ML12353A446

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Final - Outlines (Folder 3)
ML12353A446
Person / Time
Site: Salem  PSEG icon.png
Issue date: 11/20/2012
From: Parker E
Public Service Enterprise Group
To: David Silk
Operations Branch I
Jackson D
Shared Package
ML12191A056 List:
References
TAC U01859, 50-272/12-301, 50-311/12-301
Download: ML12353A446 (23)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Fi!~i1iW: Salem Printed: 12/05/2012 Date Of Exam: 12/03/2012 RO KJA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 Ai A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 -' 3 18 0 0 0 Emergency 2 2 2 1 2 1 1 9 0 0 0

& N/A NIA Abnormal Tier Plant Totals 5 5 4 5 4 4 27 0 0 0 Evolutions 1 3 3 3 "-' 3 2 3 2 28 0 0 0 2.

I

~R 2 1 1 1 1 1 1 1 10 0 0 0 0 Plant Systems Tier 4 3 4 4 4 3 4 3 3 38 0 0 0 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And Abilities Categories 10 0 2 3 2 -' 0 0 0 0 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the 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 KlAs 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) KlAs in Tiers ., 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 KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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-onlyexams.
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 KlAs that are linked to 10 CFR 55.43.

12/05/2012 2:09:15 pm

PWR RO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-40l-2 E/APE #! Name! Safety Function Kl K2 K3 Al ~i ig~ KA Topic Imp. Points 1.\ I'ii~r~:;(

000007 Reactor Trip - Stabilization - X liii,!ilill:ll EK 1.06 - Relationship of emergency 3.7 1 Recovery 11 Iji: feedwater flow to SIG and decay heat I." removal following reactor trip 0000 II Large Break LOCA / 3 X EK2.02 - Pumps 2.6* 1 000015/0000 17 RCP Malfunctions / 4 X I:*> AK2.IO - RCP indicators and controls 2.8* 1 000022 Loss of R,'( Coolant Makeup / 2 " .. AKl.03 - Relationship between 3.0 1 X I,;;*

Ii, charging flow and PZR level 000026 Loss of Component Cooling Water / X t*;,**,**; AK3.02 - The automatic actions 3.6 1 8 (alignments) within the CCWS resulting

...,.... from the actuation of the ESFAS 000027 Pressurizer Pressure Control System X AA 1.0 I - PZR heaters, sprays, and 4.0 I I.

Malfunction / 3 "',., .

PORVs 000029 A TWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1

.", .. disconnects 000038 Steam Gen. Tube Rupture / 3 2.4.8 - Knowledge of how abnormal 3.8 1

.. ,.. '.' I",.'

.... ,",. I operating procedures are used in

.'*'i conjunction with EOPs .

.i'.", ,.

000054 Loss of Main Feedwater 14 .,'il><X 2.4.46 - Ability to verity that the alarms 4.2 1 I,,:' are consistent with the plant conditions.

I"""

000055 Station Blackout / 6 X EA2.03 - Actions necessary to restore 3.9 1 power 000056 Loss of Off-site Power 1 6 X "'"", AK3.02 - Actions contained in EOP for 4.4 1

'. I***i.i, loss of offsite power 000057 Loss of Vital AC Inst. Bus 16  :::.:.*.... AA2.03 - RPS panel alarm annunciators 3.7 1 and trip indicators 000065 Loss ofInstrument Air / 8 P .. ~...., 2.3 .14 - Knowledge of radiation or contamination hazards that may arise 3.4 I during normal, abnormal, or emergency conditions or activities.

000077 Generator Voltage and Electric Grid X AA1.02 - Turbine / generator controls 3.8 I Disturbances I 6 W1E04 LOCA Outside Containment / 3 X EA 1.1 - Components, and functions of 4.0 1 I*,'* . ,* ' * * * ** control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and

HII
manual features W1E05 Inadequate Heat Transfer - Loss of X 1>"'0:' EK3.2 - Normal, abnormal and 3.7 I Secondary Heat Sink I 4

.;;;. 1::11 omecgenoy opemting proceduros associated with Loss of Secondary Heat Sink I,v!:~r Ii,:;*******

Ii I:~~

12/05/2012 2:08:47 pm

PWR RO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 1 Form ES-401-2 EIAPE # I Name / Safety Function Kl K2 K3 Al A2  ::G KA Topic Imp. Points

. ,i.*****

WlEll Loss of Emergency Coolant Recire.! r~;XL EA2.2 - Adherence to appropriate 3.4 I 4 procedures and operation within the

