group Point Total:
16 NUREG-1 021, Revision 8, Supplement 1 Page5 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE#/ Name / Safety Function I KI I K2 I K3 I Al I A2 I G I Number l
K/A Topic(s) l Imp-000028 / Pressurizer Level Malfunction / 2 X
AK3.02 Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions:
Relationships between PZR pressure increase and reactor makeup/letdown imbalance.
000036 (BW/A08) / Fuel Handling Accident / 8 X
2.2.28 Equipment Control: Knowledge of new and spent fuel Imovement procedures 000056 / Loss of Off-site Power / 6 X
AA2.51 Ability to determine and interpret the following as they apply to the Loss of Offsite Power: AT, (core, heat exchanger, etc.)
BW/E13 & E14 / EOP Rules and Enclosures BW/A05 / Emergency Diesel Actuation / 6 CE/Al 6 / Excess RCS Leakage /2
_2_.
W/El 3 / Steam Generator Over-pressure / 4 W/E15 / Containment Flooding / 5
.I-
~~~~~
I......
i 11
+--t-+---4
+
I _..
~~ _I
___..I I..I I--
i K/A Category Point Totals:
0 0
I O
1 1
Group Point Total:
NUREG-1021, Revision 8, Supplement 1 Page 6 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System #/ Name Kl K2 K3 K4 K5 IK6 A2 A4 G
Number K/A Topic(s)
Imp.
Q#
001 Control Rod Drive X
A2.03 Ability to (a) predict the impacts of the following 4.2 73 malfunction or operations on the CRDS-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of stuck rod or Misaligned rod.
003 Reactor Coolant Pump X
A3.04 Ability to monitor automatic operation of the 3.6 1
l___
003 Reactor Coolant Pump X
K4.04 Knowledge of RCPs design feature(s) and/or 3.1 2
interlock(s) which provide for the following:
Adequate cooling of RCP motor and seals.
004 Chemical and Volume Control X
K6.17 Knowledge of the effect of a loss or malfunction 4.6 3
of the following will have on the CVCS: Flow paths for emergency boration 013 Engineered Safety Features Actuation X
A1.01 Ability to predict and/or monitor changes in 4.2 4
parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: RCS pressure and temperature.
014 Rod Position Indication X
A4.01 Ability to manually operate and/or monitor in 3.1 17 the control room: Rod selection control.
015 Nuclear Instrumentation X
K5.02 Knowledge of the operational implications of 2.9 5
the following concepts as they apply to the NIS:
l___
Discriminator/compensation operation.
017 In-Core Temperature Monitor X
A4.01 Ability to manually operate and/or monitor in 4.1 6
the control room: Actual in-core temperatures.
022 Containment Cooling X
A4.04 Ability to manually operate and/or monitor in 3.2 7
the control room: Valves in the CCS.
025 Ice Condenser SUPPRESSED 026 Containment Spray X
A1.01 Ability to predict and/or monitor changes in 4.2 18 parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment pressure.
056 Condensate X
A2.04 Ability to (a) predict the impacts of the following 2.8 74 malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or
__operations:
Loss of condensate pumps.
NUREG-1021, Revision 8, Supplement 1 Page 7of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System#/ Name K
lKIl K2 lK3K4 K5 K6 Al A2 A3 A4 G
Number K/A Topic(s)
Imp.
Q#
059 Main Feedwater X
K4.19 Knowledge of MFW design feature(s) and/or 3.4 8
interlock(s), which provide for the following:
Automatic feedwater isolation of MFW.
059 Main Feedwater X
A4.03 Ability to manually operate and monitor in the 2.9 9
control room: Feedwater control during power increase and decrease.
061 Auxiliary / Emergency Feedwater X
K6.02 Knowledge of the effect of a loss or malfunction 2.7 10 of the following will have on the AFW components: Pumps.
063 DC Electrical Distribution X
K3.02 Knowledge of the effect that a loss or 3.7 24 malfunction of the DC electrical system will have on the following: Components using DC control power.
063 DC Electrical Distribution X
K1.03 Knowledge of the physical connections and/or 3.5 23 cause-effect relationships between the DC distribution system and the following systems:
Battery Charger and battery 068 Liquid Radwaste X
2.4.31 Emergency Procedures / Plan: Knowledge of 3.4 75 annunciators alarms and indications, and use of the response instructions.
071 Waste Gas Disposal X
K5.04 Knowledge of the operational implication of the 3.1 11 following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.
072 Area Radiation Monitoring X
A3.01 Ability to monitor automatic operation of the 3.1 12 ARM system, including: Changes in ventilation alignment.
K/A Category Point Totals:
1 0
1 2
2 2
2 2
2 4
1 Group Point Total:
19 NUREG-1021, Revision 8, Supplement 1 Page8 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 System # [Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
Number K/A Topic(s)
Imp.
Q#
002 Reactor Coolant_l L
1 006 Emergency Core Cooling X
K2.02 Knowledge of bus power supplies to the 2.9 1a3 following: Valve operators for accumulators.
010 Pressurizer Pressure Control X
A3.02 Ability to monitor automatic operation of the 3.5 1 4 PZR PCS, including: PZR pressure.
011 Pressurizer Level Control X
K2.02 Knowledge of bus power supplies to the 3.2 1 5 following: PZR heaters.
012 Reactor Protection X
K5.01 Knowledge of the operational implications of 3.8 16 the following concepts as they apply to the RPS: DNB.
012 Reactor Protection X
2.4.12 Emergency Procedures/Plan: Knowledge of 3.9 27 general operating crew responsibilities during emergency operations 016 Non-nuclear Instrumentation X
2.1.28 Conduct of Operations: Knowledge of the 3.3 76 purpose and function of major system
_components and controls.
027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control X
A4.02 Ability to manually operate and/or monitor in 3.9 31 the control room: Location and interpretation of containment pressure indications.
029 Containment Purge 033 Spent Fuel Pool Cooling X
A2.02 Ability to (a) predict the impacts of the following 3.0 19 malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SFPCS.
034 Fuel Handling Equipment X
K4.02 Knowledge of design features and/or interlocks 3.3 32 which provide for the following: Fuel movement 035 Steam Generator X
2.4.4 Emergency Procedures/Plan: Ability to 4.3 20 recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
039 Main and Reheat Steam X
K1.06 Knowledge of the physical connections and/or 3.0 21 cause-effect relationships between the MRSS and the following systems: Condenser steam
_______dump.
NUREG-1021, Revision 8, Supplement 1 Page 9 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 System # I Name K
K2 K3 K4 K5 K
6 A2 A3 A4 G
Number K/A Topic(s)
Imp.
Q#
055 Condenser Air Removal X
K3.01 Knowledge of the effect that a loss or 2.7 22 malfunction of the CARS will have on the following: Main condenser.
062 AC Electrical Distribution X
2.1.33 Conduct or Operations: Ability to recognize 4.0 77 indications for system operating parameters which are entry level conditions for Technical Specifications 062 AC Electrical Distribution X
K1.03 Knowledge of the physical connections and/or 4.0 26 cause-effect relationships between the AC distribution system and the following systems:
DC Distribution 064 Emergency Diesel Generator X
K3.03 Knowledge of the effect that a loss or 3.9 25 malfunction of the ED/G system will have on the following: ED/G (Manual loads).
073 Process Radiation Monitoring 075 Circulating Water 079 Station Air X
K1.01 Knowledge of the physical connections and/or 3.1 28 cause-effect relationships between the SAS and the following systems: IAS.
086 Fire Protection X
K4.07 Knowledge of design feature(s) and/or 2.8 29 interlock(s) which provide for the following:
MT/G and T/G protection.
