ML14119A389
| ML14119A389 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/31/2014 |
| From: | Hooper G Entergy Corp |
| To: | David Silk Operations Branch I |
| Jackson D | |
| Shared Package | |
| ML1330B159 | List: |
| References | |
| TAC U01887 | |
| Download: ML14119A389 (35) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 Facility:
James A. Fitzpatrick Date of Exam:
April2014 RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
Total A2 G*
Total 1
2 3
4 5
E; 1
2 3
4
- 1.
1 4
3 3
3 4
3 20 3
4 7
Emergency 2
1 1
2 1
1 1
7 2
1 3
Plant Tier Evolutions Totals 5
4 5
4 5
4 27 5
5 10 1
3 2
2 3
2 2
1 3
3
- 3 2
26 2
3 5
- 2.
2 Plant 1
1 1
1 1
1 1
2 1
1 1
12 0
1 2
3 Systems Tier Totals 4
3 3
4 3
~~
2 5
4 4
3 38 3
5 8
- 3. Generic Knowledge & Abilities 1
2 3
4 1
2 3
4 10 7
Categories 2
3 3
2 2
2 2
1 Note
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 RO exam must total 7fi points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriat':l KIA statements.
- 4.
Select topics from as many systems and evolutions as pos*sible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIA's
- 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each cate~rory in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on "the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#)on Form ES-401-3. Limit SRO selections to KIAs that are linked to 1 OCFR55.43
ES-401 2
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
~ EAPE # 1 Name Safety Function I K1 I K2 I K3 I A1 I A2 I G I KIA Topic(s)
EA2.0:l -Ability to determine and/or interpret the following as 295030 Low Suppression X
they apply to LOW Pool Water Level/ 5 SUPPHESSION POOL WATE'R LEVEL: Reactor pressure AA2.0~!- Ability to determine and/or interpret the following as 295019 Partial or they apply to PARTIAL OR Complete Loss of X
COMPLETE LOSS OF INSTRUMENT AIR: Status of Instrument Air I 8 safety-related instrument air system loads (see AK2.1 -
AK2.1H)
AA2.0i-Ability to determine 295005 Main Turbine and/or interpret the following as Generator Trip I 3 X
they apply to MAIN TURBINE GENEHATOR TRIP:
Feedwater temperature 2.4.41 - Emergency 295021 Loss of X
Procedures/ Plan: Knowledge Shutdown Cooling I 4 of the E!mergency action level thresholds and classifications.
295023 Refueling 2.4.18 - Emergency X
Procedures I Plan: Knowledge Accidents I 8 of the specific bases for EOPs.
2.2.37 - Equipment Control:
295038 High Off-site X
Ability to determine operability Release Rate I 9 and I or availability of safety related equipment.
2.4.35-Emergency 295031 Reactor Low Procedures/ Plan: Knowledge Water Level/ 2 X
of local auxiliary operator tasks during emergency and the resultant operational effects.
AK1.02-Knowledge of the 600000 Plant Fire On operational implications of the Site /8 X
following concepts as they apply to Plant Fire On Site: Fire Fightin!;J AK1.02-Knowledge of the operational implications of the 295006 SCRAM I 1 X
following concepts as they apply to SCRAM: Shutdown mar~
limp. I Q#
3.9 76 3.7 77 2.7 78 4.6 79 4.0 80 4.6 81 4.0 82 2.9 39 3.4 40
ES-401 2
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1
~ EAPE # 1 Name Safety Function I K1 I K2 I K3 I A1 I A2 I G I KIA Topic(s)
EK1.02-Knowledge of the operational implications of the 295037 SCRAM following concepts as they Condition Present and apply to SCRAM CONDITION Reactor Power Above X
PRESENT AND REACTOR APRM Downscale or POWER ABOVE APRM Unknown I 1 DOWI\\ISCALE OR UNKNOWN:
Reactor water level effects on reactor power AK2.0~~- Knowledge of the interrelations between 295016 Control Room X
CONTROL ROOM Abandonment I 7 ABANDONMENT and the following: Local control stations: Plant-Specific AK2.ml-Knowledge of the 295021 Loss of interrelations between LOSS Shutdown Cooling I 4 X
OF SHUTDOWN COOLING and the following:
RHRishutdown cooling EK2.1 fi - Knowledge of the 295031 Reactor Low interrelations between Water Level I 2 X
REACTOR LOW WATER LEVEL and the following: A. C.
