ML15110A385
| ML15110A385 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/12/2015 |
| From: | Todd Fish Operations Branch I |
| To: | Exelon Nuclear Generation Corp |
| Shared Package | |
| ML14238A301 | List: |
| References | |
| TAC U01905 | |
| Download: ML15110A385 (27) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility:
Nine Mile Point Unit 1 Date of Exam:
March 2015 SRO-Only Points Tier Group K
K K
G 1
2 3
Total A2 G*
Total
- 1.
3 3
3 4
20 4
3 7
Emergency 2
2 7
2 3
Plant Tier Evolutions Totals 5
4 4
5 27 5
5 10 2
2 2
3 2
3 2
2 2
3 3
26 3
2 5
- 2.
Plant 2
2 12 0
2 3
Systems Tier Totals 3
3 3
4 3
5 3
3 3
4 4
38 4
4 8
- 3. Generic Knowledge & Abilities 2
3 4
2 3
4 10 7
Categories 2
2 3
3 2
2 2
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 75 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 0.1.b of ES-401, for guidance regarding elimination of inappropriate KIA 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 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) Kl As 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 0.1.b of ES-401 for the applicable KIA's
- 8.
On the following pages, enter the KIA 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. 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 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A 1 A2 G
KIA Topic(s)
AA2.03 - Ability to determine and/or 295023 Refueling Accidents I 8 interpret the following as they apply to REFUELING ACCIDENTS: Airborne contamination levels AA2.04 - Ability to determine and/or 295004 Partial or Complete interpret the following as they apply to Loss of DC Power I 6 PARTIAL OR COMPLETE LOSS OF D.C. POWER: S stem lineups AA2.06 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to Trip/ 3 MAIN TURBINE GENERATOR TRIP:
Feedwater temperature 295003 Partial or Complete 2.2.40 - Equipment Control: Ability to Loss of AC Power I 6 apply technical specifications for a s stem.
2.4.31 - Emergency Procedures I Plan:
295006 SCRAM / 1 Knowledge of annunciator alarms, indications, or response procedures.
2.1.31 - Conduct of Operations: Ability 295026 Suppression Pool High to locate control room switches, controls, and indications, and to Water Temperature I 5 determine that they correctly reflect the desired lant lineu.
EA2.01 - Ability to determine and/or 295025 High Reactor Pressure I interpret the following as they apply to 3
HIGH REACTOR PRESSURE: Reactor pressure AK1.03 - Knowledge of the operational 295005 Main Turbine Generator implications of the following concepts as Trip/ 3 x
they apply to MAIN TURBINE GENERATOR TRIP: Pressure effects on reactor level AK1.03 - Knowledge of the operational 295004 Partial or Complete implications of the following concepts as Loss of DC Power I 6 x
they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Electrical bus divisional se aration EK1.01 - Knowledge of the operational 295024 High Drywell Pressure I implications of the following concepts as 5
x they apply to HIGH DRYWELL PRESSURE: Drywell integrity: Plant-Specific EK2.09 - Knowledge of the interrelations 295038 High Off-site Release x
between HIGH OFF-SITE RELEASE Rate/ 9 RATE and the following: Post accident sam le s stem PASS : Plant-S ecific AK2.02 - Knowledge of the interrelations 295018 Partial or Complete between PARTIAL OR COMPLETE x
LOSS OF COMPONENT COOLING Loss of CCW I 8 WATER and the following: Plant o erations EK2.05 - Knowledge of the interrelations between SCRAM CONDITION 295037 SCRAM Conditions PRESENT AND REACTOR POWER Present and Reactor Power x
ABOVE APRM DOWNSCALE OR Above APRM Downscale or UNKNOWN and the following: CRD Unknown/ 1 hydraulic system Imp.
Q#
3.8 76 3.3 77 2.7 78 4.7 79 4.1 80 4.3 81 4.3 82 3.5 39 2.9 40 4.1 41 2.9 42 3.4 43 4.0 44
ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G
KIA Topic(s)
AK3.06 - Knowledge of the reasons for 295006 SCRAM I 1 x
- .r*
the following responses as they apply to J'
- ,~ '
SCRAM: Recirculation pump speed reduction: Plant-Specific I{~/
j.Z **
EK3.01 - Knowledge of the reasons for the following responses as they apply to 295031 Reactor Low Water x
REACTOR LOW WATER LEVEL:
Level 12 Automatic depressurization system
- ~
- :?-
actuation EK3.03 - Knowledge of the reasons for 295028 High Drywell x
the following responses as they apply to Temperature I 5 HIGH DRYWELL TEMPERATURE:
- '. Drvwell spray operation: Mark-1&11
- ~*~;'. *.* AA 1.07 - Ability to operate and/or 295001 Partial or Complete r;
monitor the following as they apply to Loss of Forced Core Flow x
PARTIAL OR COMPLETE LOSS OF Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION:
Nuclear boiler instrumentation system AA 1.03 - Ability to operate and/or 295019 Partial or Complete monitor the following as they apply to x
./.
