ML051400345
| ML051400345 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/25/2005 |
| From: | Berry P FitzPatrick |
| To: | Conte R Operations Branch I |
| Conte R | |
| References | |
| 50-333/05-301 50-333/05-301 | |
| Download: ML051400345 (36) | |
Text
~
Facility: I J.A. FitzPatrick Date of Exam: May 16 - 20,2005
- 3. Generic Knowledge and Notes: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA 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 i1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted or justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
- 4. Select topics from as many systems and evolutions as possible; 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 WAS 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 WA categories.
7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
- 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 category in the table above. 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 WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
- i EM01 2 Form ES-401-I ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier l/Group 1 (RO I SRO)
WAPE # I Name I Safety Function KIA Toplc(8) IR #
295001 Partial or Complete Loss of Forced AA1.07 Core Flow Circulation I 1 & 4 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : 3. I 8
+ Nudear Boiler InstrumentationSystem 295003 Partial or Complete Loss of AC / 6 62.1.7 Ability to evaluate plant performanceand make operational judgments based on 3.7 14 operating characteristics/ reactor behavior / and instrument interpretation.
G2.1.8 (ldc/R 55.43.5 SRO Only)- 3.6 47 AbiMy to wodihati?pemnnel artivitie outsiide the mnttvl mom.
295004 Partial or Total Loss of DC Pwr I 6 AK2.03 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C.
POWER and the following: 3.3 11
+ D.C. bus loads AA202 (1OCICR 55.43.2 SRO Only)-
Ability to determine anuor inti?pn?tthe following as they apply to PARTZAL OR 3.9 33 COMPLETE LOSS OF D.C. POWER:
+ Extent of pattial or mmplete loss of 0.C power 295005 Main Turbine Generator Trip / 3 AK1.03 Knowledge of the operational implications of the following concepts as they 3.5 45 apply to MAIN TURBINE GENERATOR TRIP:
+ Pressure effects on reactor level G2.2.22 (10CFR 55.43.2 SRO Only) - 4.1 31 Knowldw of limiting mnaitims for opxations and saMy fimits.
SRO only K/AS shown in its//cr 1/25/2005 - 8:44:58 AM Page 2
2 I I
ES-401 2 F o E S~ - d l - 1 1 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions-Tier 1lGroup 1 (RO I SRO)
Form ES401-1 I ElAPE C I Name I Safety Function KIA Topic(8)
AK2.01 Knowledge of the interrelations between SCRAM and the following:
+ RPS 4-3 I 38 62.4.29 (IOCFR 55.43.5 SRO on/yl Knowledge of tiie emergency plan.
62.1.30 Ability to locate and operate components / includiw local controls.
AK2.01 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:
+ System loads AA2.05 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:
+ System pressure AA1.04 Abilw to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
+ Service air isolation valves: Plant-Specific 295021 Loss of Shutdown Cooling / 4 AA1.06 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:
I + Containment / drywell temperature
~~
SRO only K/As shown in itaiics 1/25/2005 - 8:27:31AM Page 3
( i I ES401 2 Form ES-41-1 ES-401 BWR Examination Outline Form ES-401-I Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO I SRO)
K A
&APE # / Name / Safety Function KIA Topic@) IR #
3 1 295023 Refueling Acc Cooling Mode / 8 1 AK3.02 Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS: 3.4 12
+ Interlocks associated with fuel handlinq eauiment 295024 High Drywell Pressure I 5 1 EK3.05 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE: 3.5 15
+ RWflooding 62-4-44( 1 K F R 55.43.2 SUO Ontj+) 4.0 40 Knowledge of emergency plan protective action nxornmendations.
295025 High Reactor Pressure / 3 62.2.12 Knowledge of surveillance procedures.
1 3.0 46 295026 Suppression Pool High Water G2.1.18 Temp. I 5 AbiJity to make accurate / clear and concise logs / records / status boards / and 2.9 76 reports.
EA2.01 ( 1 X F R 55.43.2/5 SUO Ody)
Ability to determihe and/or interpret the following as they apply to 4.2 98 SUPPRESSION POOL HIGH WA7ER TEMPERAN R E :
+ Supprssim pool water temperatun?