'ti' limitations in the facility's license and

.; ......... amendments WlE12 - Steam Line Rupture - Excessive X .i EKl.1 - Components:, capacity, and 3.4 1 Heat Transfer / 4 ......* function of emergency systems KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 12/05/2012 2:08:47 pm 2

PWR RO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier I / Group 2 Form ES-401-2 E/APE # I Name I Safety Function Kl K2 K3 Al A2 IG KA Topic Imp. Points 000003 Dropped Control Rod / 1 X AK2.05 - Control rod drive power 2.5 1 supplies and logic circuits 000074 Inad. Core Cooling 14 X EK3.04 - Tripping RCPs 3.9 1 000076 High Reactor Coolant Activity! 9 X .. AAl.04 - Failed fuel-monitoring 3.2 1 equipment W/E02 SI Termination 13 X EK2.1 - Components, and functions of 3.4 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and

.. ::;>. 1(****;> manual features W/E03 LOCA Cooldown - Depress. 14 X .';.: .;.:;'.. EK1.3 - Annunciators and conditions 3.5 1

,'" indicating signals, and remedial actions associated with the LOCA Cooldown
  • iii'::,:;; *. ';':;"i:ii; and Depressurization W/EOS RCS Overcooling - PTS / 4 X EK1.2 - Normal, abnormal and 3.4 1
  • (i:*:f, ,;;::::::" emergency operating procedures associated with Pressurized Thermal Shock WIEIO Natural Circ. / 4 X EA 1.2 - Operating behavior 3.6 I characteristics of the facility WIE 15 Containment Flooding I 5 X 2.1.45 - Ability to identify and interpret 4.3 1

.... diverse indications to validate the response of another indication.

W/E16 High Containment Radiation 19 X EA2.2 - Adherence to appropriate 3.0 1 procedures and operation within the limitations in the facility's license and amendments KIA Category Totals: 2 2 I 2 I 1 Group Point Total: 9 12/0512012 2:08:53 pm

PWR RO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Plant Systems - Tier 2 I Group 1 Form ES-401-2 Sys/Evol # I Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K6.02 - RCP seals and seal 2.7 1 water supply 003 Reactor Coolant Pump X K5.03 - Effects ofRCP 3.1 1 shutdown on T-ave.,

including the reason for the unreliability ofT-ave. in the shutdown loop 004 Chemical and Volume Control X i.*. K4.16 - Temperature at 2.6 1 which the temperature control valve automatically diverts flow from the

'.' demineralizer to the VCT; reason for this diversion 004 Chemical and Volume Control X A2.18 - High VCT level 3.1 I 005 Residual Heat Removal X r 3.4* 1 I

005 Residual Heat Removal X K4.10 - Control ofRHR 3.l 1 heat exchanger outlet flow 006 Emergency Core Cooling X K3.01 - RCS 4.1

  • 1 006 Emergency Core Cooling X K6.l0 - Valves 2.6 I 007 Pressurizer Relief/Quench X

........ K5.02 - Method offorming 3.1 I Tank a steam bubble in the PZR 008 Component Cooling Water X K4.02 - Operation of the 2.9 1 surge tank, including the associated valves and

............... controls X ....... K2.01 - PZR heaters 3.0 1 010 Pressurizer Pressure Control 012 Reactor Protection X A3.01 - Individual channel 3.8 1 013 Engineered Safety Features X A4.03 - ESFAS initiation 4.5 I Actuation ."

I:..

022 Containment Cooling X A 1.02 - Containment 3.6 1 pressure 026 Containment Spray 2.4.31 - Knowledge of 4.2 1 annunciator alarms, indications, or response I procedures.

":.. K5.08 039 Main and Reheat Steam X 1:51 ... Effect of steam removal on reactivity 3.6 1 039 Main and Reheat Steam  :-J X 2.1.28 - Knowledge of the 4.1 1 purpose and function of

. major system components

%? , and controls.