distribution: Plant-Specific EK3.01 -Knowledge of the reasons for the following 295028 High Drywell X
responses as they apply to Temperature I 5 HIGH DRYWELL TEMPERATURE: Emergency depressurization AK3.0~1 - Knowledge of the reasons for the following 295003 Partial or X
responses as they apply to Complete Loss of AC I 6 PARTIAL OR COMPLETE LOSS OF A.C. POWER: Load shedding EK3.01 - Knowledge of the reasons for the following 295024 High Drywell X
responses as they apply to Pressure I 5 HIGH DRYWELL PRESSURE:
Drywell spray operation: Mark-1&11 EA 1. oe; -Ability to operate and/or monitor the following as 295030 Low Suppression X
they apply to LOW Pool Water Level I 5 SUPPRESSION POOL WATER LEVEL: HPCI limp. I Q#
4.1 41 4.0 42 3.6 43 3.2 44 3.6 45 3.5 46 3.6 47 3.5 48
ES-401 2
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1
~ EAPE # 1 Name Safety Function I K1 I K2 I K3 \\ A1 I A2 I G KIA Topic(s)
EA1.0E>
Ability to operate and/or monitor the following as 295038 High Off-Site X
they apply to HIGH OFF-SITE Release Rate I 9 RELEASE RATE: Plant ventilation EA 1.0?- Ability to operate and/or monitor the following as 295025 High Reactor X
they apply to HIGH REACTOR Pressure I 3 PRESSURE: ARI/RPT/ATWS:
Plant-S~ecific AA2.0?- Ability to determine 295005 Main Turbine and/or interpret the following as X
they apply to MAIN TURBINE Generator Trip I 3 GENEHATOR TRIP: Reactor water l,evel AA2.0'1 -Ability to determine 295019 Partial or and/or interpret the following as they apply to PARTIAL OR Complete Loss of X
COMPLETE LOSS OF Instrument Air I 8 INSTRUMENT AIR: Instrument air system _gressure AA2.ml -Ability to determine and/or interpret the following as 295001 Partial or they apply to PARTIAL OR Complete Loss of Forced X
COMPLETE LOSS OF Core Flow Circulation I 1 FORCED CORE FLOW
&4 CIRCULATION: Actual core flow 700000 Generator 2.2.12-Equipment Control:
Voltage and Electric Grid X
Knowledge of surveillance Disturbances
_Qrocedures.
295018 Partial or 2.1.32 Conduct of Complete Loss of X
Operations: Ability to explain Component Cooling and apply system limits and Water I 8 precautions.
2.2.44 - Equipment Control:
Ability to interpret control room 295023 Refueling indications to verify the status X
and operation of a system, and Accidents I 8 understand how operator actions and directives affect
_giant and ~stem conditions.
EA2.02-Ability to determine 295026 Suppression and/or interpret the following as they apply to SUPPRESSION Pool High Water X
POOL HIGH WATER Temperature I 5 TEMPERATURE: Suppression
_gool level 295004 Partial or X
AK1.0Ei-Knowledge of the 3.5 49 4.1 50 3.5 51 3.5 52 3.3 53 3.7 54 3.8 55 4.2 56 3.8 57 3.3 58
ES-401 2
JAF 14-1 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE # I Name Safety Function KIA Topic(s)
\\Imp.\\ Q#
Complete Loss of D.C.
operational implications of the Power/6 following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C.
POWER: Loss of breaker protection KIA Category Totals:
4 3
3 3
4/3 3/4 Group Point Total:
1 20/7
ES-401 3
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 II EAPE #I Name Safety Function I K1 I K2 I K3 I A 11 I A2 I G KIA Topic(s)
AA2.0!5 -Ability to determine 2950201nadvertent and/or interpret the following as Containment Isolation I 5 X
they apply to INADVERTENT
&7 CONTAINMENT ISOLATION:
Reactor water level 2.4.45 - Emergency 295022 Loss of CRD Procedures I Plan: Ability to Pumps I 1 X
prioritize and interpret the significance of each annunt:iator or alarm.
AA2.02-Ability to determine 295015 Incomplete X
and/or interpret the following as SCRAM I 1 they apply to INCOMPLETE SCRAM: Control rod ~osition AK1.0:3-Knowledge of the operational implications of the 295010 High Drywell X
following concepts as they Pressure I 5 apply to HIGH DRYWELL PRESSURE: Temperature increases EK2.0:3-Knowledge of the 500000 High interreiations between HIGH CONTAINMENT HYDROGEN Containment Hydrogen X
CONCENTRATIONS the Concentration I 5 following: Containment Atmosphere Control System AK3.0'1 - Knowledge of the reasons for the following 295002 Loss of Main X
responses as they apply to Condenser Vacuum I 3 LOSS OF MAIN CONDENSER VACUUM: Reactor SCRAM:
Plant-Specific AA 1.04-Ability to operate 295007 High Reactor and/or monitor the following as Pressure I 3 X
they apply to HIGH REACTOR PRESSURE: Safety/relief valve operation:
Plant-S~>_ecific EA2.0'1 -Ability to determine 295036 Secondary and/or interpret the following as Containment High they apply to SECONDARY Sump/Area Water Level I X
CONTAINMENT HIGH SUMP/AREA WATER LEVEL:
5 Operability of components within the affected area 2.4.45 - Emergency 295032 High Secondary Proceaures I Plan: Ability to Containment Area X
prioritize and interpret the Temperature I 5 significance of each annunciator or alarm.
limp. I Q# ~
3.6 83 4.3 84 4.2 85 3.2 59 3.3 60 3.7 61 3.9 62 3.0 63 4.1 64
ES-401 3
JAF 14-1 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 EAPE #I Name Safety Function KIA Topic(s) limp. I Q# ~
EK3.0:2-Knowledge of the reasons for the following 295034 Secondary responses as they apply to Containment Ventilation X
SECONDARY CONTAINMENT 4.1 65 High Radiation I 9 VENTILATION HIGH RADIATION: Starting SBGT/FRVS: Plant-Specific KIA Category Totals:
1 1
2 1
1/
1/
Group Point Total:
1 7/3 2
1
ES-401 System #I Name K
K K
1 2
3 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 218000 ADS 206000 HPCI 215003 IRM 4
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4 I
.A2.11 -Ability to (a) predict the impacts of the
- following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR X
STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Standby liquid initiation A2.02 -Ability to (a) predict the impacts of the l'ollowing on the I~ELIEF/SAFETY
\\1 ALVES ; and (b) based X
on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or o~erations: Leak~ SRV 2.4.3 - Emergency X
l=>rocedures I Plan: Ability to identify post-accident instrumentation.