103 Containment K/A Category Point Totals:
3 2
2 2
1 1
4 Group Point Total:
17 NUREG-1021, Revision 8, Supplement 1 Page 10 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 System #/Name Kl lK2 K3 lK4 K5 K6 Al A2 A3 A4 G
Number K/A Topic(s) lEImp. lQ#
l 005 Residual Heat Removal X
A2.02 Ability to (a) predict the impacts of the following 3.7 30 malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.
007 Pressurizer Relief / Quench Tank 008 Component Cooling Water X
A2.02 Ability to (a) predict the impacts of the following 3.5 78 malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequences of High/Low Surge Tank Level 041 Steam Dump/Turbine Bypass Control X
A3.03 Ability to monitor automatic operation of the 2.8 33 SDS, including: Steam flow.
045 Main Turbine Generator 076 Service Water 078 Instrument Air X
2.1.23 Conduct of Operations: Ability to perform 4.0 79 specific system and integrated plant procedures during all modes of plant operation.
K/A Category Point Totals:
[
0 0
0 0
0 0
2 l 1 l0 l
1l Group Point Total:
[
4
=
=
0F---
I..;.
NUREG-1021, Revision 8, Supplement 1 Page 1 1 of 14
Plant-Specific Priorities System I Topic Recommended Replacement for....
Reason Points APE 054 G2.4.2 (Question 65)
EPE 038EK1.04 High PRA importance; Event as well as mitigating system 1
APE 058 AA2.03 (Question 67)
APE 061DAK2.01 High PRA importance; Loss of high importance system 1
SYS 004 K6.17 (Question 3)
SYS 004K2.04 High PRA importance; Risk significant post-accident human error APE 015/017 AA1.22 (Question 52)
APE 068 AA1.20 High PRA importance; Risk significant post-accident human error 1
EPE 038 EK3.01 (Question 69)
EPE El 6 EK3.4 High PRA importance; Event as well as risk significant post-1 accident human error SYS 012 Generic 2.4.12 (Question 27)
SYS 075 Generic 2.4.30 High PRA importance; Event as well as mitigating systems 1
Plant-Speciflc Priority Total: (limit 10) l 6
NUREG-1021, Revision 8, Supplement 1 Page 12 of 14
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5 Facility:
Indian Point Units 2 & 3 Date of Exam:
3/8/2003 Exam Level:
SRO l
Category K/A #
Topic Imp.
Q#
2.1.11 Knowledge of less than one hour technical 3.8 80 specification action statements for systems.
Conduct of 2.1.20 Ability to execute procedure steps.
4.2 81 Operations 2.1.8 Ability to coordinate personnel activities outside 3.6 34 the control room.
Total 3
2.2.6 Knowledge of the process for making changes in 3.3 82 procedures as described in the safety analysis report.
2.2.22 Knowledge of LCOs and Safety Limits 4.1 83 2.2.34 Knowledge of the process for determining the 3.2 84 internal and external effects on core reactivity.
l Equipment 2.2.33 Knowledge of control rod programming.
2.9 36 Control 2.2.2 Ability to manipulate the console controls as 3.5 37 required to operate the facility between shutdown and designated power levels.
2.2.13 Knowledge of tagging and clearance procedures.
3.8 35 Total 6
2.3.10 Ability to perform procedures to reduce excessive 3.3 85 levels of radiation and guard against personnel exposure.
Radiation 2.3.2 Knowledge of facility ALARA program.
2.9 86 Control 2.3.9 Knowledge of the process for performing a 3.4 38 containment purge.
Total 3
2.4.45 Ability to prioritize and interpret the significance 3.6 87 of each annunciator or alarm.
2.4.24 Knowledge of loss of cooling water procedures.
3.7 88 Emergency 2.4.12 Knowledge of general operating crew 3.9 89 Procedures I responsibilities during emergency operations.
Plan 2.4.29 Knowledge of the emergency plan.
4.0 40 2.4.19 Knowledge of EOP layout, symbols, and icons.
3.7 39 Total 5
Tier 3 Point Total SRO 17 NUREG-1021, Revision 8, Supplement 1 Page 13 of 14
ES-401 Record of Rejected K/As Form ES-401-10 Tier/ Group Randomly Selectedi K/A Reason for Rejection 2/1 (Question 23) 063 A4.03 No indication available for applicable topic in control room at facility. Replaced with randomly selected 063 K1.03.
1/2 (Question 97) 033 AA2.111 Redundant Topic (Double Jeopardy) with SYS 015K5.02 (Question 5). Replaced with manually selected 033 AA2.10.
1/3 (Question 100) 036 AA1.04 Would not yield 10CFR55.43(b) question for SRO. Replaced with manually selected Generic topic 2.2.28 to ensure coverage of 1 OCFR55.43(b) item 6 and/or 7 for SRO. (Was not randomly selected as part of generic tier 3).
2/2 (Question 26) 073 Al.01 Controls of PRM system are not operated in a manner that will cause change in the plant condition required by the topic. Replaced with randomly generated 062 K1.03 3 (Question 82) 2.1.18 Topic switched for RO 2.2.6 (RO 93) for SRO Only application 2/1 (Question 4) 013 Al.09 No suitable test item. Manually selected closest suitable KA to the selected topic (013A1.01) 1/1 (Question 41) 005 AK2.01 No suitable test item. Randomly selected topic in 005 area (005 AK1.03) 2/2 (Question 77) 062 A2.12 No suitable test item. Manually selected Generic topic 2.1.33 to ensure 10CFR55.43(b) coverage for SRO 2/3 (Question 78) 008 A2.07 No suitable test item. Manually selected 008 A2.02 in same topic area 1/2 (Question 98) 037 G2.1.30 Not suitable for SRO. Manually selected Generic topic 2.2.22 to ensure 10CFR55.43 (b) coverage for SRO 1/2 (Question 99)
E05 G2.1.27 Too many similar topics. Randomly selected Eli1 EK1.2 to replace 2/2 (Question 32) 034 K6.02 Too many similar topics. Randomly selected 034 K4.02 to replace NUREG-1021, Revision 8, Supplement 1 Page 14 of 14
>nitia1 NRC License Examination
- Indian Point Unit 2 Written Test Item Summary Senior Reactor Operator Question K/A Source Cognitive
- Comments 1
003 A3.04 New Higher 2
003 K4.04 New Higher 3
004 K6.17 Bank Higher 4
013 A1.01 Bank Memory 5
015 K5.02 Bank Higher 6
017 A4.01 Bank Higher 7
022 A4.04 New Memory 8
059 K4.19 Modified Higher 9
059 A4.03 New Memory 10 061 K6.02 Bank Higher 11 071 K5.04 Modified Memory 12 072 A3.01 New Memory 13 006 K2.02 New Memory 14 010 A3.02 New Higher 15 011 K2.02 New Memory 16 012 K5.01 Bank Memory 17 014 A4.01 Bank Memory 18 026 A1.01 New Higher 19 033 A2.02 New Higher 20 035 G2.4.4 New Higher 21 039 K1.06 Bank Higher 22 055 K3.01 Bank Higher 23 063 K1.03 New Memory 24 063 K3.02 Bank Higher 25 064 K3.03 Modified Higher 26 062 K1.03 Bank Higher 27 012 G2.4.12 New Memory 28 079 K1.01 New Memory 29 086 K4.07 Bank Memory 30 005 A2.02 Modified Higher 31 028 A4.02 New Memory 32 034 K4.02 New Memory 33 041 A3.03 New Higher 34 G2.1.8 Bank Memory 35 G2.2.13 Bank Memory 36 G2.2.33 Modified Higher 37 G2.2.2 Modified Higher 38 G2.3.9 New Memory 39 G2.4.19 New Memory 40 G2.4.29 Bank Memory 41 005 AK1.03 Bank Higher 42 E09 EK3.1 Bank Memory 43 024 AA2.04 Bank Higher 44 026 AK3.03 Bank Memory 45 027 AA2.15 New Higher 46 040 AK1.06 Bank Higher 47 040 EA1.2 Bank Memory 48 051 AA1.04 Bank Higher 49 055 EA2.01 Bank Higher 50 057 AK3.01 New Higher Confidential Page I Final Draft 1/27/2003