059 Main Feedwater X KI.05 - RCS 3.1

  • 1 059 Main Feedwater X A1.07 Feed Pump speed, 2.5* 1 including normal control speed for lCS 12/05/2012 2:08:59 pm

PWR RO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Plant Systems - Tier 2 I Group 1 Form ES-401-2 I

SyslEvol # I Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 061 Auxiliary/Emergency X Kl.03 - Main steam system 3.5 1 Feedwater I'}

061 Auxiliary/Emergency X K3.02 - S/G 4.2 1 Feedwater I, 062 AC Electrical Distribution X .'.. " A 1.03 - Effect on 2.5 I I" instrumentation and controls I'",;

of switching power supplies 063 DC Electrical Distribution X K2.0 I - Major DC loads 2.9* I 064 Emergency Diesel Generator X I******,** Kl.03 - Diesel fuel oil 3.6 I supply system 073 Process Radiation Monitoring X ", K3.01- Radioactive effluent I 3.6 1 releases 076 Service Water :X A2.02 - Service water 2.7 1

header pressure 078 Instrument Air "

X ' A3.0) - Air pressure 3.1 1 103 Containment X .... A4.09 - Containment 3.1

  • 1 I"*' vacuum system KIA Category Totals: 3 2 3 3 3 2 3 2 2 3 2 Group Point Total: 28 12/05/2012 2:08:59 pm 2

PWR RO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Plant Systems - Tier 2 1 Group 2 Form ES-401-2 SyslEvol # I Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points X  !.. *. . . **.. Al.Ol- T-ave. and no-load 3.8 I 001 Control Rod Drive

...... I***** T-ave oII Pressurizer Level Control X ...... K6.04 - Operation of PZR 3.1 1 level controllers 015 Nuclear Instrumentation X A2.02 - Faulty or erratic 3.1 I operation of detectors or compensating components iiiiiii I 017 In-core Temperature Monitor X K5.03 - Indication of 3.7 1 superheating 027 Containment Iodine Removal X K2.01 - Fans 3.1

  • 1 033 Spent Fuel Pool Cooling

- X K4.03 - Anti-siphon devices 2.6 1 041 Steam Dump/Turbine Bypass X K3.02 - RCS 3.8 1 Control 045 Main Turbine Generator X ..

A3 .11 - Generator trip  ! 2.6* 1 068 Liquid Radwaste X .'

K1.07 - Sources of liquid 2.7 1

. wastes for LRS X A4.02 - Fire detection 3.5 1 086 Fire Protection I. panels KIA Category Totals: 1 1 1 1 1 1 1 1 1 0 Group Point Total: 10 12/05/2012 2:09:04 pm

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 12/05/2012 Facility: Salem Form ES-401-3 Generic Category KA Topic Conduct of Operations 2.1.28 Knowledge of the purpose and function of major 4.1 I system components and controls.

2.1.40 Knowledge of refueling administrative 2.8 1 req uirements.

Category Total: 2 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3.7 1 2.2.20 Knowledge of the process for managing 2.6 1 troubleshooting activities.

2.2.44 Ability to interpret control room indications to 4.2 1 verity the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Category Total: 3 Radiation Control 2.3.14 Knowledge of radiation or contamination hazards 3.4 1 that may arise during normal, abnormal, or emergency conditions or activities.

2.3.15 Knowledge of radiation monitoring systems, such 2.9 I as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Category Total: 2 Emergency ProcedureslPlan 2.4.3 Ability to identity post-accident instrumentation. 3.7 1 I 2.4.19 Knowledge of EOP layout, symbols, and icons. 3.4 1 2.4.27 Knowledge of "fire in the plant" procedure. 3.4 1 Category Total: 3 Generic Total: 10 12/05/2012 2:09:10 pm

ES-401 PWR Examination Outline Form ES-401-2 Fa~iIi~: Salem Printed: 12/05/2012 Date Of Exam: 12/03/2012 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K4 IK5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 .:J 6 Emergency 2 0 0 0 0 0 0 0 2 2 4

& N/A N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 2.

Plant Systems 2

1 Tier Totals 0

0 0

0 0

0 0

0 0

n0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

3 I

5 2

2 1

.)

5 3

8 1 2 3 4 1 2 3 4

3. Generic Knowledge And Abilities Categories 0 7 0 0 0 0 2 2 1 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 (Le., except for one category in Tier 3 of the SRQ..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 SRQ..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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of E8-401 for guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRQ..only portions, respectively.
6. Select SRO topiCS for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs 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 KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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 SRQ..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 E8-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

12/05/2012 2:15:06 pm

PWR SRO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group I Form ES-401-2 E/APE # I Name I Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - ~"! 2.1.20 - Ability to interpret and execute 4.6 I Recovery II " '. procedure steps.

000009 Small Break LOCA / 3 ,,: i::l:~ X 2.2.44 - Ability to interpret control 4.4 1 room indications to verity the status and operation of a system, and understand

'I' how operator actions and directives

!i:

,"~'oiL"~, affect plant and system conditions.