PARTIAL OR COMPLETE LOSS OF Loss of Instrument Air I 8 INSTRUMENT AIR: Instrument air
[:
- ~,, *
..* r:;'. compressor power supplies
,. *--:<. ( t:~;:* EA 1.03 - Ability to operate and/or 295025 High Reactor Pressure I x
monitor the following as they apply to 3
HIGH REACTOR PRESSURE:
Safetv/relief valves: Plant-Specific
.:;:/ '";:*****
AA2.06 - Ability to determine and/or 295021 Loss of Shutdown
)(~< *'
interpret the following as they apply to Cooling/ 4 LOSS OF SHUTDOWN COOLING:
- 'c':;r-:.
- Reactor pressure AA2.04 - Ability to determine and/or 295003 Partial or Complete interpret the following as they apply to Loss of AC Power I 6
[*:
PARTIAL OR COMPLETE LOSS OF A.C. POWER: System lineups AA2.16 - Ability to determine and interpret the following as they apply to 600000 Plant Fire On-site I 8 PLANT FIRE ON SITE: Vital equipment
~{f~.,
and control systems to be maintained
.-8!i' and operated durina a fire 295026 Suppression Pool High
. *. {t* *.*
2.2.37 - Equipment Control: Ability to
.*. ;zf determine operability and I or availability Water Temperature I 5 of safety related equipment.
2.2.42 - Equipment Control: Ability to 700000 Generator Voltage and
./; ;}'.0l' '
recognize system parameters that are Electric Grid Disturbances entry-level conditions for Technical
- ~
Specifications.
295016 Control Room 2.1.20 - Conduct of Operations: Ability
.:x*
to interpret and execute procedure Abandonment I 7
'* >~-::....,
steps.
[\\;j;~),
EA 1.01 - Ability to operate and/or 295030 Low Suppression Pool
. ;.1~*)::
monitor the following as they apply to x
LOW SUPPRESSION POOL WATER Water Level I 5 LEVEL: ECCS systems (NPSH
\\
considerations): Plant-Specific x
2.4.6 - Emergency Procedures I Plan:
295023 Refueling Accidents I 8 Knowledge of EOP mitigation strategies.
KIA Category Totals:
3 3
3 4
314 4/3 Group Point Total:
Imp.
Q#
3.2 45 3.9 46 3.6 47 3.1 48 3.0 49 4.4 50 3.2 51 3.5 52 3.0 53 3.6 54 3.9 55 4.6 56 3.6 57 3.7 58 I
2017
ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G
KIA Topic(s)
.;~;
~~**.
EA2.02 - Ability to determine and/or 295034 Secondary interpret the following as they apply to Containment Ventilation High SECONDARY CONTAINMENT Radiation I 9 VENTILATION HIGH RADIATION:
Cause of high radiation levels 295032 High Secondary 2.4.18 - Emergency Procedures I Plan:
Containment Area Temperature
<*!: "*~x Knowledge of the specific bases for
/5 EOPs.
- ~**
2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system 295017 High Off-site Release 2:,
operation I status that must be reported Rate 19 to internal organizations or external
- ~ ;~
'; agencies, such as the state, the NRC, or
- ,' the transmission system operator.
"' AK1.01 - Knowledge of the operational 295015 Incomplete SCRAM/ 1 x
,i,'
y' implications of the following concepts as they apply to INCOMPLETE SCRAM:
Shutdown marain AK2.02 - Knowledge of the interrelations 295010 High Drywell Pressure I x
between HIGH DRYWELL PRESSURE 5
and the following: Drywell/suppression
',;~:'. ;;;;\\,,
chamber differential pressure: Mark-1&11
- i' '.: AK3.04 - Knowledge of the reasons for 295008 High Reactor Water
~~:.,..
the following responses as they apply to Level 12 x
HIGH REACTOR WATER LEVEL:
- 't' Reactor feed pump trip: Plant-Specific
.,~ ' '" "
EA 1.01 - Ability to operate and/or 295029 High Suppression Pool x
monitor the following as they apply to Water Level I 5 HIGH SUPPRESSION POOL WATER
- ,,i LEVEL
- HPCI: Plant-Specific
- .
- *~.'