Initial NRC License Examination Indian Point Unit 2 Written Test Item Summary Senior Reactor Operator 51 062 AA2.01 Bank Higher 52 015/017 AA1.22 Bank Higher 53 074 EK1.05 Modified Higher 54 074 EK1.3 Modified Memory 55 075 EA1.2 Bank Memory 56 076 AA2.02 Bank Memory 57 001 AA1.05 New Memory 58 003 AK2.05 New Higher 59 008 AK2.02 Bank Higher 60 009 EA1.18 New Higher 61 011 EA1.01 Modified Memory 62 EO1IE02 EK3.2 Bank Memory 63 022 AA1.08 Bank Higher 64 025 AA2.07 Bank Memory 65 054 G2.4.2 Bank Higher 66 065 G2.1.2 New Memory 67 058 AA2.03 Modified Memory 68 061 AA1.01 Bank Higher 69 038 EK3.01 Bank Memory 70 028 AK3.02 New Higher 71 036 AA2.51 New Higher 72 054 G2.2.25 New Memory SRO 73 001 A2.03 Bank Higher SRO 74 056 A2.04 New Higher SRO 75 068 G2.4.31 Bank Memory SRO 76 016 G2.1.28 Bank Higher 77 062 G2.1.33 New Higher SRO 78 008 A2.02 New Higher SRO 79 078 G2.1.23 New Higher SRO 80 G2.1.11 Bank Higher SRO 81 G2.1,20 Modified Higher SRO 82 G2.2.6 New Memory SRO 83 G2.2.22 Bank Memory SRO 84 G2.2.34 Bank Higher 85 G2.3.10 Bank Higher SRO 86 G2.3.2 Bank Memory SRO 87 G2.4.45 Bank Higher SRO 88 G2.4.24 New Higher SRO 89 G2.4.12 Bank Memory SRO 90 E09 G2.4.50 Bank Higher SRO 91 029 EA2.02 New Higher SRO 92 E08 EA2.1 Bank Higher SRO 93 059 AA2.02 New Memory SRO 94 069 AA2.02 Bank Higher SRO 95 007 G2.1.14 New Higher SRO 96 E03 EA1.02 Bank Higher 97 033 AA2.10 New Higher SRO 98 037 G2.2.22 Modified Higher SRO 99 El I EK1.2 Bank Higher 100 036 G2.2.28 Bank Higher SRO Confidential Page 2 Final Draft 1/27/2003
ES-401 PWR RO Examination Outline Form ES-401-4 Facility:
Indian Point 2 & 3 Date of Exam:
3/8/2003 Exam Level:
RO K/ACategory Point l
Point Tier Group K
K K
K K
K A
A A
A G
Total 1
2 3 l4 5
6 1
2 3
4 1
4 0
3 4
5 0
16 Emergency &
2 1
2 3
5 4
2 17 Abnormal Plant 3
0 0
1 0
1 1
3 Evolutions Tier Totals 5
2 7
9 10 3
36 1
3 0
0 5
3 2
1 1
4 3
1 23 Plant 2
4 24 1
2 0
2 1
1 1
2 20 Systems 3
0 1
2 1
0 0
1 1
1 1
0 8
Toitears 7
3 6
7 5
2 4
3 6
5 3
51
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 13 1
3 4
2 4
1 Note:
- 1.
Ensure that at least two topics from every K/A 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 category/tier.
6.*
The generic K/As in tiers 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 SRO license level, and the point totals for each system and category. K/A's below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
IP 2 & 3 - RO Outline Rev 0.doc Page 1 of 14 NUREG-1021, Revision 8, Supplement 1
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 EIAPE #Name
/ Safety Function K1 K2 K3 Al A2 G
Number]
K/A Topic(s)
Imp l
00005 Inoperable/Stuck Control Rod / 1 X
AK1.03 Knowledge of the operational implications of the following 3.2 41 l
_concepts as they apply to the stuck rod: Xenon transient.
000015/17 RCP Malfunctions / 4 X
AA1.22 Ability to operate and/or monitor the following as they apply to 4.0 52 the RCP malfunctions: RCP seal failure/malfunction BW/E09; CE/Al 3; W/E09 & 10 Natural Circ./ 4 X
EK3.1 Knowledge of the reasons for the following responses as they 3.3 42 apply to the (Natural Circulation Operations): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for l
these operating characteristics.
000024 Emergency Boration / I X
AA2.04 Ability to determine and interpret the following as they apply to 3.4 43 the Emergency Boration: Availability of BWST.
000026 / Loss of Component Cooling Water / 8 X
AK3.03 Knowledge of the reasons for the following responses as they 4.0 44 apply to the Loss of Component Cooling Water: Guidance and actions contained in EOP for Loss of CCW/Nuclear Service Water.
000027 / Pressurizer Pressure Control System X
AA2.15 Ability to determine and interpret the following as they apply to 3.7 45 Malfunction / 3 the Pressurizer Pressure Control Malfunctions: Actions to be taken if PZR pressure instrument fails high.
l 000040 (BW/E05; CE/E05; W/E12) / Steam Line X
AK1.06 Knowledge of the operational implications of the following 3.7 46 Rupture - Excessive Heat Transfer / 4 concepts as they apply to Steam Line Rupture: High-energy steam line break considerations.
000040 (BW/E05; CE/E05; W/E12) / Steam Line X
EA1.2 Ability to operate and/or monitor the following as they apply to 3.6 47 Rupture - Excessive Heat Transfer / 4 the (Uncontrolled Depressurization of all Steam Generators):
Operating behavior characteristics of the facility.
CE/All1; W/E08 / RCS Overcooling - PTS /4
_4______
000051 / Loss of Condenser Vacuum / 4 X
MAA.04 Ability to operate and / or monitor the following as they apply to 2.5 48 the Loss of Condenser Vacuum: Rod position.
000055 / Station Blackout / 6 X
EA2.01 Ability to determine or interpret the following as they apply to a 3.4 49 Station Blackout: Existing valve positioning on a loss of instrument air system.
000057 / Loss of Vital AC Elec. Inst. Bus / 6 X
AK3.01 Knowledge of the reasons for the following responses as they 4.1 50 apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.
000062 / Loss of Nuclear Service Water / 4 X
AA2.01 Ability to determine and interpret the following as they apply to 2.9 51 the Loss of Nuclear Service Water: Location of a leak in the CCWS.
000067 / Plant Fire On-site / 9 000068 (BW/A06) / Control Room Evac. / 8 000069 (W/E1 4) / Loss of CTMT Integrity / 5 NUREG-1021, Revision 8, Supplement 1 Page 2of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE #Name
/ Safety Function KI lK2 K3 Al A2 G
Number K/A Topic(s)
Imp.
Q#
000074 (W/E06 & E07) / Inad. Core Cooling / 4 X
EK1.05 Knowledge of the operational implications of the following 2.8 53 concepts as they apply to the Inadequate Core Cooling:
Definition of saturated liquid.
000074 (W/E06 & E07) / Inad. Core Cooling / 4 X
EK1.3 Knowledge of the operational implications of the following 3.7 54 concepts as they apply to the (Degraded Core Cooling):
Annunciators and conditions indicating signals, and remedial actions associated with the (Degraded Core Cooling).
000074 (W/EO6 & E07) / Inad. Core Cooling / 4 X
EA1.2 Ability to operate and/or monitor the following as they apply to 3.2 55 the (Saturated Core Cooling): Operating behavior characteristics of the facility.