2.4.4 - Emergency Procedures I Plan: Ability to recognize abnormal indications for system X
operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
2.1.31 -Conduct of Operations: Ability to locate control room X
switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
Imp.
Q#
3.9 86 3.2 87 3.9 88 4.7 89 4.3 90
ES-401 System # I Name K
K K
1 2
3 262001 AC Electrical X
Distribution 223002 PCIS/Nuclear X
Steam Supply Shutoff 203000 RHR/LPCI:
Injection Mode X
212000 RPS X
215004 Source Range X
Monitor 259002 Reactor Water X
Level Control 4
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
~I A2 I*IGI 4
5 6
1<1.03-Knowledge of the physical connections and/or cause-effect t*elationships between A.C. ELECTRICAL DISTRIBUTION and the following: Off-site power sources 1<1.19 - Knowledge of the physical connections and/or cause-effect relationships between I=>RIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the following:
Component cooling water systems 1<2.02 - Knowledge of t:!lectrical power supplies to the following: Valves 1<2.01 -Knowledge of t:!lectrical power supplies to the following: RPS motor-generator sets 1<3.02-Knowledge of the t:!ffect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM)
SYSTEM will have on following: Reactor manual control: Plant-Specific 1<3.05-Knowledge of the effect that a loss or malfunction of the H.EACTOR WATER LEVEL CONTROL SYSTEM will have on following: Recirculation flow control system limp I Q# I 3.4 1
2.7 2
2.5 3
3.2 4
3.4 5
2.8 6
ES-401 System #I Name K K K 1
2 3
261000 SGTS 264000 EDGs 263000 DC Electrical Distribution 218000 ADS 400000 Component Cooling Water 211000 SLC 4
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K K K
~I A2 1*1 G
4 5
6 K4.01 -Knowledge of STANDBY GAS TREATMENT SYSTEM X
design feature(s) and/or rnterlocks which provide
- for the following:
Automatic system initiation IK4.02-Knowledge of I::MERGENCY GENERATORS (DIESEL/JET) design X
feature(s) and/or interlocks which provide for the following:
i=:mergency generator trips (emergency/LOCA) 1<5.01 -Knowledge of the operational implications of the following concepts as X
they apply to D.C.
I::LECTRICAL DISTRIBUTION:
Hydrogen generation during battery charging.
1<5.01 -Knowledge of the operational implications of the following concepts as X
they apply to AUTOMATIC DEPRESSURIZATION SYSTEM: ADS logic operation 1<6.05 - Knowledge of the E~ffect that a loss or X
malfunction of the following will have on the CCWS: Motors 1<6.03-Knowledge of the effect that a loss or malfunction of the X
following will have on the STANDBY LIQUID CONTROL SYSTEM:
A.C. power 3.7 7
4.0 8
2.6 9
3.8 10 2.8 11 3.2 12
ES-401 System #I Name K
K K
1 2
3 262002 UPS (AC/DC) 239002 SRVs 209001 LPCS 206000 HPCI 4
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
~I A2 I*IGT 4
5 6
1<4.01 -Knowledge of UNINTERRUPTABLE i=>OWER SUPPLY X
(A.C./D.C.) design feature(s) and/or interlocks which provide for the following: Transfer from preferred power to alternate _Qower supplies A1.09-Ability to predict and/or monitor changes in parameters associated with operating the X
I~ELIEF/SAFETY VALVES controls including: Indicated vs.
actual steam flow: Plant-Specific A2.08-Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those X
predictions, use procedures to correct, Gontrol, or mitigate the Gonsequences of those abnormal conditions or operations: Valve openings
~~.17 -Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: HPCI inadvertent initiation:
BWR-2,3,4 limp I Q# I 3.1 13 3.1 14 3.1 15 3.9 16
ES-401 System #I Name K K K 1
2 3
205000 Shutdown Cooling 215005 APRM I LPRM 300000 Instrument Air 215003 IRM 217000 RCIC 205000 Shutdown Cooling 263000 DC Electrical Distribution 4
Form ES-401-1 JAF '14-1 NRC Exam Written Examination Outlint3 Plant Systems -Tier 2 Group 1 K K K
~I A2 I*IGl 4
5 6
/\\3.03 -Ability to monitor automatic operations of the SHUTDOWN X
COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including: Lights and alarms
/\\3.02 -Ability to monitor automatic operations of the AVERAGE POWER RANGE X
MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: Full core dis olav
/\\4.01 -Ability to manually X
operate and/or monitor in the control room:
Pressure qauqes
/\\4.06 -Ability to manually X
operate and/or monitor in the control room: Detector drives 2.4.20 - Emergency Procedures I Plan:
X Knowledge of operational implications of EOP warnings, cautions, and notes.
- ~. 1. 7 - Conduct of Operations: Ability to evaluate plant performance and make X
operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
A3.01 -Ability to monitor automatic operations of the D.C. ELECTRICAL X
DISTRIBUTION including:
Meters, dials, recorders, alarms, and indicating lights limp I a*!