- - N/A for 3AF - KJA for Mark I11 Containments ONLY---------------------- --
SRO only K/As shown In /ta/icr 1/25/2005 - 8:27:31 AM Page 4
( 1 ES401 2 Form ES-dl-1 ES41 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 11Group 1 (RO ISRO)
K K ElAPE # I Name ISafety Function KIA Toplc(s) IR #
1 2 295028 High Drywell Temperature 1 5 EK3.04 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE:
3.6 93
+ Increased drywell coding 295030 Low Suppression Pod Wtr Lvl I 5 EAl.06 Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: 3.4 79
+ Condensate storage and transfer (make-up to the suppression pool):
Plant-Specific 295031 Reactor Low Water Level 12 EA2.02 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:
4.0 74
+ Reactor power 295037 SCRAM Condition Present and EK3.01 Power Above APRM Downscale or Unknown I 1 Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR 4.1 02 UNKNOWN:
+ Recirculation pump trip/runback: Plant-Specific 295038 High off-site Release Rate I 9 1 EK2.03 Knowledge of the interrelations between HIGH OFF-SITERELEASE RATE and the 3.6 94 following:
+ Plant ventilation systems -
SRO only K/As shown in italics 1/25/2005 - 8:44:41 AM Page 5
[ f EM01 2 F o ES~-4-1 I ES401 WNR Examination Outline Emergency and Abnormal Plant Evolutions -Tier I/Group 1 (RO I SRO)
F o ES-401-1
~
1 EIAPE II Name I Safety Function K
2 K
3 KIA Topic(.)
62.1.22 Ability to determine Mode of Operation.
2.8 57 WA Category Totals: (RO) 4 4
- Group Point Total: (RO)
Gmup Point Total: (SRO) 7 SRO only K/As shown in /ts//cr 1/25/2005 - 8:27:31 AM Page 6
d ( I ES-401 3 Form ES-WJI-I R BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier f/Group 2 (RO I SRO)
-Form ES-401-1 1 UAPE II Name I Safety Function KIA Topic($) IR
~
295007 High Reactor Pressure I 3 2.9 84 AA1.02 **Plant OE**
Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:
4 D w e l l floor and equipment drain sumps N/A for JAF - K/A for Marlc III Containments ONLY --- 7 -.
295012 High Drywell Temperature I 5 AK2.02 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and 3.6 91 the foltowing:
4 Drywell cooling G2.1.20 (IOCIR 55.43.5 SUO Only)- 4.2 53 Ability to eyecute p & u ~ skps.
SRO only K/As shown in &tics 1/25/2005 - 8:27:31 AM Page 7
i i i EM01 3 F o ES-4-1
~
ES401 BWR Examination Outline Form ES401-1 Emergency and Abnormal Plant Evolutions Tier lIGroup 2 (RO I SRO)
WAPE # I Name I Safety Function
- 2 I O 1 KIA Toplc(s)
IR 1 #
295015 Incomplete SCRAM / 1 I 1 162.4.20 I 3.3 I 92 Knowledge of operational implications of EOP warnings / cautions / and notes.
- - NOTRANDOMLY SELECTED------ -
u--
295029 High Suppression Pool wtr Lvl I 5 f EA1.01 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL:
+ HPCI: Plant-Specific 3-4 I 73 62'4.8 (IOCFR 55A3.5 SRO OnW) - t Knowledge of how the event-based emegerq/abnorma/ operating p/clrcedures an?used in conjundbn with the symptom-&&
NOT RANDOMLY SELECTED------------
EO&.
I -I 3.7 I 59 295034 Secondary Containment EK2.01 Ventilation High Radiation I 9 Knowledge of the interrelations between SECONDARY CONTAINMENT VENTILATION HIGH RADIATION and the following:
+ Process radiation monitoring system 295035 Secondary Containment Hgh 1 62.1.21 Differential Pressure I 5 Ability to obtain and verify controlled procedure copy.
SRO only K/AS shown in italics 1/25/2005 - 8:27:31 AM Page 8
2 i ES-401 3 Form ESudl-1 ES-401 BWR ExaminationOutline FOIT~
ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1IGroup 2 (RO ISRO)
WAPE t I Name I Safety Function K K A A G 1 1 2 1 I KIA Topic@) 1R I #
500000 High CTMT Hydrogen Conc. I 5 7 EA2.02 (10 CFR 55.43.2 SRO -
I AbiHy tv determihe and/w interptet the MJowing as they appfy to HIGH PWMRY CON7-AINMENTHYDROGEN CONENJ7U77ONS:
3.5 57
+ Oxygen mnRorthg system svaihbiJ#y WA Category Totals: (RO)
I l l ~ ~~~~ ~
Group Point Total:
Group Point Total:
(RO)
(SRO)
2 I 1 -
ES-401 4 Form ES+d-l BWR ExaminationOutline Plant Systems -Tier ZGroup I(RO I SRO)
FOITIIES-401-1 System # / Name A
1 A
2 =I 1 62.3.4 KIA Toplc(s) IR #
Knowledge of radiation exposure limits and contamination control / 2.5 26 including permissible levels in excess of those authorized.