EA2.01 - Ability to determine and/or 295036 Secondary interpret the following as they apply to SECONDARY CONTAINMENT HIGH Containment High Sump/Area SUMP/AREA WATER LEVEL:
Water Level I 5
- n '
Operability of components within the affected area 295032 High Secondary
- . :1 2.4.1 - Emergency Procedures I Plan:
Containment Area Temperature
' *:x Knowledge of EOP entry conditions and 15 immediate action steps.
AK1.02 - Knowledge of the operational 295022 Loss of CRD Pumps I 1 x
.~~;
- ,'~.
implications of the following concepts as they apply to LOSS OF CRD PUMPS: Reactivity control KIA Category Totals:
2 1
1 1
1tl;;,; ****112 Group Point Total:
Imp.
Q#
4.2 83 4.0 84 4.1 85 3.6 59 3.3 60 3.3 61 3.4 62 3.0 63 4.6 64 3.6 65 I
7/3
ES-401 System #I Name K
K K
1 2
3 206000 HPCI 207000 Isolation (Emergency) Condenser 205000 Shutdown Cooling 211000 SLC 215005 APRM I LPRM 211000 SLC x
264000 EDGs x
Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
A2.06 - Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b)
- x:
based on those predictions, use ii*.. procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow: BWR-2,3,4 A2.01 - Ability to (a) predict the impacts of the following on the ISOLATION (EMERGENCY)
CONDENSER; and (b) based on Xe those predictions, use 1:
procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Tube bundle leak:
BWR-2,3 2.4.8 - Emergency Procedures I Plan: Knowledge of how x
abnormal operating procedures are used in conjunction with k** ;,
EOPs.
~. *:.i
- ".c_'.
2.4.47 - Emergency Procedures n:;:
I Plan: Ability to diagnose and recognize trends in an accurate
/>\\,'
and timely manner utilizing the k:**
appropriate control room reference material.
A2.07 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE
.. MONITOR/LOCAL POWER
.::; ) RANGE MONITOR SYSTEM; and (b) based on those
- }(
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation flow channels flow mismatch K1.01 - Knowledge of the physical connections and/or cause-effect relationships J~
between STANDBY LIQUID
...* ;;~
CONTROL SYSTEM and the following: Core spray line break detection: Plant-Specific K1.04 - Knowledge of the physical connections and/or cause-effect relationships
. between EMERGENCY GENERATORS (DIESEUJET) and the following: Emergency qenerator coolinq water system Imp.
Q#
3.5 86 4.5 87 4.5 88 4.2 89 3.4 90 3.0 1
3.2 2
ES-401 System #I Name K
K K
1 2
3 205000 Shutdown Cooling x
212000 RPS x
218000 ADS x
215004 Source Range x
Monitor 400000 Component Cooling Water 261000 SGTS 215005 APRM I LPRM 215003 IRM 262001 AC Electrical Distribution 259002 Reactor Water Level Control Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
K2.01 - Knowledge of electrical power supplies to the following:
Pump motors K2.02 - Knowledge of electrical power supplies to the following:
Analog trip system logic cabinets K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following: Ability to rapidly depressurize the reactor K3.02 - Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM) SYSTEM will have on following: Reactor manual control: Plant-Specific K4.01 - Knowledge of CCWS design feature(s) and or x
interlocks which provide for the following: Automatic start of standby pump K4.02 - Knowledge of STANDBY GAS TREATMENT x
SYSTEM design feature(s) and/or interlocks which provide for the following: Charcoal bed decay heat removal K5.05 - Knowledge of the operational implications of the following concepts as they apply x
to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:
Core flow effects on APRM trip setpoints K5.03 - Knowledge of the operational implications of the x
following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM:
Changing detector position K6.02 - Knowledge of the effect that a loss or malfunction of the x
following will have on the A.C.
ELECTRICAL DISTRIBUTION:
Off-site power K6.04 - Knowledge of the effect that a loss or malfunction of the x
following will have on the REACTOR WATER LEVEL CONTROL SYSTEM: Reactor feedwater flow input Imp.