3.5 17 3.5 18 2.6 19 3.0 20 3.8 21 4.4 22 3.2 23
ES-401 System #I Name K
K K
1 2
3 206000 HPCI X
218000 ADS 212000 RPS KIA Category Totals:
3 2 2 4
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outlin,e Plant Systems -Tier 2 Group 1 K
K K
~I A2 1*1 G 4
5 6
1<1.01 -Knowledge of the physical connections and/or cause-effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following: Reactor vessel:
13WR-2,3,4 A2.04 -Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based X
on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: ADS failure to initiate A4.09-Ability to manually X
operate and/or monitor in the control room: SCRAM instrument volume level 3 2 2 1 3/
3 3 2/
Group Point Total:
2 3
3.8 24 4.1 25 3.9 26 I
26/5
ES-401 System # I Name K K K
1 2
3 290001 Secondary Containment 202001 Recirculation 201003 Control Rod and Drive Mechanism 259001 Reactor X
Hydraulic 223001 Primary Containment and X
Auxiliaries 5
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
~I A2 1*1 G L 4
5 6
/\\2.04 -Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High airborne radiation
- ~.4.6-Emergency X
Procedures I Plan:
Knowledge of EOP mitigation strategies.
- ~.4.8 - Emergency Procedures I Plan:
X Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
K1.06-Knowledge of the physical connections and/or cause-effect relationships between REACTOR FEEDWATER SYSTEM and the following: Plant air systems 1<2.03-Knowledge of E~lectrical power supplies to the following: Backup SCRAM valve solenoids 1<3.03-Knowledge of the E~ffect that a loss or malfunction of the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES will have on following:
Containment/drywell pressure: Plant-Specific limp I Q# I 3.7 91 4.7 92 4.5 93 2.9 27 3.5 28 3.4 29
ES-401 System #I Name K
K 1
2 215001 Traversing In-core Probe 245000 Main Turbine Generator and Auxiliary Systems 239003 MSIV Leakage Control 226001 RHR/LPCI:
Containment Spray Mode 201006 RWM 5
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
K ~I., I*IGI 3
4 5
6 IK4.01 -Knowledge of TRAVERSING IN-CORE IDROBE design feature(s)
X and/or interlocks which provide for the following:
FJrimary containment isolation: Mark-I&II(Not-13WR1) 1<5.06-Knowledge of the operational implications of the following concepts X
as they apply to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: Turbine shaft sealing 1<6.02-Knowledge of the effect that a loss or malfunction of the following will have on the X
IVISIV LEAKAGE CONTROL SYSTEM:
Standby gas treatment system: BWR-4,5,6(P-Spec)
A 1.10 -Ability to predict and/or monitor changes in parameters associated with operating the X
HHR/LPCI:
CONTAINMENT SPRAY SYSTEM MODE controls including: Emergency
~lenerator loading_
A2.03 -Ability to (a) predict the impacts of the following on the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC); and (b)
X based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod drift: P-Spec(Not-BWR6) limp I Q# I 3.4 30 2.5 31 2.8 32 3.0 33 3.0 34
ES-401 System #I Name K
K K
1 2
3 204000 RWCU 233000 Fuel Pool Cooling/Cleanup 216000 Nuclear Boiler Instrumentation 201003 Control Rod and Drive Mechanism KIA Category Totals:
1 1 1 5
Form ES-401-1 JAF 14-1 NRC Exam Written Examination Outlin,e Plant Systems - Tier 2 Group 2 K
K K
~I A2 I*IGr 4
5 6
A3.05 -Ability to monitor automatic operations of X
the REACTOR WATER CLEANUP SYSTEM including: Reactor water tem~erature A4.11 - Ability to manually operate and/or X
monitor in the control room: Closed cooling water tem~erature 2.1.32 -Ability to explain X
and apply system limits and precautions.
A2.06 -Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of CRD cooling water flow 1 1 1 1 2/
1 1 1/
Group Point Total:
1 2
limp I Q# I 2.8 35 2.5 36 3.8 37 3.0 38 1 12/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
James A. Fitzpatrick Date:
April 2014 Category KIA#
Topic RO SRO-Only IR Q#
IR Q#
2.1.35 Knowledge of the fuel-handling 3.9 94 responsibilities of SROs.
2.1.39 Knowledge of conservative decision making 4.3 98 practices.
- 1.
Knowledge of criteria or conditions that Conduct 2.1.14 require plant-wide announcements, such as 3.1 66 of Operations pump starts, reactor tri~s, mode Ghanges, etc.
Ability to use procedures related to shift 2.1.5 staffing, such as minimum crew complement, 2.9 67 overtime limitations, etc.
Subtotal 2
2 2.2.23 Ability to track Technical Specification limiting 4.6 95 conditions for operations.
Knowledge of the process for mana~Jing 2.2.18 maintenance activities during shutdown I 3.9 100 operations, such as risk assessments, work I
prioritization, etG.
i I
- 2.
Ability to manipulate the console controls as Equipment 2.2.2 required to operate the facility betwe!en 4.6 68 Control shutdown and designated power levels.
Ability to perform pre-startup proGedures for 2.2.1 the facility, including operating those* controls 4.5 69 associated with plant equipment that could affect reactivity.
2.2.22 Knowledge of limiting conditions for 4.0 74 operations and safety limits.
Subtotal 3
2 Ability to use radiation monitoring systems, 2.3.5 such as fixed radiation monitors and alarms, 2.9 96 portable survey instruments, personnel monitoring equipment, etc.
- 3.
Knowledge of radiation monitoring systems, Radiation such as fixed radiation monitors and alarms, Control 2.3.15 portable survey instruments, personnel 3.1 99 monitoring equipment, etc.