K2.02 Knowledge of electrical power supplies to the following: 2.5 1
+ Motor operated valves 1 K5.05 Knowledge of the operational implications of the following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSlEM: 3.3 48
+ Turbine speed control: BWR-2,3,4 A1.07 Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION S Y mM 3.7 43 controls including:
+ System discharge pressure: BWR-2,3,4 I -
K6.03 Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSlEM:
3.3 29 Torus/suDpression pool water level SRO only K/& shown in &lks 1/25/2005 - 8:27:31 AM Page 10
I ( (
EM01 4 Form E S s d - 1 BWR Examination Outline F o ES-401-1
~
Plant Systems -Tier 2/GrouD 1 (RO I SRO)
KIA Topic($) IR A3.07 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including:
3.7 24 6 Lights and alarms: Plant-Specific K3.12 Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on the following:
3.2 32 6 Secondary containment integrity K5.01 Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: 2.6 44 6 Detector operation K6.05 Knowledge of the effect that a loss or malfunction of the following will 3.1 25 have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM:
6 Trip units SRO only K/As shown in italics 1/25/2005 - 8:27:31 AM Page 11
ES-401 4 Form ES-WJI-1 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO I SRO)
K 2
K 3
KIA TopIc(s) IR 1 I K4.04 1 Knowledge of SOURCE RANGE MONITOR (SRM) S Y m M design featwe(s) and/or interlocks which provide for the following:
+ Changing detector position A4.05 Ability to manually operate and/or monitor in the control room:
+ SRM back panel switches, meters, and indicating lights A3.05 Ability to monitor automatic operations of the AVERAGE POWER RANGE MOMITOR/LOCAL POWER RANGE MONITOR SYSIEM including:
Flow cortverter/comparator alarms
-0 only K/AS shown in &#cx 1/25/2005 - 8~27~31 AM Page 12
f i ES-401 4 Form ES-WJI-~
BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO I SRO)
P P
- K K A A A KIA Toplc(s) IR 5 6 1 3 4 I K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR CORE ISOLATION COOLING SYSEM (RCIC): 3.5 41
+ Condensate storage and transfer system A2.01 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING S Y m M (RCIC); and (b) based on those 3.8 58 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
+ System initiation signal 624.16 (IOCFR 55.43.5 S t O Onw) 4.0 64 Kmwkdge of EOP impkmeniatkm hierarchy and modination wth other supprt p&un?s.
1 A4.02 Ability to manually operate and/or monitor in the control room: 4.2 97 c
+ ADS logic initiation - I_
-0 only K/As shown in /talks 1/25/2005 - 8:27:31 AM Page 13
03 03
1 I ES401 4 Form ES-WJI-I BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 1 (RO I SRO)
KIA Topic(8) IR A1.O1 Ability to predict and/or monitor changes in parametersassociated with operating the STANDBY GAS TREATMENT S Y m M controls 2.9 56 including:
+ systemflow 262001 AC Electrical 62.4.27 Knowledge of fire in the plant procedure. 3.0 77 A 2 0 1 ( I K F R 55.43.5 5RO Onlyl Ability to (a) p m f . . the imp& of the tblowing on the A. C ELECTRIC;IIL OISiT.lBU77ON; and (b) k e d on those p&idionnS, use 3.6 60 pmcedures to cv&/ cvntrvb or mitiipte the cvnsquences of t h s e abnomat cvndtions or operahons:
+ Tuhihe/genemtor ttip A4.01 Ability to manually operate and/or monitor in the control room: 2.0 87
+ Transfer from alternative source to preferred source -
SRO only K/As shown in italics 1/25/2005 - 8:27:31AM Page 15
2 I I ES-401 4 FOIITI ES-d-1 ES-401 BWR ExaminationOutline F O ~ES-401-1 I
Plant Systems - Tier 2lGroup 1 (RO I SRO)
System # I Name KIA Toplc(s) IR I 263000 DC Electrical K1.04 Distribution Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECIRICAL DISTRIBUTION and the 63 following:
+ Grounddetection A3.01 Ability to monitor automatic operations of the D.C. ELECTRICAL DI!3RIBUTION including: 3.2 89
+ Meters, dials, recorders, alarms, and indicating lights A 2 0 2 (IOCFR 55.43.5 -0 Om) -
AbiMy to (a) p d i d the imp& of the following on the D.C.
E L E M G 4 L DISlRiBUl7Oh$-and (6) based on r/7ose pw"ions, use 2.9 62 prvceduns to c v m wntrvb or mitrigate the wnsquences of those abnormal cvndmns or optations:
+ Loss of ventilabbn dwng charging 264000 EDGs K3.03 Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEUJET') will have on the following: 4.1 65
+ Major loads powered from electrical buses fed by the emergency generator(s) 300000 InstrumentAir K2.01 Knowledge of electrical power supplies to the following: 2.8 90
+ Instrument air compressor -
SRO only K/As shown in italics 1/25/2005 - 8:27:31 AM Page 16
2 I i ES-401 4 Form ESvrll-1 b
I ES-401 BWR Examination Outline
. 1 (RO Plant Systems -Tier 2/GrouD . / SROl F o ES-401-1
~
K K System # I Name 1 2 400000 Component Cooling Water Knowledge of CCWS design feature(s) and/or interlocks which provide for the following:
+ Automatic start of the standby pump 1 KM&atego'y Point Totals:
I11212 4131 Group Point Total: (RO)
I 1
I I
I I 26 SRO only K/AS shown in its/ics 1/25/2005 - 8:27:31 AM Page 17
i I ES-401 5 Form ESUdl-1 1 ES-401 BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO I SRO)
FOITI ES-401-1 I System1YIName I: KIA Topic($) IR #
A1.01 Ability to predict and/or monitor changes in parametersassociated with operating the REACTOR MANUAL CONTROL SYSTEM controls 2.8 42 including:
+ CRD drive water flow 201003 Control Rod and Wive K6.02 Mechanism Knowledge of the effectthat a loss or malfunction of the following will have on the CONTROL ROD AND DRIVE MECHANISM:
3.0 9
+ Reactor pressure I- I-202002 Recirculation Flow Control K5.02 Knowledge of the operational implications of the following concepts as they apply to RECIRCULATIONFLOW CONTROL SY!3EM: 2.6 17
+ Feedback signals 62.214 (10CFR 55.43.3 SRO Only]
3.0 30 Knowledge of the prvces for making mnfiguration changes.