'~\ I;:,

000025 Loss ofRHR System 14 AA2.05 - Limitations on LPI flow and 3.5* 1 I'i temperature rates of change 000054 Loss of Main Feedwater 14 X AA2.05 - Status of MFW pumps, 3.7 1 regulating and stop valves 000062 Loss of Nuclear Svc Water 14 X 2.4.6 - Knowledge of EOP mitigation 4.7 1

':"~y I> strategies.

W/E12 - Steam Line Rupture - Excessive )~I:~:*: EA2.1 - Facility conditions and 4.0 1 Heat Transfer / 4 selection of appropriate procedures Ii during abnormal and emergency KIA Category Totals: 0 0 0 012

't. 3 operations Group Point Total: 6 12/05/2012 2:14:40 pm

PWR SRO Examination Outline Printed: 12!0512012 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name I Safety Function Kl K2 K3 At A2 G KA Topic Imp. Points 000001 Continuous Rod Withdrawal! 1 X AA2.03 - Proper actions to be taken if 4.8 1

.i.~ automatic safety functions have not

, taken place 000028 Pressurizer Level Malfunction 12 X 2.2.43 - Knowledge of the process used 3.3 1

...... to track inoperable alarms .

000069 Loss of CTMT Integrity 1 5

..... AA2.01 - Loss of containment integrity 4.3 1 I"X I 4.1 W IE 16 High Containment Radiation I 9 X 2.4.30 - Knowledge of events related to 1 system operation/status that must be reported to internal organizations or external agencies, such as the State, the it NRC, or the transmission system operator.

I KIA Category Totals: 0 0 0 0 2 :2 Group Point Total: 4 12/05/2012 2:14:45 pm

PWR SRO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 401 Plant Systems - Tier 2 I Group I Form ES-401-2 SyslEvol # I Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp_ Points 005 Residual Heat Removal X A2.02 - Pressure transient 3.7 1

" protection during cold shutdown 012 Reactor Protection X A2.0 1 - Faulty bistable 3.6 1 operation 026 Containment Spray X 2.4.50 - Ability to verifY 4.0 1 system alarm setpoints and operate controls identified in the alarm response manual.

039 Main and Reheat Steam X A2.04 - Malfunctioning 3.7 I

... steam dump 103 Containment I***

X 2.4.22 - Knowledge of the 4.4 1

. ... bases for prioritizing safety functions during

... abnormal/emergency operations.

KIA Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 12/05/2012 2:14:50 pm

I'WR SRO Examination Outline Printed: 12/05/2012 Facility: Salem ES - 40] Plant Systems - Tier 2 / Group 2 Form ES-401-2 SyslEvol # / Name KI :;- K3 K4 K5

~ Al A2 A3 A4 G KA Topic Imp. Points

~:

016 Non-nuclear Instrumentation " 2.2.3 7 - Ability to determine 4.6 1 operability and/or

, availability of safety related equipment.

034 Fuel Handling Equipment X .

A2.0 1 - Dropped fuel 4.4 I

.:i.I element 086 Fire Protection X .' A2.03 - Inadvertent 2.9 1 actuation of the FPS due to circuit failure or welding KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 J Group Point Total: 3 12/05/2012 2:14:55 pm

Generic Knowledge and Abilities Outline (Tier 3) 1>WR SRO Examination Outline Printed: 12/05/2012 Facility: Salem Form ES-401-3 Generic Category KA Topic Conduct of Operations 2.1.32 Ability to explain and apply system limits and 4.0 1 precautions.

2.1.35 Knowledge of the fuel-handling responsibilities 3.9 1 ofSROs.

Category Total: 2 Equipment Control 2.2.11 Knowledge of the process for controlling 3.3 1 temporary design changes.

2.2.37 Ability to determine operability and/or 4.6 1 availability of safety related equipment.

Category Total: 2 Radiation Control 2.3.13 Knowledge of radiological safety procedures 3.8 1 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Category Total: 1 Emergency Procedures/Plan 2.4.26 Knowledge of facility protection requirements, 3.6 I including fire brigade and portable fIre fighting equipment usage.

2.4.29 Knowledge of the emergency plan. 4.4 1 Category Total: 2 Generic Total: 7 12/05/2012 2:15:00 pm

ES-401 Record of Rejected K/As 11-01 NRC Exam Form ES-40 1-4 Tier/Group Reason for Rejection Selected KIA R02/2 002 K4.09 Salem no Randomly automatically replaced with System 068,

~iquid Radwaste system, Kl.07.