BW/E03 / Inadequate Subcooling Margin /4 000076 / High Reactor Coolant Activity / 9 X
AA2.02 Ability to determine and interpret the following as they apply to 2.8 56 the High Reactor Coolant Activity: Corrective actions required for high fission product activity in RCS.
BW/A02 & A03 / Loss of NNI-X/Y /7 K/A Category Point Totals:
4 0
3 4
5 0
Group Point Total:
16 NUREG-1021, Revision 8, Supplement 1 Page 3 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE #Name
/ Safety Function KI K2 K3 Al A2 G
Number K/A Topic(s)
Imp-000001 / Continuous Rod Withdrawal / 1 X
AA1.05 Ability to operate and / or monitor the following as they apply to 4.3 57 the Continuous Rod Withdrawal: Reactor trip switches.
000003 / Dropped Control Rod / 1 X
AK2.05 Knowledge of the interrelations between the Dropped Control 2.5 58 Rod and the following: Control rod drive power supplies and logic circuits.
000007 (BW/E02 & El0; CE/E02) / Reactor Trip -
Stabilization - Recovery / 1 BW/A01 / Plant Runback/ I BW/AO4 / Turbine Trip /4 4 000008 / Pressurizer Vapor Space Accident /3 X
AK2.02 Knowledge of the interrelations between the Pressurizer Vapor 2.7 59 l_
_ _Space Accident and the following: Sensors and detectors.
000009 / Small Break LOCA / 3 X
EA1.18 Ability to operate and monitor the following as they apply to a 3.4 60 small break LOCA: Balancing of HPI loop flows.
000011 / Large Break LOCA / 3 X
EA1.01 Ability to operate and monitor the following as they apply to a 3.7 61 Large Break LOCA: Control of RCS pressure and temperature to avoid violating PTS limits, W/E04 / LOCA Outside Containment / 3 X
EK1.3 Knowledge of the operational implications of the following 3.5 97 concepts as they apply to the (LOCA Outside Containment):
Annunciators and conditions indicting signals, and remedial actions associated with the (LOCA Outside Containment).
BW/E08; W/E03 / LOCA Cooldown / Depress. /4 l
W/El1 / Loss of Emergency Coolant Recirc. /4 I
WE/01 & 02 / Rediagnosis & Si Termination / 3 X
EK3.2 Knowledge of the reasons for the following responses as they 3.0 62 apply to the Reactor Trip or Safety Injection/Rediagnosis:
Normal, abnormal and emergency operating procedures I associated with (Reactor Trip or Safety Injection/Rediagnosis).
WE/01 & 02 / Rediagnosis & Si Termination /3 X
EA2.2 Ability to determine and interpret the following as they apply to 3.3 98 the (Si Termination): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
000022 / Loss of Reactor Coolant Makeup / 2 X
AA1.08 Ability to operate and/or monitor the following as they apply to 3.4 63 the Loss of Reactor Coolant Pump Makeup: VCT level.
000025 / Loss of RHR System / 4 X
AA2.07 Ability to determine and interpret the following as they apply to 3.4 64 the Loss of Residual Heat Removal System: Pump cavitation.
000029 / Anticipated Transient w/o Scram / 1 000032 / Loss of Source Range NI / 7 X
AA2.04 Ability to determine and interpret the following as they apply to 3.1 72 the Loss of Source Range instrumentation: Satisfactory Source Range/Intermediate Range overlap 000033 / Loss of Intermediate Range NI / 7 000037 / Steam Generator Tube Leak / 3 NUREG-1021, Revision 8, Supplement 1 Page 4 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 EIAPE#/Name/Safety Function KI K2 K3 Al A2 G I Number K/A Topic(s)
Imp.
l Q
000038 / Steam Generator Tube Rupture / 3 X
EK3.01 Knowledge of the reasons for the following responses as they 4.1 69 apply to the Steam Generator Tube Rupture: Equalizing pressure on primary and secondary sides of ruptured SG 000054 (CE/E06) / Loss of Main Feedwater / 4 X
2.4.2 Emergency Procedures/Plan: Knowledge of system setpoints, 3.9 65 interlocks, and automatic actions associated with EOP entry conditions BW/E04; W/E05 / Inadequate Heat Transfer -
X 2.4.6 Emergency Procedures/Plan: Knowledge of symptom based 3.1 100 Loss of Secondary Heat Sink / 4 EOP mitigation strategies 000058 / Loss of DC Power /8 X
AA2.03 Ability to determine and interpret the following as they apply to 3.5 67 the Loss of DC Power: DC loads lost. Impact on ability to operate and monitor plant systems 000058 / Loss of DC Power / 8 X
AK3.02 Knowledge of the reasons for the following responses as they 4.0 99 apply to the Loss of DC Power: Actions contained in EOP for loss of DC power.
000059 / Accidental Liquid Radwaste Rel. / 9 000060 / Accidental Gaseous Radwaste Rel. /9 000061 / ARM System Alarms / 7 X
M1.01 Ability to operate and/or monitor the following as they apply to 3.6 68 the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation.
W/El 6 / High Containment Radiation / 9 CE/E09 / Functional Recovery K/A Category Point Totals:
1 2
3 5
4 2
Group Point Total:
17 NUREG-1021, Revision 8, Supplement 1 Page 5 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APEI#1 Name I Safety Function
'K flK 3lA1lA2 Number I K/ATopic(s)
Imp.
l Q#
000028 / Pressurizer Level Malfunction / 2 X
AK3.02 Knowledge of the reasons for the following responses as they 2.9 70 apply to the Pressurizer Level Control Malfunctions:
Relationships between PZR pressure increase and reactor
_ ________ makeup/letdown imbalance.
000036 (BW/A08) / Fuel Handling Accident /8 000056 / Loss of Off-site Power / 6 X
AA2.51 Ability to determine and interpret the following as they apply to 3.3 71 the Loss of Offsite Power: AT, (core, heat exchanger, etc.)
000065 / Loss of Instrument Air /8 X
2.1.2 Conduct of Operations: Knowledge of operator responsibilities 3.9 66 during all modes of plant operation.
BW/E13 & E14 / EOP Rules and Enclosures BW/A07 / Flooding / 8 CE/Al 6 / Excess RCS Leakage / 2 W/El 3 / Steam Generator Over-pressure /4 W/E1 5 / Containment Flooding / 5 K/A Category Point Totals:
0 0
1 0
1 1
______Group Point Total:3 NUREG-1021, Revision 8, Supplement 1 Page 6 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # Name K1 K2 K3 K4 K5 A
A4 G
Number lKA Topic(s)
Imp l 001 Control Rod Drive X
K4.02 Knowledge of CRDS design feature(s) and/or 3.8 73 interlock(s) which provide for the following:
Control rod mode select control (movement control).
001 Control Rod Drive X
A3.05 Ability to monitor automatic operation of the 3.5 78 CRDS, including: Individual versus group position 003 Reactor Coolant Pump X
A3.04 Ability to monitor automatic operation of the 3.6 1
RCPS, including: RCS flow.
003 Reactor Coolant Pump X
K4.04 Knowledge of RCPS design feature(s) and/or 2.8 2
interlock(s) which provide for the following:
Adequate cooling of RCP motor and seals.
004 Chemical and Volume Control X
K5.19 Knowledge of the operational implications of 3.5 74 the following concepts as they apply to the CVCS: Concept of SDM.
004 Chemical and Volume Control X
K6.17 Knowledge of the effect of a loss or malfunction 4.4 3
of the following will have on the CVCS: Flow paths for emergency boration 013 Engineered Safety Features Actuation X
A2.01 Ability to (a) predict the impacts of the following 4.6 75 malfunctions or operations on the ESF Actuation System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: LOCA 013 Engineered Safety Features Actuation X
A1.01 Ability to predict and/or monitor changes in 4.0 4
parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including: RCS pressure and temperature.