_ I_
S t O only K/As shown in italics 1/25/2005 - 8:27:31 AM Page 18
Sldtl OOOPCZ C-Cf-S3 U O j E COPS3 I
2 i [
ES-401 5 Form ESUd1-1 I BWR ExaminationOutline Plant Systems -Tier ZGroup 2 (RO I SRO)
Form ES-401-1 I System # / Name
=I K/A Topic(8) IR #
_ I -
- NOT RANDOMLY SELE(=TED-------------------
268000 Radwaste K1.03 Knowledge of the physical connections and/or cause-effect 2 relationships between RADWA5l-Eand the following:
2.6
+ Reactor building equipment drains: Plant-Specific 271000 Offgas A2.10 Ability to (a) predict the impacts of the following on the OFFGAS SYSIEM; and (b) based on those predictions, use procedures to 3. I 19 correct, control, or mitigate the consequences of those abnormal conditions or operations:
+ Offgas system high flow 272000 Radiation Monitoring A2.16 Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSEM; and (b) based on those predictions, use 2.7 66 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
+ Instrument malfunctions SRO only K/AS shown in ita/ics 1/25/2005 - 8:27:31 AM Page 20
I A: I I ES-401 5 Form ES-dl-1 l ES401 BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO I SRO)
Form ES401-1 1I K/A Topic(8)
/ I R / #
K4.01 Knowledge of FIRE PROTECTION S Y m M design feature(s) and/or interlocks which provide for the following:
3.4 20
+ Adequate supply of water for the fire protection system NOTRANDOMLY w--- 1 - 1 A2.01 Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 3.3 85 conditions or operations:
+ Personnel airlock failure A2.03 Abillty to (a) predict the impacb of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 3.4 71 conditions or operations:
+ Initiation/reconfiguratinfailure K4.02 Knowledge of REACTOR VESSEL INTERNALS design feature(s) and/or interlocks which provide for the following:
+ Separation of fluid flow paths within the vessel Group Point Total: (RO)
Group Point Total: (SRO) 1 3 SRO only K/AS shown in its/lb 1/25/2005- 8:27:31 AM Page 21
ES-401 Generic Knowledge and Abilities Outline (Tier 3) FOIWI ES-401-3 lay 16 - 20,2 35 A
RO SRO-Only KIA#
I Topic IR # IR #
2.1. G 2.1.20 4.3 3 Ability to execute procedure steps.
G2.1.9 (1OcFR 5543.5 s;RO mw)
Abillly to d i m pefionnel activities inside the 4.0 23 31 I 62.1.27 2.8 4 I
- . I .
Knowledge of system purpose and/or function.
62.1.20 (locF# 55,43.2/6 -mOon/LI 4.2 52 Ability to ewxute procedure steps.
?A NOT RANDOMLY SELECTED----------- -
?& NOT RANDOMLY SELECTED----------
I NOT RANDOMLYSELECT- -
?& 1 NOT RANDOMLY SELECT- -
Subtotal 2.2. 62.2.24 **Plant OE**
m-2.6 2
80 Abilrty to analyze the affect of maintenance activities on LCO status.
62.2.13 (lOcn0 55.43.5 -0 on/LI
- p/ant O**
KmwMge of tagging and dearam pmedures.
2.2. G2.2.1 3.7 55 Ability to perform pre-startup procedures for the facility / including operating those controls associated with plant equipment that could affect reactivity.
62.2.29 (1oIcFR 55.43.2/6 -0 on/y)
Knowledge of SRO fuel bandlihg respnsibiliti&s.
2.2. 62.2.30 3.5 35 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area / communication with fuel storage facility / systems operated from the control room in support of fueling operations /
and supportinq instrumentation.