R021I 026 K4.08 Containment spray system has no suction auto swapover feature, it is part of the RHR system.

~andoml~ automatically replaced with System 026 Containment Spra~ system, 2.4.31.

RO 2/1 061 Gen 2.2.41 "Ability to obtain" drawings N/A to written exam. Randomly automatically replaced with System 01 RPS A3.0l.

RO 2/1 064 Gen 2.1.19 to use Plant Computer" NI A to written exam. Randomly automatically replaced with sy§tem 064, EDG system, Kl.03.

R02/1 086 Gen 1.13 Knowledge of requirements for controlling vital area access not related to Fire Protection system.

Randomly automatically replaced with system 086, Fire Protection system A4.02.

RO 1/2 024 Gen 2.1.13 Knowledge of requirements for controlling vital area access not related to Emergency Boration.

_Randomly automatically re]2laced with 003 Dropped Control Rod, AK2.0S. (see next deletion also)

ROII2 003 AK2.03 Salem does not have a metroscope associated with Rod Control. Randomly automatically replaced with---

AK2.0S.

ROII1 054 Gen 1.17 "Ability to make accurate, clear, and concise verbal reports" more suited to operating exam eVi!luation. Randomly automaticall~ re]2laced with 054 2.4.46.

RO 111 062 Gen 2.1.15 "Knowledge of administrative requirements such as standing orders, night orders ..." not applicable to loss of Nuclear Service Water. Randomly automatically replaced with 065 Loss ofInstrument 2.3.14.

ROllI 025 AAI.09 KiA overlapped from previous 2 exams. Deleted per NRC instruction. with 077 Generator Voltage and Electric Grid Disturbances, AA1.02. This IvA was not sampled on the pre~ious 2 exams.

RO 111 008 AKl.01 KiA overlapped from previous 2 exams. Deleted per NRC instruction. Randomly replaced with El2 Uncontrolled Depressurization of All Steam Generators, EK1.1. This IvA was not sampled on the 2 previous exams.

SRO 211 010 A2.03 IvA overlapped from previous 2 exams. Deleted per NRC instruction. Randomly replaced with 005 Residual Heat Removal A2.02. This KIA was not sam led on the 2 revious exams.

SR03 2.3.4 KIA overlapped from previous 2 exams. Deleted per NRC instruction. Randomly replaced with 2.3.13. (Was sampled on the 08-01 RO exam.)