015 Nuclear Instrumentation X
K5.02 Knowledge of the operational implications of 2.7 5
the following concepts as they apply to the NIS:
Discriminator/compensation operation.
015 Nuclear Instrumentation X
K4.03 Knowledge of NIS design feature(s) and/or 3.9 76 interlock(s) provide for the following: Reading of source range/intermediate range/power range outside Control Room.
017 In-Core Temperature Monitor X
K1.01 Knowledge of the physical connections and/or 3.2 77 cause/effect relationship between the ITM system and the following: Plant computer 017 In-Core Temperature Monitor X
A4.01 Ability to manually operate and/or monitor in 3.8 6
the Control Room: Actual in-core temperatures.
NUREG-1021, Revision 8, Supplement I Page 7of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System #I Name
=
K K2 K317 K5 d
A1 A2 A3 A4 G
Number K/A Topic(s)
Imp.
Q#
022 Containment Cooling X
A4.04 Ability to manually operate and/or monitor in 3.1 7
the Control Room: Valves in the CCS.
025 Ice Condenser SUPPRESSED 056 Condensate X
K1.03 Knowledge of the physical connections and/or 2.6 83 cause-effect relationships between the Condensate system and the following systems:
MFW 056 Condensate X
2.1.2 Conduct of Operations: Knowledge of operator 3.3 79 responsibilities during all modes of plant operation.
059 Main Feedwater X
K4.19 Knowledge of MFW design feature(s) and/or 3.2 8
interlock(s) which provide for the following:
Automatic feedwater isolation of MFW.
059 Main Feedwater X
A4.03 Ability to manually operate and monitor in the 2.9 9
Control Room: Feedwater control during power increase and decrease.
061 Auxiliary / Emergency Feedwater X
K6.02 Knowledge of the effect of a loss or malfunction 2.6 10 of the following will have on the AFW components: Pumps.
061 Auxiliary / Emergency Feedwater X
K4.04 Knowledge of AFW design feature(s) and/or 3.1 80 interlock(s) which provide for the following:
Prevention of AFW runout by limiting AFW flow.
068 Liquid Radwaste X
A3.02 Ability to monitor automatic operation of the 3.6 81 Liquid Radwaste System including: Automatic isolation.
068 Liquid Radwaste X
K1.07 Knowledge of the interrelations and/or cause-2.7 82 effect relationships between the Liquid Radwaste System and the following: Sources of liquid waste for LRS.
071 Waste Gas Disposal X
K5.04 Knowledge of the operational implication of the 2.5 11 following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.
072 Area Radiation Monitoring X
A3.01 Ability to monitor automatic operation of the 2.9 12 ARM system, including: Changes in ventilation l_KACtegryPoitTtas:__0__53_21_14__1_rouP alignment.
KACategory Point Totals:
3 0
0 5
3 2
1 1
4 3
1 Group Point Total:
2 NUREG-1021, Revision 8, Supplement 1 Page 8 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System Name KS1 K2 K3 K4 K5 K6 Al A2 lA3 A4 G
Number K/A Topic(s)
Imp Q#
002 Reactor Coolant X
K5.19 Knowledge of the operational implications of 2.6 84 the following concepts as they apply to the RCS: Neutron embrittlement.
006 Emergency Core Cooling X
K2.02 Knowledge of bus power supplies to the 2.5 13 following: Valve operators for accumulators.
010 Pressurizer Pressure Control X
A3.02 Ability to monitor automatic operation of PZR 3.6 14 I
- IPCS, including: PZR pressure.
011 Pressurizer Level Control X
K2.02 Knowledge of bus power supplies to the 3.1 15 following: PZR heaters.
012 Reactor Protection X
K5.01 Knowledge of the operational implications of 3.3 16 the following concepts as they apply to the RPS: DNB.
012 Reactor Protection X
2.4.12 Emergency Procedures/Plan: Knowledge of 3.4 27 general operating crew responsibilities during emergency operations 014 Rod Position Indication X
A4.01 Ability to manually operate and/or monitor in 3.3 17 I the Control Room: Rod selection control.
016 Non-nuclear Instrumentation X
K3.04 Knowledge of the effect that a loss or 2.6 85 malfunction of the NNIS will have on the following: MFW system.
026 Containment Spray X
A1.01 Ability to predict and/or monitor changes in 3.9 18 parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment pressure.
029 Containment Purge X
A1.02 Ability to predict and/or monitor changes in 3.4 86 parameters (to prevent exceeding design limits) associated with operating the Containment Purge System controls including: Radiation levels.
033 Spent Fuel Pool Cooling X
A2.02 Ability to (a) predict the impacts of the following 2.7 19 malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SFPCS.
035 Steam Generator X
2.4.4 Emergency Procedures/Plan: Ability to 2.5 20 recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
NUREG-1021, Revision 8, Supplement 1 Page 9 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System#IName K1 K2 lK3 K4 K'
K6 A
A2 l A3 l A4 G
Number K
Topic(s)
Imp.
Q#
039 Main and Reheat Steam X
K1.06 Knowledge of the physical connections and/or 3.1 21 cause-effect relationships between the MRSS and the following systems: Condenser steam dump.
055 Condenser Air Removal X
K3.01 Knowledge of the effect that a loss or 2.5 22 malfunction of the CARS will have on the following: Main condenser.
062 AC Electrical Distribution X
K1.03 Knowledge of the physical connections and/or 3.5 26 cause-effect relationships between the AC distribution system and the following systems:
DC Distribution 063 DC Electrical Distribution X
K1.03 Knowledge of the physical connections and/or 2.9 23 cause-effect relationships between the DC distribution system and the following systems:
Battery Charger and battery 063 DC Electrical Distribution X
K3.02 Knowledge of the effect that a loss or 3.5 24 malfunction of the DC Electrical System will have on the following: Components using dc control power.
064 Emergency Diesel Generator X
K3.03 Knowledge of the effect that a loss or 3.6 25 malfunction of the ED/G system will have on the following: ED/G (manual loads).
073 Process Radiation Monitoring 075 Circulating Water 079 Station Air X
K1.01 Knowledge of the physical connections and/or 3.0 28 cause-effect relationships between the SAS and the following systems: IAS.
086 Fire Protection X
K4.07 Knowledge of design feature(s) and/or 2.5 29 interlock(s) which provide for the following:
MT/G and T/G protection.
K/A Category Point Totals:
4 2
4 1
2 0
2 1
1 1
2 Group Point Total:
20 NUREG-1021, Revision 8, Supplement 1 Page 10 of 14
INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 System # I Name l
K1 lK2 lK3 K4 lK5 6
Al A2 A3 A4 G I Number K/A Topic(s)
Imp.
Q#
005 Residual Heat Removal X
A2.02 Ability to (a) predict the impacts of the following 3.5 30 malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.
007 Pressurizer Relief/Quench Tank 008 Component Cooling Water X
K3.01 Knowledge of the physical connections and/or 3.4 90 cause-effect relationships between the CCWS and the following: Loads cooled by CCWS 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control X
A4.02 Ability to manually operate and/or monitor in 3.7 31 the Control Room: Location and interpretation of containment pressure indications.
034 Fuel Handling Equipment X
K4.02 Knowledge of design features and/or interlocks 2.5 32 which provide for the following: Fuel movement 041 Steam Dump/Turbine Bypass Control X
A3.03 Ability to monitor automatic operation of the 2.7 33 SDS, including: Steam flow.
045 Main Turbine Generator X
A1.06 Ability to predict and/or monitor changes in 3.3 88 parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: Expected response of secondary plant parameters following T/G trip.