NOT RANDOMLY SELECTE-NOT RANDOMLY SELECTE-NOT RANDOMLYSELECTE-Subtotal SRO only K/As shown in italics 1/25/2005- 8~32~28 AM Page 22
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility:
-ck J.A. FitzPat Date of Exam: -
May 16 20,2 05 RO 1
i SRO-Only Category KIA # Topic 2.3 62.3.4 2.5 18 Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.
62.3.2(ZOICFR 55.4.3.24 -mOon/j.) 2.9 69 T
Knowme of hdt&AMRA pmqram.
2.3 62.3.9 2.5 16 Knowledge of the process for performing a containment purge.
62.3.7(10CfR 55.4.3.4 -m0 3.3 70 KmwMge of the process for preparing a radiation work permit.
2.3 62.3.11 Ability to control radiation releases. 2.7 NOT RANDOMLY SELECTED---------- -
NOT RANDOMLY SELECTE- -
NOT RANDOMLY SELECTE- _ I T
Subtota 2.4.
3 62.4.2 I 3.9 Knowledge of system setpoints / interlocks and automatic actions associated with EOP entry conditions.
62.4.49 (JOCFR 55.43.5 -m0 Abilty to pedorm without reference to onlj.) 4.0 22 procedures those actions that q u i r e immeaiate operation of systm mpunents and cvntmls.
2.4. 62.4.26 I I Knowledge of facility protection requirements including fire brigade and portable fire fighting 2.9 72 z?c equipment usaqe.
NOT RANDOMLYSELECTE-Q)
P NOT RANDOMLYSELECTE- E NOT RANWMLY SELECTED---------- --I-w NOT RANDOMLY SELECTED---------- - I- - I --
rier 3 Point Total E
SRO only K/AS shown in italics 1/25/2005- 8:32:28AM Page 23
ES-401 Record of Rejected WAS Form ES-4014 Tier I Randomly Reason for Rejection Group Selected WA 111 295016 G2.1.5 RO WA 2.5 (2.3), No Plant-Specific Priority 111 295023 AK3.05 Plant-Specific BWR-1 Only 111 295023 AK3.04 No Plant Procedures for Non-Coincident Scram No reasonable link between High Drywell Pressure Emergency 111 295024 G2.3.2 Procedures and the facility ALARA Program that is testable at the SRO level 111 295025 G2.2.5 RO KIA 2.5 (1.6), No Plant-Specific Priority 111 295026 G2.1.4 RO WA < 2.5 (2.3), No PlantSpecific Priority 111 295038 EK2.12 Plant-Specific BWR-6 Only 1I 1 600000 AA2.01 SRO WA < 2.5 (2.3), No Plant-Specific Priority 112 295015 G2.4.44 RO KIA < 2.5 (2.1), No Plant-Specific Priority 1/2 295035 G2.1.34 RO WA < 2.5 (2.3), No Plant-Specific Priority 112 295035 G2.1.5 RO WA < 2.5 (2.3), No Plant-Specific Priority
~
211 203000 G2.3.7 RO WA < 2.5 (2.0), No Plant-Specific Priority
~
211 215003 K5.02 RO WA 2.5 (2.2), No Plant-Specific Priority 211 21 5004 K4.03 RO KIA < 2.5 (2.4), No Plant-Specific Priority 2/1 223002 G2.3.5 RO KIA < 2.5 (2.3), No Plant-Specific Priority No WAS > 2.5, No Plant-Specific Priority, Randomly Selected 211 262002 A1 Another Category No WAS In This Category, Randomly Selected Another 211 300000 A I Category 211 300000 K5.03 RO WA < 2.5 (2.1), No Plant-Specific Priority
~
212 20 1004 N/A JAF - All WAS for BWRs-486 Only No Reasonable Link Between RPlS And Radioactive Control 212 214000 G3 Generic WAS 2/2 226001 K5.01 RO WA < 2.5 (2.2), No Plant-Specific Priority 1/25/2005 - 8106148AM Page 1
ES401 Record of Reiected WAS Form ES401-4 Tier I Randomly Reason for Rejection Group Selected WA 212 268000 K1.15 RO WA < 2.5 (2.3), No Plant-Specific Priority No WAS In This Category, Randomly Selected Another 212 290001 K2 Category 3 G2.1.34 RO WA 2.5 (2.3), No Plant-Specific Priority 3 G2.2.10 RO WA < 2.5 (1.9), No Plant-Specific Priority 3 G2.2.16 RO WA 2.5 (1.9), No Plant-Specific Priority 3 G2.2.3 JAF Single Unit - WA for Multi-Unit 3 G2.2.6 RO KIA 2.5 (2.3), No Plant-Specific Priority 3 G2.2.14 RO WA < 2.5 (2.1), No Plant-Specific Priority 3 G2.2.31 RO WA < 2.5 (2.2), No Plant-Specific Priority Rejected On Overlap With Questions 18 And 26. Randomly 111 295024 G.2.3.4 Selected Another Category WA.
Rejected On No Reasonable Linkage Between High 1I 2 500000 G.2.3.6 Containment H2 And Knowledge Of Requirements To Review And Approve Release Permits.