Q#
3.1 3
2.7 4
4.5 5
3.4 6
3.4 7
2.6 8
3.6 9
3.0 10 3.6 11 3.1 12
ES-401 System # I Name K
K K
1 2
3 262002 UPS (AC/DC) 209001 LPCS 239002 SRVs 300000 Instrument Air 206000 HPCI 207000 Isolation (Emergency) Condenser 263000 DC Electrical Distribution 223002 PCIS/Nuclear Steam Supply Shutoff 206000 HPCI Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the x
UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs A 1.04 - Ability to predict and/or monitor changes in parameters x
associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls includinq: Reactor pressure A2.03 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, x
use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM; and (b) based on those x
predictions, use procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations: Air dryer and filter malfunctions A3.03 - Ability to monitor automatic operations of the x
HIGH PRESSURE COOLANT INJECTION SYSTEM including:
System lineup: BWR-2,3.4 A3.02 - Ability to monitor automatic operations of the x
ISOLATION (EMERGENCY)
CONDENSER including:
Reactor pressure: BWR-2,3 A4.04 - Ability to manually x
operate and/or monitor in the control room: Ground detection circuit: Plant-Specific A4.02 - Ability to manually x
operate and/or monitor in the control room: Manually initiate the system 2.1.23 - Conduct of Operations:
Ability to perform specific system x
and integrated plant procedures during all modes of plant ooeration.
Imp.
Q#
2.5 13 3.7 14 4.1 15 2.9 16 3.9 17 3.8 18 3.0 19 3.9 20 4.3 21
ES-401 System # I Name K
K K
1 2
3 259002 Reactor Water Level Control 264000 EDGs 215003 IRM 223002 PCIS/Nuclear Steam Supply Shutoff 218000 ADS KIA Category Totals:
2 2
2 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
2.1. 7 - Conduct of Operations:
Ability to evaluate plant performance and make x
operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2.4.21 - Emergency Procedures I Plan: Knowledge of the parameters and logic used to assess the status of safety x
functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
K4.01 - Knowledge of INTERMEDIATE RANGE x
MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the followina: Rod withdrawal blocks K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the x
PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Nuclear boiler instrumentation A4.08 - Ability to manually x
operate and/or monitor in the control room: Suppression pool level 3
2 3
2 2/3 2
3 3/2 Group Point Total:
Imp.
Q#
4.4 22 4.0 23 3.7 24 3.3 25 3.7 26 I 26/5
ES-401 System # I Name K
K K
1 2
3 239001 Main and Reheat Steam 234000 Fuel Handling Equipment 271000 Off-gas 202002 Recirculation Flow x
Control 239001 Main and Reheat x
Steam 233000 Fuel Pool x
Cooling/Cleanup 201003 Control Rod and Drive Mechanism 201006 RWM 272000 Radiation Monitoring Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
A A2 A
A G
4 5
6 1
3 4
A2.01 - Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use x
procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Malfunction of reactor turbine pressure regulating system 2.4.9 - Emergency Procedures I Plan: Knowledge of low power I x
shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
2.4.11 - Emergency Procedures x
I Plan: Knowledge of abnormal condition procedures.
K1.04 - Knowledge of the physical connections and/or cause-effect relationships between RECIRCULATION FLOW CONTROL SYSTEM and the following: Reactor/turbine pressure regulating system:
Plant-Specific K2.01 - Knowledge of electrical power supplies to the following:
Main steam isolation valve solenoids K3.01 - Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLING AND CLEAN-UP will have on following: Fuel pool temperature K4.05 - Knowledge of CONTROL ROD AND DRIVE x
MECHANISM design feature(s) and/or interlocks which provide for the following: Rod position indication K5.06 - Knowledge of the operational implications of the following concepts as they apply x
to ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC): Rod groups and steps: P-Spec(Not-BWR6)
K6.03 - Knowledge of the effect that a loss or malfunction of the x
following will have on the RADIATION MONITORING SYSTEM: A.C. power Imp.
Q#
3.9 91 4.2 92 4.2 93 3.1 27 3.2 28 3.2 29 3.2 30 2.8 31 2.8 32
ES-401 System #I Name K
K K
1 2
3 219000 RHR/LPCI:
Torus/Pool Cooling Mode 245000 Main Turbine Generator and Auxiliary Systems 286000 Fire Protection 226001 RHR/LPCI:
Containment Spray Mode 259001 Reactor Feedwater 201001 CRD Hydraulic KIA Category Totals:
1 1
1 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
A A2 A
A G
4 5
6 1
3 4
A 1.07 - Ability to predict and/or monitor changes in parameters associated with operating the x
RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE controls including: Emergency generator loading A2.01 - Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS; x
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine trip A3.06 - Ability to monitor x
automatic operations of the FIRE PROTECTION SYSTEM including: Fire dampers A4.12 - Ability to manually x
operate and/or monitor in the control room:
Containment/drvwell pressure 2.4.46 - Ability to verify that the x
alarms are consistent with the plant conditions.
K6.03 - Knowledge of the effect that a loss or malfunction of the x
following will have on the CONTROL ROD DRIVE HYDRAULIC System: Plant air svstems 1
1 2
1 1/1 1
1 1/2 Group Point Total:
Imp.