076 Service Water X
K2.01 Knowledge of bus power supplies to the 2.7 89 following: Service water.
076 Service Water X
K3.07 Knowledge of the effect that a loss or 3.7 87 malfunction of Service Water will have on the l
following: ESF loads 078 Instrument Air 103 Containment K/A Category Point Totals:
0 1
2 1
0 0
1 1
1 1
0 Group Point Total:
8 NUREG-1021, Revision 8, Supplement 1 Page I11 of 14
Plant-Specific Priorities System / Topic Recommended Replacement for...
Reason Points APE 054 G2.4.2 (Question 65)
EPE 038EK1.04 High PRA importance; Event as well as mitigating system 1
APE 058 AA2.03 (Question 67)
APE 060AK2.01 High PRA importance; Loss of high importance system 1
EPE E05 G2.4.6 (Question 100)
APE 059AA2.02 High PRA importance; Event as well as mitigating systems 1
SYS 004 K6.17 (Question 3)
SYS 004K2.04 High PRA importance; Risk significant post-accident human error l
APE 015/017 AAI.22 (Question 52)
APE 068 M1.20 High PRA importance; Risk significant post-accident human error 1
EPE 038 EK3.01 (Question 69)
EPE E16 EK3.4 High PRA importance; Event as well as risk significant post-1 accident human error SYS 008 K3.01 (Question 90)
SYS 103 A4.01 High PRA importance; Risk significant post-accident human error 1
SYS 012 Generic 2.4.12 (Question 27)
SYS 075 Generic 2.4.30 High PRA importance; Event as well as mitigating systems 1
Plant-Specific Priority Total: (limit 10) 8 NUREG-1021, Revision 8, Supplement 1 Page 12 of 14
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5 Facility:
Indian Point Units 2 & 3 Date of Exam:
3/8/2003 Exam Level:
RO Category K/A #
Topic Imp.
Q#
2.1.2 Knowledge of operator responsibilities during all 3.0 91 modes of plant operation.
2.1.18 Ability to make accurate, clear and concise logs, 2.9 93 records, status boards, and reports.
Conduct of 2.1.8 Ability to coordinate personnel activities outside 3.8 34 Operations the Control Room.
Total 3
2.2.12 Knowledge of surveillance procedures.
3.0 92 Equipment 2.2.13 Knowledge of tagging and clearance procedures.
3.6 35 Control 2.2.33 Knowledge of control rod programming.
2.5 36 2.2.2 Ability to manipulate the console controls as 4.0 37 required to operate the facility between shutdown and designated power levels.
Total 4
2.3.4 Knowledge of radiation exposure limits and 2.5 94 contamination control, including permissible levels in excess of those authorized.
Radiation 2.3.9 Knowledge of the process for performing a 2.5 38 Control containment purge.
Total 2
2.4.14 Knowledge of general guidelines for EOP 3.0 95 flowchart use.
Emergency 2.4.34 Knowledge of RO tasks performed outside the 3.8 96 Procedures /
main control room during emergency operations Plan including system geography and system implications.
2.4.19 Knowledge of EOP layout, symbols, and icons.
2.7 39 2.4.29 Knowledge of the emergency plan.
2.6 40 Total 4
Tier 3 Point Total RO 13 NUREG-1021, Revision 8, Supplement 1 Page 13 of 14
ES-401 Record of Rejected K/As Form ES-401-10 Tier/ Group Randomly Selected! K/A Reason for Rejection 1/2 (Question 72) 054 G2.2.25 No connection to 10CFR55.41 for RO. Replaced with randomly generated 032 AA2.04 2/2 (Question 23) 063 A4.03 No indication available for applicable topic in control room at facility. Replaced with randomly generated 063 K1.03.
2/1 (Question 78) 056 G2.2.22 No connection to 10CFR55.41 for RO and no TS connection to system. Replaced with l
randomly generated 001 A3.05 2/1 (Question 83) 071 A4.27 No indication or control available in control room. Replaced with randomly generated 056 K1.03 2/1 (Question 75) 013 K4.17 Operation not performed at facility. Replaced with randomly generated 013 A2.01 2/1 (Question 74) 004 K5.02 Potential Double Jeopardy with 071 K5.04. Replaced with manually selected 004 K5. 19.
(Manually selected the next topic with same KA importance value) 2/2 (Question 26) 073 A1.01 Controls of PRM system are not operated in a manner that will cause change in the plant condition required by the topic. Replaced with randomly generated 062 K1.03 3 (Question 93) 2.2.6 Not RO level topic. Replaced by trading topic with SRO 2.1.18 (SRO 82) 2/1 (Question 4) 013A1.09 No suitable test item. Manually selected closest suitable KA to the selected topic l
~(01 3AI.01)I 1/1 (Question 41) 005 AK2.01 No suitable test item. Randomly selected topic in 005 area (005 AK..03) 2/1 (Question 77) 0017 K4.02 No suitable test item. Randomly selected topic in area (017 K 1.01) 2/3 (Question 87) 007A2.06 No suitable test item. Randomly selected topic in area (076 K3.07) 2/3 (Question 32) 034 K6.02 Related item on exam. Randomly selected topic in area (034 K4.02) 2/1 (Question 82) 068 A2.04 Related item on exam. Randomly generated topic in area (068 K1.07)
NUREG-1021, Revision 8, Supplement 1 Page 14 of 14
Initial NRC License Examination Indian Point Unit 2 Written Test Item Summary Reactor Operator Question K/A Source Cognitive Comments 1
003 A3.04 New Higher 2
003 K4.04 New Higher 3
004 K6.17 Bank Higher 4
013 A1.01 Bank Memory 5
015 K5.02 Bank Higher 6
017 A4.01 Bank Higher 7
022 A4.04 New Memory 8
059 K4.19 Modified Higher 9
059 A4.03 New Memory 10 061 K6.02 Bank Higher 11 071 K5.04 Modified Memory 12 072 A3.01 New Memory 13 006 K2.02 New Memory 14 010 A3.02 New Higher 15 011 K2.02 New Memory 16 012 K5.01 Bank Memory 17 014 A4.01 Bank Memory 18 026 Al.01 New Higher 19 033 A2.02 New Higher 20 035 G2.4.4 New Higher 21 039 KI.06 Bank Higher 22 055 K3.01 Bank Higher 23 063 K1.03 New Memory 24 063 K3.02 Bank Higher 25 064 K3.03 Modified Higher 26 062 K1.03 Bank Higher 27 012 G2.4.12 New Memory 28 079 KI.01 New Memory 29 086 K4.07 Bank Memory 30 005 A2.02 Modified Higher 31 028 A4.02 New Memory 32 034 K4.02 New Memory 33 041 A3.03 New Higher 34 G2.1.8 Bank Memory 35 G2.2.13 Bank Memory 36 G2.2.33 Modified Higher 37 G2.2.2 Modified Higher 38 G2.3.9 New Memory 39 G2.4.19 New Memory 40 G2.4.29 Bank Memory 41 005 AK1.03 Bank Higher 42 E09 EK3.1 Bank Memory 43 024 AA2.04 Bank Higher 44 026 AK3.03 Bank Memory 45 027 AA2.15 New Higher 46 040 AK1.06 Bank Higher 47 040 EA1.2 Bank Memory 48 051 AA1.04 Bank Higher 49 055 EA2.01 Bank Higher 50 057 AK3.01 New Higher Confidential Page 1 Final Draft 1/27/2003