1/25/2005 - 8106148AM Page 2
ES-301 Administratlve ToPics Outline F o ES-301-1
~
Facility: J.A. FitzPatrick Date of Examination: May 16 - 20,2005 Examination Level (circle one): R8 Operating Test Number: LOI-05-01 Administrative Topic Type Describe activity to be performed (see Note) Code Conduct of Operations G2.1.7 (SRO VR: 4.4) AbUw to W u a t e phnt perfonncmce 1Md make op.rrdonul/udgmeurlrbared~tin~charscteritics/mcfw bahsvior/andin~~~taion.
Perform Core Thermal Heat Balance Verification 3
Conduct of Operations (RAP-7.3.03, Section 9.2, Attachment 2)
~~
02.1.25 (SRO m:3.1) ~billly to o G i n 8nd interpret strrdion
~ ~ m ~ t s ~ 1 1 o o r q p h d / m o ~ ~ / a n d t s b (
contain perfonnance dutr.
Determine HPCl High RPV Water Level Trip Setpoint (OP-I 5, Attachment 3) 62.222 (SRO UR: 4.1) Knowledge of llmiting conditions fbr Equipment Control I N m o t 3 8 8nd ha.
Given a Chemistry Report, Evaluate Technical Specification Compliance (TS 3.4.6, TRM 3.4.8 and Table 3.4.8-1)
Radiation Control 62.3.4 (SRO UR: 3.1) Kmwb@m of rsdladon expasum limb and contaminatbncontrd/MWngpemisdbie ieveh in excess of thme 8uthorized.
N Determine Visitor RCA Access Requirements (AP-07.05, Section 8.1 and Attachments 3 & 5)
Emergency Plan 62.4.41 (SRO UR: 4.1) Knowledg.of the e m w y action level thmshokiband chss&at&rs.
N, s Classify the Event Following NRC Exam Scenarios l(2)
(IAP-2)
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.
Ir Type Codes & Criteria: (C)ontrol Room (D)irect from bank (I3 for ROs; 5 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (r 1)
(P)revious 2 exams 1; randomly selected)
(S)imulator
ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 Facility: J.A. FitzPatrick Date of Examination: May 16 - 20, 2005 Control Room Systems@(8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
Safety System I JPM Title Type Code*
Function
- a. Verify HPCl Isolation SIA, N 4
- b. Reset PClS Group I Isolation s, D, L, p 5
- c. Re-open MSlVs s, D, L, p 3
- d. Respond to CRD Pump Trip s, A, N 1
- e. Swap FWLC, Single to 3-Element s, N 2
- f. Swap Electrical Bus, Reserve to Normal Service s, M, A 6
- 3. Perform APRM Gain Adjustments s, A, p 7
- h. NIA SRO- -_.-
In-Plant Systemse (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
I. Remove a HCU from Service 1 8 All control room (and inplant) systems must be different and serve different safety functions; inplant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RO I SRO-I I SROY (A)lternate 46 I 46 I 2-3 (C)ontrol room (D)ired from bank (E)mergencyor abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank induding l(A)
(P)revious2 exams (WA (S)imulator
Appendix D Scenario Outline F o ES-D-1
~
Facility: J. A. FitzPatrick Scenario No.: 1-1 Op-TestNo.: LOI-05-01 I I I I I I1 Examiners: I I CRS: SROI-1 SROI-2 I RO: SURROGATE Initial Conditions: Operating normally at 100% O P Turnover: Operating normally at 100% CTP; RHR Loop "Alpha" in Torus Cooling Mode; HPCI Surveillance Testing recently completed successfully; Torus Cooling needs to be secured; Then, reduce power to 95% per Reactor Engineer's guidance and perform ST-208.