Q#
3.2 33 3.7 34 3.0 35 3.8 36 4.2 37 3.0 38 I
12/3
ES-401 Generic Knowledges and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Nine Mile Point Unit 1 Date:
March 2015 RO SRO-Only Category KIA#
Topic 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 4.3 100 practices.
- 1.
Conduct 2.1.28 Knowledge of the purpose and function of 4.1 66 of Operations major system components and controls.
2.1.6 Ability to manage the control room crew 3.8 67 during plant transients.
Subtotal 2
2 Ability to perform pre-startup procedures for 2.2.1 the facility, including operating those controls 4.4 95 associated with plant equipment that could affect reactivity.
2.2.14 Knowledge of the process for controlling 4.3 98 equipment configuration or status.
- 2.
Equipment Control Ability to determine Technical Specification 2.2.35 Mode of Operation.
3.6 68 2.2.12 Knowledge of surveillance procedures.
3.7 69 Subtotal 2
2 2.3.11 Ability to control radiation releases.
4.3 96 2.3.11 Ability to control radiation releases.
3.8 70 Knowledge of Radiological Safety Procedures
- 3.
pertaining to licensed operator duties, such as Radiation 2.3.13 response to radiation monitor alarms, 3.4 71 Control containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.
Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 75 conditions.
Subtotal 3
1
2.4.41 Knowledge of the emergency action level 4.6 97 thresholds and classifications.
Ability to take actions called for in the facility 2.4.38 emergency plan, including supporting or 4.4 99 acting as emergency coordinator if required.
- 4.
Emergency 2.4.45 Ability to prioritize and interpret the 4.1 72 Procedures I significance of each annunciator or alarm.
Plan Knowledge of local auxiliary operator tasks 2.4.35 during emergency and the resultant 3.8 73 operational effects.
2.4.13 Knowledge of crew roles and responsibilities 4.0 74 durinq EOP usaqe.
Subtotal 3
2 Tier 3 Point Total 10 7
ES-401 1 / 1 212 212 Record of Rejected K/As Form ES-401-4 Randomly Selected KIA Question 41 295024 High Drywell Pressure EK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: Containment building integrity: Mark-Ill Question 37 259001 Reactor Feedwater 2.4.1 - Emergency Procedures I Plan: Knowledge of EOP entry conditions and immediate action steps.
Question 29 233000 Fuel Pool Cooling/Cleanup K3.05 - Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLING AND CLEAN-UP will have on following: Fuel pool water fission product concentration Reason for Rejection The facility has a Mark-I containment, not a Mar-Ill containment.
Randomly re-selected KIA 295024 High Drywell Pressure EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL_.
PRESSURE: Drywell integrity: Plant-Spec1f1c.
The randomly selected generic KIA overlaps with those selected for Questions 64 and 7 4 and has the least applicability with this question.
Randomly re-selected KIA 259001 Reactor Feedwater 2.4.46 -Ability to verify that the alarms are consistent with the plant conditions.
A discriminating question could not be developed without testing generic fundamentals knowledge.
Randomly re-selected KIA 233000 Fuel Pool Cooling/Cleanup K3.01 - Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLING AND CLEAN-UP will have on following: Fuel pool temperature.
Question 32 Due to limited interrelation between Radiation 272000 Radiation Monitoring Monitoring and DC power at the facility, an acceptable question could not be developed K6.02 - Knowledge of the effect without testing minutia.
that a loss or malfunction of the Randomly re-selected KIA 272000 Radiation 212 following will have on the Monitoring K6.03 - Knowledge of the effect that RADIATION MONITORING a loss or malfunction of the following will have SYSTEM: D.C. power on the RADIATION MONITORING SYSTEM:
A.C. power.
Question 45 A question could not be developed without 295006 SCRAM testing Generic Fundamentals knowledge or overlapping aspects of Questions 27 and 39.
AK3.03 - Knowledge of the Randomly re-selected KIA 295006 SCRAM 1 / 1 reasons for the following AK3.06 - Knowledge of the reasons for the responses as they apply to following responses as they apply to SCRAM:
SCRAM: Reactor pressure Recirculation pump speed reduction: Plant-response Specific.
Question 69 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 2.2.12 - Knowledge 3
using design and configuration of surveillance procedures.
control documentation, such as drawings, line-ups, tag-outs, etc.
Question 74 The randomly selected KIA overlaps with the 2.4.1 - Knowledge of EOP entry KIA for Question 64.
3 conditions and immediate action Randomly re-selected KIA 2.3.13 - Knowledge steps.
of crew roles and responsibilities during EOP usage.