Initial NRC License Examination Indian Point Unit 2 Written Test Item Summary Reactor Operator 51 062 AA2.01 Bank Higher 52 015/017 AA1.22 Bank Higher 53 074 EK1.05 Modified Higher 54 074EK1.3 Modified Memory 55 075 EAI.2 Bank Memory 56 076 AA2.02 Bank Memory 57 001 AA1.05 New Memory 58 003 AK2.05 New Higher 59 008 AK2.02 Bank Higher 60 009 EA1.18 New Higher 61 011 EA1.01 Modified Memory 62 EO1/EO2 EK3.2 Bank Memory 63 022 AA1.08 Bank Higher 64 025 AA2.07 Bank Memory 65 054 G2.4.2 Bank Higher 66 065 G2.1.2 New Memory 67 058 AA2.03 Modified Memory 68 061 AA1.01 Bank Higher 69 038 EK3.01 Bank Memory 70 028 AK3.02 New Higher 71 036 AA2.51 New Higher 72 032 AA2.04 New Higher 73 001 K4.02 Bank Higher 74 004 K5.19 Modified Higher 75 013 A2.01 Modified Higher 76 015 K4.03 Bank Memory 77 017 K1.01 Modified Higher 78 001 A3.05 Bank Higher 79 056 G2.1.2 New Memory 80 061 K4.04 Bank Memory 81 068 A3.02 Bank Memory 82 068 K1.07 Bank Memory 83 056 K1.03 New Memory 84 002 K5.19 New Memory 85 016 K3.04 Bank Higher 86 029 A1.02 New Memory 87 076 K3.07 Bank Higher 88 045 A1.06 Bank Higher 89 076 K2.01 New Memory 90 008 K3.01 Modified Higher 91 G2.1.2 Bank Memory 92 G2.2.12 Bank Memory 93 G2.1.18 New Memory 94 G2.3.4 Bank Memory 95 G2.4.14 Bank Higher 96 G2.4.34 Modified Memory 97 E04EK1.3 Bank Higher 98 EOl/E02 EA2.2 Bank Memory 99 058 AK3.02 New Memory 100 E05 G2.4.6 Bank Higher Confidential Page 2 Final Draft 1/27/2003
ES-301 Administrative Topics Outline Form-ES-301 -1
[Facility:
Indian Point 2 Date of Examination:
3/10/2003 Examination Level:
SRO Operating Test Number:
1 Administrative Topic/Subject Describe method of evaluation:
Descipton 1
ONE Administrative JPMV, OR j2. TWO Administrative Questions A.1a Conduct of 2.1.7 Ability to evaluate plant performance and make operational Operations judgments based on operating characteristics, reactor behavior, and instrument interpretation. (3.7/4.4)
JPM:
Review a QPTR calculation and direct appropriate actions A.1 b Conduct of 2.1.18 Ability to make accurate, clear, and concise logs, records, status Operations boards, and reports. (2.9/3.0)
JPM:
Review Control Room Log Entries A.2 Equipment Control 2.2.17 Knowledge of the process for managing maintenance activities during power operations. (2.3/3.5)
JPM:
Review (for approval) a completed surveillance for Tech Spec required equipment A.3 Non-Emergency 2.3.4 (3.1)
Knowledge of radiation exposure limits and contamination dose imitscontrol, including permissible levels in excess of those qusestiont authorized.
QUESTION: Given the plant in a SAE and a personnel exposure history, determine the exposure limit for a Non-Emergency operation.
2.3.2 (2.9)
Knowledge of facility ALARA program.
Emergency Exposure Limits QUESTION: Given a situation requiring valve alignment verification in a Question radiation area, determine the waiver requirements for independent or concurrent verification of a locked valve and identify an alternate process for verification.
A.4 Emergency Plan 2.4.44 Knowledge of Emergency Plan Protective Action Recommendations. (2.1/4.0)
JPM:
Perform Protective Action Recommendation Is, _-
P`
-) 5 0 2
_Vt 0
Form ES-301 -1 SRO ADM OutlineNU E-02,Rvso 8
NUREG-1021, Revision 8
ES-301 Administrative Topics Outline Form-ES-301-1 Facility:
Indian Point 2 Date of Examination:
3/10/2003 Examination Level:
RO Operating Test Number:
1 Administrative Describe method of evaluation:
Topic/Subject Description
- 2. TWO Administrative Questions A.1a Conduct of 2.1.7 Ability to evaluate plant performance and make operational Operations judgments based on operating characteristics, reactor behavior, and instrument interpretation. (3.7/4.4)
JPM:
Perform QPTR Calculation A.1b Conduct of 2.1.18 Ability to make accurate, clear, and concise logs, records, status Operations boards, and reports. (2.9/3.0)
JPM:
Perform a set of Control Room logs A.2 Equipment 2.2.12 Knowledge of surveillance procedures. (3.0/3.4)
Control JPM:
Perform the RCS Leak Rate surveillance A.3 Radiation 2.3.2 Knowledge of facility ALARA program. (2.5/2.9)
Exposure Control JPM:
Determine appropriate RWP and take action for High Area Radiation alarm A.4 Emergency Plan 2.4.43 Knowledge of RO responsibilities in E-Plan implementation.
(3.3/3.1)
Question:
Duties of operations department personnel when site accountability is required 2.4.29 Knowledge of the Emergency Plan. (2.6/4.0)
Question: Emergency Response Facilities activated in a Site Area Emergency Form ES-301-1 RO ADM Outline NUREG-1021, Revision 8
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility:
Indian Point 2 Date of Examination:
3/10/2003 Exam Level:
RO/SROI Operating Test No.:
1 lB.1: Control Room Systems System JPM Description Type Safety Code*
Function S1 001 Stabilize reactor power at 104 amps following N,S,A,L 1
Rod Control criticality S2 006 Fill a Safety Injection Accumulator D,S 2
ECCS (Repeat from last NRC exam)
I S3 010 Depressurize the RCS following a SGTR M,S,A,E 3
Pressurizer Pressure Control S4 041 Cooldown the RCS to target temperature N,S,A,E 4S Steam Dump S5 007 Respond to PRT High Pressure N,S,A,E 5
Pressurizer Relief Tank S6 062 Restore 6.9KV Busses from off-site power.
D,S 6
AC Distribution S7 015 Return a Power Range Channel to service N,S 7
Nuclear Instrumentation B.2 Facility Walk-Through P1 004 Align City Water Cooling to Charging pumps R,D,E 2
CVCS P2 041 Local Operation of Atmospheric Steam Dumps D,E 4S Steam Dump P3 063 Startup a Battery Charger D
6 DC Distribution Type Codes:
(D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA, (E)OP/AB NOTES Si S3 S4 S5 S7 New JPM. Candidate will establish a startup rate, block source range channels above P-6, and raise power to 10-8 amps. When candidate inserts control rods to stabilize power, Bank D Group 2 rods will drop, requiring a reactor trip.
Modified JPM. Normal spray and PORVs will be unavailable. Candidate will be required to use Aux Spray New JPM. Candidate will be required to cooldown to target temperature during an SGTR, but must use alternate method (ADVs), for cooldown.
New JPM. PRT pressure reduction will not be effective when candidate attempts to spray. Candidate will be required to vent PRT to restore parameters within limits.
New JPM. Candidate will restore channel to service. Existing JPM only removes from service NRCJPMOUTRevO.doc
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility:
Indian Point 2 Date of Examination:
3/10/2003 Exam Level:
SROU Operating Test No.:
1 B.1: Control Room Systems System JPM Description Type Safety Code*
Function Si 001 Stabilize reactor power at 1 -8 amps following N,S,A,L 1
Rod Control criticality S2 S3 010 Depressurize the RCS following a SGTR 3
Pressurizer
~,
Pressure Control S4 S5 007 Respond to PRT High Pressure N,S,A,E 5
Pressurizer Relief Tank S7 B.2 Facility Walk-Through P1 004 Align City Water Cooling to Charging pumps R,D,E 2
__CVCS P2 041 Local Operation of Atmospheric Steam Dumps D,E 4S Steam Dump P3 Type Codes:
(D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA, (E)OP/AB NOTES Si S3 s5 New JPM. Candidate will establish a startup rate, block source range channels above P-6, and rai power to 10-8 amps. When candidate inserts control rods to stabilize power, Bank D Group 2 rods will dro
, requiring a reactor trip.