Knowledge of radiological safety principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 70 responsibilities, access to locked hi~lh-radiation areas, aligning filters, etc.
Knowledge of radiation or contamination 2.3.14 hazards that may arise during normal, 3.4 71 abnormal, or emergency conditions or activities.
2.3.4 Knowledge of radiation exposure limits under 3.2 75 normal or emergenc~ conditions.
Subtotal 3
2 2.4.29 Knowledge of the emergency plan.
4.4 97
- 4.
Emergency 2.4.28 Knowledge of procedures relating to a 3.2 72 Procedures I security event (non-safeguards information).
Plan 2.4.1 Knowledge of EOP entry conditions and immediate action ste~s.
4.6 73 Subtotal 2
1 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Selected KIA Reason for Rejection Group The ~ng t~
ltOAs we~*xcluded from ~t~tie andnrridtfn "'
..,.~~
295027 High Containment This topic applies to plants with Mark Ill 1 /1 Temperature containments only. The facility has a Mark I containment.
295011 High Containment This topic applies to plants with Mark Ill 1 /2 Temperature containments only. The facility has a Mark I containment.
207000 Isolation (Emergency)
This system is not installed at the facility.
2/1 Condenser 209002 HPCS This system is not installed at the facility.
2/1 201004 RSCS This system is no longer installed at the facility.
2/2 201005 RCIS This system is* not installed at the facility.
2/2 2.2.3 Knowledge of the design, This KIA applies to multi-unit facilities only.
G procedural, and operational differences between units.
2.2.4 Ability to explain the This KIA appli,es to multi-unit facilities only.
variations in control board/control room layouts, G
systems, instrumentation, and procedural actions between units at a facility.
Question 48 HPCS is not installed at the facility.
295030 Low Suppression Pool Randomly re-:sampled 295030 Low Water Level Suppression Pool Water Level EA 1.05 -Ability EA 1.03 -Ability to operate to operate and/or monitor the following as they 1 /1 and/or monitor the following as apply to LOW SUPPRESSION POOL WATER they apply to LOW LEVEL: HPCI.
SUPPRESSION POOL WATER LEVEL: HPCS: Plant-Specific Question 50 RRCS is not installed at the facility.
295025 High Reactor Pressure EA 1.08 -Ability to operate Randomly re-sampled 295025 High Reactor 1 /1 and/or monitor the following as Pressure EA 1.07 -Ability to operate and/or they apply to HIGH REACTOR monitor the following as they apply to HIGH PRESSURE: RRCS: Plant-REACTOR PHESSURE: ARI/RPT/ATWS:
Specific Plant-Specific.
Question 52 Randomly seh:!cted KIA is identical to the KIA 295019 Partial or Complete for Question 77. Re-sampling this KIA to limit Loss of Instrument Air overlap.
AA2.02 -Ability to determine and/or interpret the following as Randomly re-sampled 295019 Partial or 1 /1 they apply to PARTIAL OR Complete Loss of Instrument Air M2.01 -
COMPLETE LOSS OF Ability to determine and/or interpret the INSTRUMENT AIR: Status of following as they apply to PARTIAL OR safety-related instrument air COMPLETE LOSS OF INSTRUMENT AIR:
system loads (see AK2.1 -
Instrument air system pressure.
AK2.19)
Question 62 Isolation Condensers are not installed at the 295007 High Reactor Pressure facility.
M 1.01 -Ability to operate 1 /2 and/or monitor the following as Randomly re-sampled 295007 High Reactor they apply to HIGH REACTOR Pressure M 1. 04 - Ability to operate and/or PRESSURE: Isolation monitor the following as they apply to HIGH condenser: Plant-Specific REACTOR PRESSURE: Safety/relief valve operation: Pla,.nt-Specific.
Question 2 High pressure core spray (HPCS) is not 223002 PCIS/Nuclear Steam installed at th1:! facility.
Supply Shutoff K1.15 - Knowledge of the Randomly re-:sampled 223002 PCIS/Nuclear physical connections and/or Steam Supply Shutoff K1.19 - Knowledge of the 2 I 1 cause-effect relationships physical connections and/or cause-effect between PRIMARY relationships between PRIMARY CONTAINMENT ISOLATION CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SYSTEM/NUCLEAR STEAM SUPPLY SHUT-SUPPLY SHUT-OFF and the OFF and the following: Component cooling following: High pressure core water systems.
spray: Plant-Specific Question 5 Rod control and information system (RCIS) is 215004 Source Range Monitor not installed at the facility.
K3.03-Knowledge of the effect that a loss or malfunction of the Randomly re-sampled 215004 Source Range 2 I 1 SOURCE RANGE MONITOR Monitor K3.02-Knowledge of the effect that a (SRM) SYSTEM will have on loss or malfunction of the SOURCE RANGE following: Rod control and MONITOR (SRM) SYSTEM will have on information system: Plant-following: Reactor manual control: Plant-Specific Specific.
Question 94 Randomly seh:!cted KIA is identical to the KIA 2.1.14-Knowledge of criteria or for Question 66. Re-sampling this KIA to limit conditions that require plant-overlap.
G wide announcements, such as pump starts, reactor trips, mode changes, etc.
Randomly re-sampled 2.1.19 - Ability to use plant computers to evaluate system or component status.
Question 68 Randomly selected KIA is identical to the KIA 2.2.23 -Ability to track for Question 95. Re-sampling this KIA to limit Technical Specification limiting overlap.
conditions for operations.