Question 84 An acceptable question could not be developed 295032 High Secondary for the randomly selected KIA due to limited Secondary Containment area temperature Containment Area Temperature instrumentation installed at the facility.
1 / 2 2.4.3 - Ability to identify post-Randomly re-selected KIA 295032 High accident instrumentation.
Secondary Containment Area Temperature 2.4.18 - Knowledge of the specific bases for EOPs.
Question 89 There are no RO-specific tasks performed outside of the control room during an 211000 SLC emergency related to SLC at the facility.
2.4.34 - Knowledge of RO tasks Randomly re-selected KIA 211000 SLC 2.4.47 -
2 I 1 performed outside the main Ability to diagnose and recognize trends in an control room during an accurate and timely manner utilizing the emergency and the resultant appropriate control room reference material.
operational effects.
ES-301 Facility: Nine Mile Point Unit 1 Examination Level: RO Administrative Topic (see Note)
Conduct of Operations Conduct of Operations Equipment Control Administrative Topics Outline Form ES-301-1 Type Code*
P, D, S 2013 NRC M,R D,R Date of Examination: March 2015 Operating Test Number: LC1 13-01 Describe activity to be performed Perform Reactor Water Level Instrument Checks N1-ST-DO, KIA 2.1.7 (4.4)
Determine Personnel Overtime Availability CNG-SE-1.01.1002, KIA 2.1.5 (2.9)
Perform Daily Thermal Limit Surveillance N1-RESP-1A, KIA 2.2.12 (3.7)
Perform CRO Firefighting Checklist Emergency Procedures/Plan N, S EPIP-EPP-28, KIA 2.4.27 (3.4)
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; s 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: Nine Mile Point Unit 1 Date of Examination: March 2015 Examination Level: SRO Operating Test Number: LC1 13-01 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Review Reactor Water Level Instrument Checks and Conduct of Operations P,D, R Determine Technical Specification Impact 2013 NRC N1-ST-DO, KIA2.1.7(4.7)
Determine Personnel Overtime Availability Conduct of Operations M,R CNG-SE-1.01.1002, KIA2.1.5 (3.9)
Perform Daily Thermal Limit Surveillance Equipment Control D, R N1-RESP-1A, KIA 2.2.12 (4.1)
Determine Radiation Controls - Emergency Exposure Radiation Control D,R for Local MSIV Closure GAP-RPP-07, CNG-EP-1.01-1014, KIA 2.3.4 (3.7)
Classify an Emergency Event and Perform Initial Emergency Procedures/Plan M,R Notifications CNG-EP-1.01-1013, KIA 2.4.41 (4.6)
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 (2! 1)
(P)revious 2 exams (::; 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Nine Mile Point Unit 1 Date of Examination: March 2015 Exam Level: RO/SR0-1/SRO-U Operating Test No.: LC1 13-01 NRC Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function
- a. Place SOC in service, Pump trips D,A,S, L 4
KIA 205000 A4.01 (3.7/3.7), N1-0P-4
- b. Vent the Drywell Prior to Personnel Entry <212 KIA 223001 A4.03 (3.4/3.4), N1-0P-9 N,S,L 5
- c. Partial MSIV Stroke test P,S, D 3
KIA 239001 A4.01 (4.2/4.0), N1-ST-Q26 NRC 2010
- d. Transfer House Loads from Reserve to Normal N,S 6
KIA 262001 A4.04 (3.6/3.7) N1-0P-30
- e. Swap RBV Fans 11to12, Fan 12 low amps D,S,A 9
KIA 288000 A4.01 (3.1/2.9), N1-0P-10
- f. Half Scram, Bypass LPRM to APRM, Reset half scram M,S 7
KIA 215005 A4.04 (3.2/3.2), N1-0P-38C
D,S 2
KIA 204000 A4.01 (3.1/3.0), N1-0P-3
KIA 211000 A1.08 (3.7/3.8), N1-EOP-HC In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
DFP Start with No Control Power KIA 286000 A3.01 (3.4/3.4)
D,R 8
- j. Perform OATC Actions for Control Room Evacuation-Hot EOG M,A,R 6
KIA 295003 AA1.02 (4.2/4.3)
- k. Initiate ECs from the RSP, Level Control Fails D,A,E,R, 7
KIA 295016 AA1.09 (4.0/4.0) N1-SOP-21.2 EN All RO and SRO-I 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator Pairings:
A then B. Start with SRO-U on B.
CandD E then F End with SRO-U on E G alone H alone Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2-3
- S9/:S8/:S4
<:1/<:1/<=1
- I -
I
<=1 (control room system)
<:1/<:1/<:1
<:2/<:2/<:1 s 3 Is 3 Is 2 (randomly selected)
<=1/<:1/<=1
Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-2 Op-Test No.: LC1 13-01 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 50-55% power. Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.