Modified JPM. Normal spray and PORVs will be unavailable. Candidate will be required to e Aux Spray New JPM. PRT pressure reduction will not be effective when candidate attempts to spray Candidate will be required to vent PRT to restore parameters within limits.
II0A.1 0
IP2 NRCJPMOUTRevO.doc
Appendix D Scenario Outline Form ES-D-1 Facility:
IP2 Scenario No.:
1 Op Test No.:
1 Examiners:
Candidates:
100% power EOL 21 Charging Pump OOS 21 CCW Pump OOS Small SG Tube Leak < 25 GPD Turnover:
Reduce load to 800 MWe to remove 23 Condensate Pump frp m service within 60 minutes q
u Critical Tasks:
Manual reactor trip&-
- 0 Initiate Bleed and Feed Cooling Event Malf.
Event No.
No.
Type*
Event Description 1
R (RO)
Reduce power N (BOP)
MFRV fails closed slowly PCs8 3
XMT I (RO)
Pressurizer level channel fails high RCS20 I (BOP) 4 ATS7B C (ALL)
Feedwater Pump trip requiring rapid load decrease to 700 MWe 5
ATS7A M (ALL)
Feedwater pump trip. Reactor trip required.--
6 BAT C (RO)
Auto reactor trip failure. Manual trip required ESR. FAIL.
RX.TRIP 7
ATS5C C (BOP)
TDAFW trips 8
MDAFW fails to start AFW1 9
MOT C (BOP)
MDAFW trips AFW1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor IP2 Sim 1 ES-D-1
Scenario Event Description IP2 NRC Simulator Scenario 1 The crew assumes the shift and initiates a power reduction IAW POP-3.1. The RO will commence RCS boration and the BOP will slowly reduce generator load.
23MFRV controller fails in automatic. The controller must be placed in manual IAW AOI 28.0 and/orAOl 21.1.1, and 23 SG level restored to the normal control band. The CRS will referto Tech Specs.
Pressurizer level channel 460 (controlling channel) will fail high. The crew will respond IAW AOI-28.0 and AOI-28.7. The RO will operate charging pumps and pressurizer heaters manually while the BOP defeats the failed channel inputs and the CRS refers to Technical Specifications.
Subsequently, 22 MBFP will trip, requiring a plant runback to <745 MWe IAW AO1-21.1.1. 23 SG level must be controlled manually and normal boration will be performed for AFD control. If Rod Insertion Limits are exceeded, the RO will commence Emergency Boration.
When the plant is stabilized, 21 MBFP will trip, requiring a reactor trip. The reactor must be tripped manually IAW AOI-21.1.1, because automatic reactor trip is not functional.
Subsequent AFW failures result in the requirement to transition to FR-H.1, and restore Heat Sink using Bleed and Feed.
EOP flow path: E ES-0.1 - FR-H.1 IP2 Sim 1 ES-D-1
Appendix D Scenario Outline Form ES-D-1 Facility:
IP2 Scenario No.:
2 Op Test No.:
1 Examiners:
Candidates:
CRS I_
RO PO Initial Conditions:
100% power EOL 21 Charging Pump OOS 21 AFW Pump OOS Small SG Tube Leak < 25 GPD Turnover:
Main Condenser rupture disc is leaking. Reduce Power to 50 MWe at 200 MWe per hour and remove Main Turbine and Generator from service Critical Tasks:
Manual Turbine Trip Initiate Emergency Boration Event Malf.
Event No.
No.
Type*
Event Description 1
R (RO)
Reduce load N (BOP)
First Stage Shell Pressure PT-412B fails low MSS054A C (CRS) 3 XMT I (RO)
Steam Pressure transmitter 404 fails high SGN34 I (CRS) 4 CCW1 C (ALL)
CCW Pump Trip. Standby trips upon starting.
CCW2 CCW3 5
CVC6 C (BOP)
RCP TBHX leak. RCP vibration CCW8 RCP7A 6
RCP21 M (ALL)
RCP sheared shaft; ATWS PPL3-4 7
TCA1-6 C (RO)
Turbine Trip failure PPL4348 8
CVC9 C (BOP)
Boration failure
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor IP2 Sim 2 ES-D-1
Scenario Event Description IP2 Simulator Scenario 2 The crew will assume the shift and initiate a load decrease in accordance with POP-3.1.
First Stage Shell Pressure transmitter PT-41 2B will fail low. The crew will place steam dumps in Pressure Control Mode and trip Si steam flow bistables IAW AO1-28.0 and AO1-28.14. The CRS will refer to Technical Specifications.
When actions are complete, Steam pressure transmitter PT-404 will fail high. The crew will respond by placing Feed Pump Speed Control and steam dumps in manual IAW AO1-28.0.
A running CCW pump will trip. The standby pump will have to be manually started, and will subsequently trip. The crew will respond IAW AO1-4.1.1. Subsequently, a TBHX leak will develop, and manual action to isolate the TBHX leak will be taken IAW AO1-4. 1.2.
During the TBHX tube leak, RCP vibration will rise, eventually resulting in failure of the RCP shaft. The crew will respond using AOP-RCP-1. A reactor trip will be required, but will not automatically occur.
The RO will attempt to manually trip the reactor, but the reactor will not trip. The turbine must be manually tripped, and emergency boration will fail, requiring an alternate methpd for emergency boration.
EOP flow path: E FR-S.1 - E ES-0.1 IP2 Sim 2 ES-D-1
Appendix D Scenario Outline Form ES-D-1 Facility:
IP2 Scenario No.:
3 Op Test No.:
1 Examiners:
Candidates:
9% power BOL Plant startup in progress Turnover:
Raise power and synchronize the Main Generator Critical Tasks:
Place ECCS equipment in PTL Isolate ruptured SG Event Malf.
Event l
No.
No.
Type*
Event Description 1
R (RO)
Raise reactor power. Synchronize Main Generator N (BOP)
N (CRS) 2 XMT I (ALL)
Tcold instrument fails high RCS036A 3
RCS14C C (ALL)
Steam Generator Tube Leak 4
RCS14C M (ALL)
SGTR 5
XMT C (RO)
Atmospheric Dump valve on ruptured SG fails open SGN43 6
SWI C (BOP)
CIA fails to reset. Manual action to bypass and reset CIA PPLO30B
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor IP2 Sim 3 ES-D-1
Scenario Event Description IP2 Simulator Scenario 3 The crew will assume the shift to raise power and synchronize the Main Generator to the grid IAW POP-1.3 and SOP-26.4.
When the generator is on-line, a Tcold instrument will fail high. IAW AOI-28.0 and 28. 1, the RO will place the running Charging Pump in manual, the BOP will trip bistables, and the CRS will refer to Technical Specifications.
When the plant is stable, a steam generator tube leak will develop, requiring action IAW AOI-1.2. Leak rate is quantified, secondary systems are isolated, and the crew will begin a plant shutdown IAW POP-3. 1 based on excessive SG tube leakage. The CRS will again refer to Technical Specifications.
While the crew is shutting the plant down, the tube leak will increase in severity. The crew will determine that pressurizer level cannot be maintained, and a reactor trip will be required.
When the reactor trips, one Atmospheric Dump Valve will fail open, requiring manual action to close it to minimize the radioactive release to atmosphere. Additionally, CIA will fail to reset.
The crew must bypass and manually reset CIA to provide instrument air to containment, avoiding RCS depressurization using PORVs EOP flow path: E E ES-3.1 IP2 Sim 3 ES-D-1