G Randomly re-sampled 2.2.2 -Ability to manipulate the! console controls as required to operate the facility between shutdown and designated power levels.
Question 27 There is no direct connection or relationship 259001 Reactor Feedwater between the Reactor Feedwater and RHR systems.
K1.15 - Knowledge of the physical connections and/or 2/2 cause-effect relationships Randomly re-sampled 259001 Reactor between REACTOR Feedwater K1.06-Knowledge of the physical FEEDWATER SYSTEM and the connections a1nd/or cause-effect relationships following: RHR: Plant-Specific between REACTOR FEEDWATER SYSTEM and the following: Plant air systems Question 37 There is no less than one hour technical 216000 Nuclear Boiler specification related to Nuclear Boiler Instrumentation lnstrumentatiC>n.
2/2 2.2.39-Equipment Control:
Knowledge of less than one Randomly re-:sampled 216000 Nuclear Boiler hour technical specification Instrumentation 2.1.32-Ability to explain and action statements for systems.
apply system limits and precautions.
Question 46 A discriminating question at the appropriate 295003 Partial or Complete license level was unable to be developed with the plant reference material and the randomly Loss of AC selected KIA.
AK3.04-Knowledge of the 1 I 1 reasons for the following responses as they apply to Randomly re-sampled 295003 Partial or PARTIAL OR COMPLETE Complete Loss of AC AK3.03-Knowledge of LOSS OF A.C. POWER:
the reasons for the following responses as they Ground isolation apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Load shedding.
Question 67 This KIA is tested extensively during the
- 2. 1.17 - Ability to make operating portion of the examination. A discriminating question was unable to be accurate, clear and concise developed without significant overlap with the verbal reports.
operating examination.
3 Randomly re-sampled 2.1.5 -Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
Question 72 This generic I<! A is also tested on Question 64, 2.4.45 -Ability to prioritize and Question 84, and the operating portion of the examination. A discriminating question was interpret the significance of unable to be developed without significant each annunciator or alarm.
overlap with these other areas.
3 Randomly re-sampled 2.4.28 - Knowledge of procedures relating to a security event (non-safeguards information).
Question 92 This system dices not have a significant impact 201006 RWM on EOP mitigation strategies. This system is also tested on Question 34, Question 69, and 2.4.6-Emergency Procedures I September 2012 NRC Question 23. A valid Plan: Knowledge of EOP question was unable to be developed without 2/2 mitigation strategies.
significant overlap with these other areas.
Randomly re-:sampled new system 202001 Recirculation.
Question 94 This generic ~'JA is tested extensively during 2.1.19 the operating portion of the exam and does not lend itself to construction of an adequate SRO-Ability to use plant computers to level question.
evaluate system or component 3
status.
Randomly re-sampled 2.1.5-Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
Question 13 The facility has replaced motor generators with 262002 UPS (AC/DC) static inverters.
A 1.02-Ability to predict and/or 2/1 monitor changes in parameters Randomly re-sampled 262002 UPS (AC/DC) associated with operating the K4.01 - Knowlt~dge of UNINTERRUPTABLE UNINTERRUPTABLE POWER POWER SUPPLY (A C./D.C.) design feature(s)
SUPPLY (A.C./D.C.) controls and/or interlocks which provide for the including: Motor generator following: Transfer from preferred power to outputs alternate power supplies.
Question 29 Since the facility does not have Hydrgen Recombiners, a discriminating question was 223001 Primary Containment unable to be developed with the randomly and Auxiliaries selected KIA K3.04-Knowledge of the effect Randomly re-sampled 223001 Primary that a loss or malfunction of the Containment and Auxiliaries K3.03-Knowledge 2/2 PRIMARY CONTAINMENT of the effect that a loss or malfunction of the SYSTEM AND AUXILIARIES PRIMARY CONTAINMENT SYSTEM AND will have on following:
AUXILIARIES will have on following:
Containment/drywell hydrogen Containment/drywell pressure: Plant-Specific.
gas concentration Question 39 Unable to develop a valid question at the 600000 Plant Fire On Site license level for the randomly selected KIA.
Randomly re-sampled 600000 Plant Fire On AK 1. 01 - Knowledge of the Site AK1.02-Knowledge of the operational 1 /1 operational implications of the implications of the following concepts as they following concepts as they apply to Plant Fire On Site: Fire Fighting.
apply to Plant Fire On Site: Fire Classifications by type Question 94 The randomly selected KIA overlaps with the 2.1.5-Ability to use procedures KIA for question 67.
related to shift staffing, such as Randomly re-sampled 2.1.35-Knowledge of 3
minimum crew complement, the fuel-handling responsibilities of SROs.
overtime limitations, etc.
Question 47 The facility do,es not have an Auxiliary Building 295024 High Drywell Pressure that isolates on high Drywell pressure.
Randomly re-sampled KIA 295024 High Drywell EK3.09-Knowledge of the Pressure EK3. 01 - Knowledge of the reasons reasons for the following for the following responses as they apply to 1 /1 responses as they apply to HIGH DRYWELL PRESSURE: Drywell spray HIGH DRYWELL PRESSURE:
operation: Mark-1&11.
Auxiliary building isolation:
Plant-Specific
Question 55 An acceptabiH question could not be developed 295018 Partial or Complete for the given transient that tested ability to Loss of Component Cooling utilize control room reference material.