Turnover: Start Circulating Water pump 11. Raise Reactor power with Recirculation flow.
Event Malf.
Event Event No.
No.
Type*
Description N-Start Circulating Water Pump 11 1
N/A
N/A
NM36A I-SRO Recirculation Flow Unit Fails Upscale ARP F2-2-6, Technical Specifications 4
EC03B I-BOP, Emergency Condenser 12 Inadvertent Initiation SRO ARP K1-1-5, N1-0P-13, Technical Specifications Fuel Failure 5
RX01 C-All N1-SOP-25.2, N1-SOP-1.1, N1-SOP-1 6
MS01 M-All Main Steam Line Break in Turbine Building N1-EOP-2, N1-EOP-6 ED27 Powerboard 12 Fails to Fast Transfer and Feedwater Pump 11 7
C-BOP Trips FW03A N1-SOP-30.2, N1-SOP-1 MS13A Two MSIVs Fail to Close 8
C-All MS13C N1-EOP-6, N1-EOP-8 9
Override C-ATC Turbine Building Ventilation Exhaust Fan Trips N1-EOP-6, N1-EOP-8 (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior
Facility: Nine Mile Point Unit 1 Scenario No.: NRC-2 Op-Test No.: LC113-01
- 1. Total malfunctions (5-8) 7 Events 3, 4, 5, 6, 7, 8, 9
- 2. Malfunctions after EOP entry (1-2) 3 Events 7, 8, 9
- 3. Abnormal events (2-4) 3 Events 3, 4, 5
- 4. Major transients (1-2) 1 Events
- 5. EOPs entered/requiring substantive actions (1-2) 2 N1-EOP-2, N1-EOP-6
- 6. EOP contingencies requiring substantive actions (0-2) 1 N1-EOP-8
- 7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:
CT Given fuel failure causing Main Steam Line radiation levels to approach and/or exceed 3.75 times normal full power background, scram the Reactor, in accordance with N1-SOP-25.2.
CT Given an un-isolable primary system discharging outside of primary and secondary containments and off-site release rate approaching the General Emergency level, perform an RPV Slowdown, in accordance with N1-EOP-6.
Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-3 Op-Test No.: LC1 13-01 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 85% power. Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.
Turnover: Shutdown Condensate Pump 11 for maintenance due to a motor oil leak and place in Pull-To-Lock. Then Perform a Rod Sequence Exchange.
Event Malf.
Event Event No.
No.
Type*
Description 1
N/A N-BOP, Condensate Pump 11 shutdown SRO N1-0P-15A, Tech Spec 3.1.8 2
N/A R-ATC, Rod Sequence Exchange SRO N1-0P-5, RMI I-BOP, Main Steam Line Radiation Monitor Failure 3
RM51A SRO ARP F1-2-7, Tech Spec 3.6.2.h 4
CW19 I-BOP, RBCLC Temperature Controller fails to minimum cooling SRO N1-SOP-11.1 RP01B C-ATC, RPS MG Set trip 5
SRO N1-0P-48, N1-SOP-16.1, Tech Spec 3.6.12 RD34 Instrument air leak, Reactor scram required 6
C-All IA01 N1-SOP-20.1, N1-SOP-1 ATWS 7
RD33 M-All N1-EOP-2, N1-EOP-3 Feedwater Isolation Valves 11 and 12 fail to isolate 8
Overrides C-All N1-EOP-3 (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior
Facility: Nine Mile Point Unit 1 Scenario No.: NRC-3 Op-Test No.: LC113-01
- 1. Total malfunctions (5-8) 6 Events 3, 4, 5, 6, 7, 8
- 2. Malfunctions after EOP entry (1-2) 2 Events 7, 8
- 3. Abnormal events (2-4) 4 Events 3, 4, 5, 6
- 4. Major transients (1-2) 1 Event 7
- 5. EOPs entered/requiring substantive actions (1-2) 1 N1-EOP-2
- 6. EOP contingencies requiring substantive actions (0-2) 1 N1-EOP-3
- 7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:
CT-1.0 Given lowering CRD system air pressure, the crew will insert a manual reactor scram before control rods begin drifting, in accordance with N1-ARP-F3 and/or N1-SOP-20.1.
CT-2.0 Given a failure of the reactor to scram with power above 6% and RPV water level above -41 inches, the crew will terminate and prevent all injection except boron and CRD, in accordance with N1-EOP-3.