Event Event No. Malf. No. Type* (Credited Position) / Event Description 1 ------ N (SNO) Shut down Torus Cooling 2 SW04:A TS (CRS) Running RHR/SW Pump Trip (Before S/D) 3 ------ R (SNO) Power Reduction to 95%
4 I NMl4(X) 1 I ~-
1 (RO) APRM Fails to Respond to Power Reduction I ------ [ APRM Bypassed 5 j ------ I TS I (CRS) APRM Declared Inoperable 6 I ------ I C I (SNO) NPO Reports EHC Leak; Swap EHC Pumps 7 I RH1O:A I C 1 (SNO) Torus Rupture in RHR Suction; Level Drops; EOP-5/4 8 1 RD22(A/B) 1 M 1 (ALL) Manual Scram; ATWS; SDN Blockage; EOP-3; Level/Power Control 9 SLOl:A/B C (RO) SLC Pump Start Failure (NOTE 1) 10 TC02:B C (SNO) EHC Pump Trip; Turbine Trip; Bypass Valve Failure 11 ------ M (ALL) Level / Power Control NOTE 1- SLC initiation is related to the JAF IPE ATWS Dominant Accident Sequence
- (N)omal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 2.2.2 - SITE AREA
Appendix D Scenario Outline FOITII ES-D-1 Facility: J. A. FitzPatrick Scenario No.: 1-2 Op-Test No.: LOI-05-01 CRS: SROI-3 Examiners:
t- - i Operators: SNO: SROI-4 RO: SURROGATE Facility: 3. A. FitzPatrick Scenario No.: 1-3 Op-Test No.: LOI-05-01 I Examiners:
t------l Facility: 3. A. FibPatrick Scenario No.: 1-4 Op-Test No.: LOI-05-01 m Examiners: F CRS:
SNO:
SROI-7 SURROGATE SURROGATE I
ANTICIPATED EAL: 2.2.2 - SITE AREA
LOI-05-01 NRC EXAM SCENARIO 1NARRATIVE 1
The scenario will begin with the plant operating normally at 100% Core mermal Power. HPCI surveillance testing has just been completed and the Torus Cooling Mode of RHR is to be secured. During the shutdown of the Torus Cooling Mode, the " A RHR/SW pump will trip. Dispatch of the NPO will produce a local report of "A" RHR/SW pump breaker charring. The CRS will declare the RHR/SW Subsystem inoperable. Per Reactor Engineer's guidance, a power reduction to 95% will then be commenced for performance of ST-20B. During the power reduction, "C"APRM will not respond as expected. The APRM will be declared inoperable and bypassed. An NPO performing rounds will report a sizable EHC leak in the running 'A" EHC pump discharge filter. The crew will swap the running EHC pumps isolating the leak. A rupture in the Torus shell will then start a slow reduction in Torus Water Level. AOP-9 may be entered momentarily resulting in immediate direction to enter EOP-4/EOP-5. EOP4 will be entered on low Torus water level and EOP-5 will be entered on High Sump/Floor Water Level in the Crescent Area. Local investigation will reveal that the leak is isolable and isolation actions will commence. Before Torus Water Level reaches 10.75 feet, HPCI will be tripped and a manual scram inserted. Shortly after the manual scram occurs, the leak will be reported isolated. The manual scram will result in a power reduction to 20-30% due to a blockage in the SDN(s). EOP-2 will be entered then exited to EOP-3 resulting in a start of either SLC pump. SLC I
injection will fail resulting in a manual start of the other SLC pump. The Level/Power Control contingency will be exercised by first terminating and preventing injection sources followed by re-injection at a reduced R W water level. A loss of the remaining EHC pump will result in a turbine trip and a loss of the bypass valves shortly thereafter. This will force transitioning pressure control to the SRV's and trending the approach to the Boron Injection Initiation Temperature (BITT). If BIIT is reached, another Terminate and Prevent will result in RPV water level control at an even lower level. Timely action to complete rod insertion may avoid exceeding BIIT. The control rod insertion success path will require resetting the scram signal, draining the SDN(s) and re-inserting a manual scram. Upon inserting the second manual scram, all control rods will be reported full-in and the scenario will be terminated.
ADDendix D Scenario Outline F o ES-D-1
~
c Facility:
Examiners:
initial J. A. FitzPatrick Scenario No.: 2-1 loperston: SNO:
I CRS:
I RO:
Op-Test No.:
SROI-2 SROI-1 SURROGATE LOI-05-01 I
Conditions: 3% - 5% CTP, Reactor Startup In-Progress Turnover: Reactor Startup In-Progress at 3 - 5% CTP; Currently at OP-65, Step D.19; Reactor Mode Switch in "Startup"; Continue Power Ascent to 25% CTP Using Control Rods; Reactor Engineer is present in Control Room; "Alpha" Circulating Water Pump Has Just Been Repaired; Start Up "Alpha" CW Pump and Secure "Bravo" CW Pump for Inspection.