Water Randomly re-selected KIA 295018 Partial or 2.4.47 - Emergency Procedures Complete Loss of Component Cooling Water 1 /1 2.1.32-Conduct of Operations: Ability to I Plan: Ability to diagnose and explain and apply system limits and recognize trends in an accurate precautions.
and timely manner utilizing the appropriate control room reference material.
Question 87 An acceptable~ SRO level question could not be 239002 SRVs developed for the randomly selected KIA.
A2.05-Ability to (a) predict the Randomly re-selected KIA 239002 SRVs A2.02
-Ability to (a) predict the impacts of the impacts of the following on the following on the RELIEF/SAFETY VALVES; RELIEF/SAFETY VALVES; and and (b) based on those predictions, use 2/1 (b) based on those predictions, procedures to correct, control, or mitigate the use procedures to correct, consequences of those abnormal conditions or control, or mitigate the operations: Le\\aky SRV.
consequences of those abnormal conditions or operations: Low reactor pressure Question 74 An acceptable RO level question could not be 2.2.15 -Ability to determine the developed for the randomly selected KIA.
expected plant configuration Randomly re-selected KIA 2.2.22-Knowledge 3
using design and configuration of limiting conditions for operations and safety control documentation, such as limits.
drawings, line-ups, tag-outs, etc.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: James A. FitzQatrick Date of Examination: AQril 2014 Examination Level: RO Operating Test Number: 14-1 Administrative Topic Type I
Describe activity to be performed (see Note)
Code*
Core Thermal Heal Balance Verification Using Turbine Conduct of Operations M,R Steam Pressure KIA 2.1.19 (3.9), OP-65, RAP-7.3.03 Perform RHR Lineup Verification Conduct of Operations N,S KIA 2.1.31 (4.6), ST-2AN Explain RPS Operation Using Electrical Drawings Equipment Control D,R KIA2.2.41 (3.5), 1.67-99,1.67-101
, Determine Release Rates Radiation Control M,R KIA 2.3.11 (3.8), ISP-27-2
- i*'"**
- t*
Emergency*Proc~~
,i~v
,/r/"
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; ::; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (<::: 1)
(P)revious 2 exams (S 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: James A Fitz12atrick Date of Examination: A12ril 2014 Examination Level: SRO Operating Test Number: 14-1 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Core Thermal Heat Balance Verification Using Turbine Conduct of Operations M,R Steam Pressure KIA 2.1.19 (3.8), OP-65, RAP-7.3.3 Determine Reportability Requirements-Scram with Conduct of Operations N,R HPCI and RCIC Injection KIA2.1.18 (3.8}, NUREG 1022, EN-LI-108 I Explain RPS Operation Using Electrical Drawings,
' Determine Technical Specification Impact of Failed Equipment Control D,R Component KIA 2.2.41 (3.9), 1.67-99, 1.67-101 Determine Release Rates and ODCM Actions Radiation Control D,R I I I KIA 2.3.11 (4.3), ISP-27-2, ODCM Determine Emergency Classification and Initiate Event Emergency Procedures/Plan M,R Notification KIA 2.4.40 (4.5), IAP-2, IAP-1 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank(::=; 3 for ROs; =~ 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams(::=; 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: James A. Fitzpatrick Date of Examination: April 2014 Exam Level: RO/SR0-1 Operating Test No.: 14-1 Control Room Systems (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function
7 KIA 212000 A4.14 (3.8/3.8), AOP-1 2012-1 NRC
- b. Initiate RCIC in Pressure Control Mode with Speed Failure P, D, A, EN, L, S 4
KIA217000A4.01 (3.7/3.7}, OP-19 2012-2 NRC
KIA 201001 A2.07 (3.2/3.1 ), EP-3, OP-25
- d. Feedwater Pump Restoration Following High Level Trip N, L, S 2
KIA 259001 A4.02 (3.9/3.7), OP-2A
- e. Perform Area Radiation Monitor Functional Test D,S 9
KIA 272000 A4.02 (3.0/3.0}, OP-32
- f. Initiate Alternate Containment Spray from RHRSW KIA226001 A4.08 (3.2/3.1), EP-14 D,A,S 5
- g. Transfer Bus 10100 from Reserve to Normal Using Single Meter Voltage Match Method D,A,S 6
KIA 262001 A4.04 (3.6/3.7}, OP-46A
D,S 8
KIA 400000 A4.01 (3.1/3.0}, EP-12 In-Plant Systems (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)
- i. Startup Main Steam Leakage Collection System KIA 239003 A4.01 (3.2/3.2}, AOP-40 D, E 9
- j. Perform In-Plant Actions for Station Blackout N,R,E 6
KIA 295003 AA1.04 (3.6/3.7}, AOP-49
All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant
~11~11~1 (EN)gineered safety feature
- I - I
~1 (control room system)
(L)ow-Power I Shutdown
~11~11~1 (N)ew or (M)odified from bank including 1 (A)
~21~21~1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)
(R)CA
~11~11~1 (S)imulator
Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 14-1 Examiners:
Operators:
Initial Conditions: Reactor power is approximately 85% during a power reduction. Service Water Pump B is out of service for maintenance. SRV J is inoperable. L44 is cross-connected to L43.
Turnover: Restore L44 to the normal power source. Then continue power reduction to 75% with Recirculation flow.
Event Malf.
Event 1:vent No.
No.