CT-3.0 Given a failure of the reactor to scram with power above 6%, the crew will lower reactor power by inserting control rods or injecting boron, in accordance with N1-EOP-3.
Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-4 Op-Test No.: LC1 13-01 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 90% Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.
Turnover: Recirc Pump 11 MG set has been repaired and is ready to be returned to service. Lower reactor power per the RMI and restore 11 recirc pump to service.
After starting Recirc Pump 11 MG set and placing in service, operate it for one hour while maintenance takes readings before returning to 100% power.
Event Malf.
Event Event No.
No.
Type*
Description 1
N/A R-ATC, Lower power to permit returning Recirc Pump 11 to service SRO 2
N/A N-BOP, Restore Recirc Pump 11 to service SRO 3
HV01A C-BOP, Reactor Building Exhaust Fan 11 trips. Requires RBEVS initiation.
SRO L 1-3-4, L 1-1-5, N1-EOP-5, N1-0P-10, Technical Specifications RR65E RR pump 15 Blind Controller failure and delayed pump trip 4
I-All RR09E N1-SOP-1.3, Tech Spec 3.1.7 EC01 Steam leak inside Drywell 5
M-All N1-EOP-2, N1-EOP-4 6
PC10 C-All Failed open vacuum breaker N1-EOP-4 FW28A HPCI fails to initiate, Core Spray fails to auto-inject 7
FW28B C-BOP, N1-EOP-2 SRO CS07 CT01A C-ATC, Containment Spray pump 111 trips 8
SRO N1-EOP-8 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Facility: Nine Mile Point Unit 1 Scenario No.: NRC-4 Op-Test No.: LC113-01
- 1. Total malfunctions (5-8) 6 Events 3, 4, 5, 6, 7, 8
- 2. Malfunctions after EOP entry (1-2) 3 Events 6, 7, 8
- 3. Abnormal events (2-4) 2 Events 3 &4
- 4. Major transients (1-2) 1 Event 5
- 5. EOPs entered/requiring substantive actions (1-2) 2 N1-EOP-2, N1-EOP-4
- 6. EOP contingencies requiring substantive actions (0-2) 1 N1-EOP-8
- 7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:
CT Given a LOCA in the Drywell and a failure of HPCI to initiate, the crew will inject with preferred and alternate injection systems to restore and maintain RPV water level above -84 inches, in accordance with N1-EOP-2.
CT Given a LOCA in the Drywell and degraded Containment Spray capability, the crew will execute N1-EOP-8, RPV Slowdown, when it is determined Torus pressure cannot be maintained below the Pressure Suppression Pressure limit, in accordance with N1-EOP-4.
Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-5 Op-Test No.: LC1 13-01 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 100% power. Reactor Building Exhaust fan 12 is out of service for maintenance. Containment Spray Pump 112 is out of service for maintenance.
Turnover: Remove Line 4 from service.
Event Malf.
Event Event No.
No.
Type*
Description N-Remove Line 4 from Service 1
N/A
SRO N1-SOP-1.4, N1-SOP-1.1, Technical Specifications R-ATC C-Powerboard 16A Electrical Fault 3
ED12A
- BOP, SRO ARP L4-3-6, N1-EOP-4 CW04A 4
CW04B C-All All RBCLC Pumps Trip CW04C N1-SOP-11.1, N1-SOP-1, N1-EOP-2 FW03A 5
FW03B C-All Feedwater Pumps Fail to Operate N1-EOP-2 FW06 CU01 Coolant Leak Inside Primary Containment 6
M-All EC01 N1-EOP-2, N1-EOP-4 VICP201 I-All Fuel Zone Level Instrument Sporadic Indication 7
68169 N1-EOP-2, N1-EOP-7 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Facility: Nine Mile Point Unit 1 Scenario No.: NRC-5 Op-Test No.: LC113-01
- 1. Total malfunctions (5-8) 6 Events 2, 3, 4, 5, 6, 7
- 2. Malfunctions after EOP entry (1-2) 3 Events 5, 6, 7
- 3. Abnormal events (2-4) 3 Events 2, 3, 4
- 4. Major transients (1-2) 1 Event&
- 5. EOPs entered/requiring substantive actions (1-2) 2 N1-EOP-2, N1-EOP-4
- 6. EOP contingencies requiring substantive actions (0-2) 1 N1-EOP-7
- 7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:
CT Given an inadvertently open ERV at power, close the ERV or insert a manual scram prior to Torus temperature exceeding 110°F, in accordance with N1-SOP-1.4.
CT Given a LOCA in the Drywell, initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP-4.
CT Given the plant with RPV water level unknown, execute N1-EOP-7, RPV Flooding, in accordance with N1-EOP-2.