Event Event No. Malf. No. TY Pe* (Credited Position) / Event Description 1 ------ N (SNO) Swap Circulating Water Pumps 2 RR19(X) I (SNO) Selected Level Transmitter Fails Downscale 3 ------ TS (CRS) Level Transmitter Inoperable 4 AD0600 I (SNO) Inadvertent Safety Relief Valve (SRV) Opening
I AD05(X) I ------ I SRV Experiences Leakage 5 ------ TS (CRS) SRV Inoperable 6 EDl8(X) C (SNO) 10500 / 10600 Bus Loss
------ ------ Degraded Containment Cooling on Operating Side 7 AD08(X) C (SNO) Same (Leaking) SRV Opens Mechanically 8 I ~
~
I ~
M I (ALL) Manual Scram; EOP-2 9 MS16(X) C (SNO) SRV Tailpipe Failure in Torus; EOP-4 10 RHOl(X) c (SNO) RHR Pump Trip During Torus Spray 11 ------ M (ALL) RPV Emergency Depressurization
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 3.1.I- ALERT
~~
Atmendix D Scenario Outline Form ES-0-1 Facility: J. A. FitzPatrick Scenario No.: 2-2 Op-Test No.: LOI-05-01 Examiners:
SURROGATE I I Facility: J. A. FitzPatrick Scenario No.: 2-3 Op-Test No.: LOI-05-01 Examhers:
SURROGATE Facility: J. A. FitrPatrick Scenario No.: 2-4 Op-Test No.: LOI-05-01 SURROGATE Examiners:
SURROGATE ANTICIPATED EAL: 3.1.1 - ALERT
LOI-05-01NRC EXAM SCENARIO 2 NARRATIVE The scenario will begin with a reactor startup in progress at 3-5% Core Thermal Power. Turnover information will indicate that repairs to the 'A' Circulating Water Pump have just been completed. Crew will be directed to place the 'A' CW pump in service and secure 'B'. The "selected" Reactor Water Level Transmitter will fail downscale resulting in a slow rise in RPV Water Level. The crew will take manual control of RPV water level, swap level columns and return to automatic level control. The CRS will declare the failed transmitter inoperable. An inadvertent ADS SRV opening will result in actions to place Toms cooling in service and remove the SRV fuses. Fuse removal will close the SRV; yet it will continue to have pilot valve leakage that slowly worsens. The CRS will declare the SRV inoperable. A 4160 VAC bus loss will remove / degrade the containment cooling functions of the loop in Torus Cooling. Continued SRV leakage will result in mechanical opening of the SRV (industry OE) requiring the crew to manually scram the reactor. The crew will enter and perform EOP-2. The leaking SRV tailpipe will start leaking into the Torus air space resulting in EOP-4 entry. Torus spray will have to occur on the opposite RHR loop; and shortly after initiation, the only RHR pump in that loop will trip unexpectedly. This will force the crew to conclude that an Emergency Depressurization (contingency) is or will soon be required. The scenario will terminate upon the opening of 7 ADS valves.
ADnendix D Scenario Outline Form ES-D-1 Facility: 3. A. FitzPatrick Scenario No.: 3-1 Op-Test No.: LOI-05-01
- MODIFIED CONTINGENCY SCENARIO FROM LOI-03-01 EXAMINATION**
I I , I Examiners:
m I Il Operators:
CRS:
1 SNO:
l l I RO:
Initial Conditions: 75% CTP Turnover: Alpha Circulating Water Pump Just Repaired and Returned to Service; Return Power to 92% Using Recirculation Flow; Hold at 92% for Reactor Engineers Ramp Guidance.
Event No. 1 Malf. No. I Fz1 (Credited Position) I Event Description 1 RFI EP09 ------ Seismic Event (Cry Wolf RFP Turbine Vibration Alarm) 2 RFI HP15 C (SNO) HPCI Power Supply Loss (Aux Oil Pump, MOV)
------ TS (CRS) HPCI Inoperable
- -~
3 I MCOl 1 CI(SN0) <ow Loss of Condenser Vacuum 4 I ------ I R I (SNO) AOP-Required Power Reduction RP13 (Pre) (ALL) Main Steam Line Break in Turbine Building (w/ Failure to 5
MSO5 Auto-Isolate, Manual Scram); EOP-2 6 RD13(X) C (RO) One (1) Control Rod Fails to Scram 7 I ------ I ------ I RCIC for Level Control; SRVs for Pressure Control (Note 1/2) 8 1 AD07(X) 1 I/C I (SNO/RO) Several SRVs Fail to Open NOTE 1- RCIC is an IPE Risk-Reduction System NOTE 2 - Use of RCIC for level Control Upon HPCI Failure is an IPE Key Operator Action (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 8.4.4 - ALERT
ADDendix D Scenario Outline F o ES-D-1
~
Facility: J. A. FitzPatrick Scenario No.: 3-2 Op-Test No.: LOI-05-01 Examiners:
Faciltty: 3. A. FitzPatrick Scenario No.: 3-3 Op-Test No.: LOI-05-01 Examiners:
LOX-05-01 NRC EXAM SCENARIO 3 NARRATIVE The scenario will begin with the reactor at 75% Core Thermal Power. A seismic event will result in several failures starting with a 'crywolf' RFP Turbine alarm on high vibration. Vibration will be slightly elevated and monitored by the crew.
The following event will be a HPCI power supply loss that will disable HPCI. The CRS will declare HPCI inoperable. The crew will then notice a slow loss of condenser vacuum and perform the AOP actions including a power reduction using recirculation flow. The major event will be a Main Steam tine Break in the Turbine Building that will fail to automatically isolate. A manual scram will be inserted followed by manually isolating the steam lines. During the scram, one control rod will fail to scram but will be inserted using RMCS. RCIC will be operated for Level Control and the SRVs will be operated in Pressure Control.
Several SRVs will fail to open forcing alternative SRV selection. The scenario will terminate upon stabilization of Pressure and Level Control.