Type*
Dencrietion N-Restore L44 to Normal Power Source 1
N/A
N/A
Remote C-SRO HPCI Aux Oil Pump Power Supply Loss HP15 ARP 09-3-3-38, Technical Specifications ED21 C-L-16 Electrical Fault and Drywelll Cooling Fan 4A Fails to Auto-Start 4
- BOP, Override SRO ARP 09-8-3-29, Technical Specifications FW05:B Feedwater Pump B High Vibration and Pump Trip 5
C-All FW01:B ARP 09-6-4-18, AOP-41, AOP-*8 FW05:A Feedwater Pump A High Vibra':ion and Pump Trip 6
C-All FW01:A ARP-09-6*-4-31, AOP-1, EOP-2 7
RR15:A M-All Coolant Leak in Drywell EOP-2, EOP-4 C-RHR Pumps Fail to Automatically Start 8
RH14
C-Trip of All Condensate Pumps 9
(A-C)
{C}om~onent, {M@.lQr
Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 14-*1
- 1. Total malfunctions (5-8) 7 Events 3, 4, 5, 6, 7, 8, 9
- 2. Malfunctions after EOP entry (1-2) 2 Events 8, 9
- 3. Abnormal events (2-4) 3 Events 4, 5, 6
- 4. Major transients (1-2) 1 Event7
- 6. EOP contingencies requiring substantive actions (0-2) 2 EOP-2 Alternate Level Control Leg EOP-2 Emergency Depressurization Leg
- 7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:
CT-1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4.
CT-2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization before Reactor water level lowers below -19", in accordance with EOP-2.
Appendix D Scenario Outline Form ES-D-1 Facility: James A Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 14-1 Examiners:
Operators:
Initial Conditions: Reactor power is approximately 90%. EHC pump A is out of service for maintenance.
Turnover: Perform ST-3PA, Core Spray Loop A Quarterly Operability Test. The procedure is in progress up to step 8.4.1.
I Event I Malf. I Event I Event No.
No.
T~pe*
Description N-Perform ST-3PA, Core Spray Loop A Quarterly Operability Test 1
N/A
SL04 C-SRO SLC Squib Loss of Continuity ARP 09-3-3-30, Technical Specifications C-SRV A Inadvertently Opens 3
AD06:A
- BOP, SRO AOP-36, Technical Specifications ED19:E Fault on 10700 Bus and Service Water Pump A Fails to Auto-Start 4
C-All SW15 AOP-20 C-Degraded Stator Water Coolin!~ Pump A Flow with Delayed Trip, Remote Followed by Degraded Stator Water Cooling Pump B Flow with 5
RD13 M-All Hydraulic.ATWS EOP-2, EOP-3 RD06 C-CRD Pump Trip and ATWS/RPT Failure to Actuate 7
RP03 SRO EOP-3 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Facility: James A. Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 14-1
- 1. Total malfunctions (5-8) 7 Events 2, 3, 4, 5, 6, 7, 8
- 2. Malfunctions after EOP entry (1-2) 2 Events 7, 8
- 3. Abnormal events (2-4) 3 Events 3, 4, 5
- 4. Major transients (1-2) 1 Event 6
- 7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:
CT-1: Given a failure to scram with Reactor power above 2.5%, the crew will lower Reactor power by one or more of the following methods, in accordancet with EOP-3:
Terminating and preventing all RPV injection except SLC, RCIC, and CRD, Tripping Recirculation pumps, Injecting SLC.
CT-2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3.
Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 14-1 Examiners:
Operators:
Initial Conditions: Reactor power is approximately 7% during a startup. The Rod Worth Minimizer is bypassed. IRM F is bypassed.
Turnover: Return IRM F to service per OP-16. Then continue power ascension with control rod withdrawals.
Event Malf.
Event Event I
No.
No.
Type*
Del;cription N-Return I RM F to Service 1
N/A
- BOP, SRO OP-16 R-Withdraw Control Rods 2
N/A
- ATC, SRO OP-65, OP-26 C-Stuck Control Rod 3
RD10
RR22:B 1-SRO RPS Level Transmitter Fails High ARP 09-5-2-60, Technical SpeGifications CU07 C-Reactor Water Cleanup Pump Seal Failure, Reactor Water 5
CU10
- BOP, Cleanup Fails to Automatically Isolate CU12 SRO ARP-09-3**3-2(12}, EOP-5, Technical Specifications RC06 C-RCIC Inadvertent Initiation and High Bearing Temperature 6
- BOP, Override SRO AOP-77, ARP-09-4-1-15, Technical Specifications RC09 RCIC Steam Leak and Failure to Isolate 7
RC12 M-All Remote EOP-5, AOP-1, EOP-2 RP01A 1-ATC, RPS Fails to Scram, ARI Inserts Control Rods 8
RP01B SRO AOP-1, EOP-2 C-Multiple SRVs Fail to Open 9
ADO?
{C}om~onent, {M)_§j_Qr
Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 14-1
- 1. Total malfunctions (5-8) 7 Events 3, 4, 5, 6, 7, 8, 9
- 2. Malfunctions after EOP entry (1-2) 2 Events 8, 9
- 3. Abnormal events (2-4) 3 Events 3, 5, 6
- 4. Major transients (1-2) 1 Event 7
- 7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:
CT-1: Given the plant operating at power with an un-isolable primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram, in accordance with EOP-5.
CT-2: Given an un-isolable primary system discharging into Secondary Containment and two areas exceeding Maximum Safe Temperatures, the crew will perform an emergency RPV depressurization, in accordance with EOP-5.