ES-401, Page 27 of 33 Page 1 of 2

ES-401 Form ES-401-4 SR03 2.1.6 to manage the control room crew during plant transients" more suited to operating exam

~~~~~~~~~~~~~~~~~----1--------I evaluil QI1' Randomly automatically replaced with 2.1.32 ti SRO 1 Oen 2.2.5 Knowledge of process for making design or operating changes to the facility NA to Loss of Emergency Coolant Recirculation. Randomly automatically replaced with PZR Vapor Space Accident 008, 2.1.4. (see next deletion also) f---S-R-O-l/-l-+--0-0-8-0-e-n-2-.l-.-4---l1 Incli~icl~al Licensed Operator Responsibilities NA to PZR Vapor Space Accident. Randomly aut()l11atically replaced with 009 Small Break LOCA, 2.2.44.

SRO 111 E06 Gen 2.2.6 Knowledge of the process for making changes to procedures NA to Degraded Core Cooling. 028 PZR Level Control Malfunctions 2.2.43 SRO 212 029 Gen 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing ....N A to Containment Purge. Randomly automatically replaced with System 016 Non-Nuclear ES-401, Page 27 of 33 Page 2 of 2

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SALEM Date of Examination: 11/26/12 Examination Level:

  • RO SRO Operating Test Number: 11-01 NRC Administrative Describe activity to be performed Type Topic (See Note)

Code*

Calculate Shutdown Margin Conduct of R,M 2.1..25 Ability to interpret reference materials such as graphs, curves, tables, etc ..

Operations RO 3.9 Perform Manual AFD calculation.

Conduct of R,N 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, Operations and reports. RO 3.6 Perform ST.CVC-01 0 Borated Water Sources (Simulator)

Equipment Control S,N 2.2.37 Ability to determine operability and/or availability of safety related equipment. RO 3.6 Perform radiation dose calculation and determine if any Dose Limit will be exceeded.

Radiation Control R,M,P 2.~\.4 Knowledge of radiation exposure limits under normal and emergency conditions. RO 3.2 Emergency N/A Procedures / Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes and 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 Administrative Outline Form ES-301-1 Facility: SALEM Date of Examination: 11/26/12 Examination Level: RO

  • SRO Operating Test Number: 11-01 NRC Administrative Describe activity to be performed Type I Topic (See Note)

Code*

Conduct of J ReView: completed surveillance to demonstrate Operability of 21 CFCU R,D 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Operations

  • SRO-4.2 Direct Actions for Spent Fuel Movement (Determine work which would require Conduct of R,D suspension of Fuel Movement)

Operations

  • 2.1A2 Knowledge of new and spent fuel movement procedures. SRO-3A Review an OTSC to an Implementing Procedure Equipment Control R,M 2.2.6 Knowledge of the process for making changes in procedures. SRO 3.6 Determine required actions upon Radioactive Effluent Monitor failure Radiation Control R,N 2.3.11 Ability to control radiation releases SRO 4.3 (based on Pilgrim 1/2011 NRC I Exam SRO A3)

~

Emergency Classify Emergency I Non-Emergency Events, and complete the ICMF.

S,M,P Procedures 1 Plan 2.4.29 Knowledge of the Emergency Plan SRO 4.4

, :(

  • NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unle~ they are retaking only the administrative topics, when 5 are required.
  • Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)ireGt 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 \/o.=".... rTl Outline Form ES-301-2 Facility: SALEM Date of Examination: 11/26/2012 Exam Level: SRO-I SRO-U Operating Test No.: 11-01 NRC Control Room Systems@ (8 for RO; 7' for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function i a) Perform a Control Rod Operability Verification.

001 A4.03 RO-4.0 SRO-3.7 A,D,S 1 b) Perform ECCS Accumulator check valve forward flow surveillance (S2.0P-ST.SJ-0006) 006 A4.02, RO-4.0, SRO 3.8 N,A,L,S,EN 2 I~Pressure Malfunction (Failed open Pressurizer Spray Valve) 010 A4.01, RO 3.7 SRO 3.5 A,D,P,L,S 3 in Shutdown Cooling Mode APE 025 AA 1.09 RO-3.2 SRO 3.1 D,L,S 4(pri) e) TCAF Turbine Trip <P-9 (MT ASO trip)

Generic 2.4.31 RO-4.2 SRO-4.1 M,A,P,S 4(sec) f) Adjust PZR Relief Tank (PRT) Level and Pressure 007 A4.04 RO-2.6 SRO-2.6 D,S 5 g) Respond to a loss of Control Air APE 065 AA2.06 RO 3.6 SRO 4.2 A,N,S 8 h) Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System (and respond to High Radiation with failure of A,D,S 9 2WL51 to automatically shut.) 068 A4.03 RO-3.9, SRO-3.8 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i i) Locally Borate the RCS I APE 068 AA1.08 RO- 4.2 SRO- 4.2 D,E,R 2 j) Start and synch EDG Start and synchronize an EDG 064 A2.09 RO-3.1 SRO-3.3 D,R 6 k) Start the SSO Air Compressor Generic 2.1.23 RO-4.3 SRO-4.4 D,E,P 8

@ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; ailS 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 SRO-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C}ontrol room

{D)irect from bank  :::9 I ::: 8 1:::4 (E)mergency or abnormal in-plant ~1 I ~ 1 /~1 (EN)gineered safety feature - I - I ~ 1 (control room system)

(L)ow-Power I Shutdown ~1 / ~11 ~1 (N)ewor (M)odified from bank including 1 (A) ~2 I ~2 /~1 (P)revious 2 exams  :::3 I :::3 I ::: 2 (randomly selected)

(R)CA ~1 I ~ 1/ ~ 1 (S)imulator

ES-301 Control Room _'<C>lrTl Outline Form ES-301-2 Facility: SALEM Date of Examination: 1112612012 Exam Level: RO ISRO-II SRO-U Operating Test No.: 11-01 NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code* Safety Function a) Perform a Control Rod Operability Verification.

001 A4.03 RO-4.0 SRO-3.7 A,D,S 1 i~

b) Perform ECCS Accumulator check valve forward flow surveillance II (S2.0P-ST.SJ-0006) 006 A4.02, RO-4.0, SRO 3.8 N,A,L,S,EN 2 c) TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve) 010 A4.01, RO 3.7 SRO 3.5 A,D,P,L,S 3 d)

I I~ F Turbine Trip <P-9 (MT ASO trip)

Generic 2.4.31 RO-4.2 SRO-4.1 M,A,P,S 4(sec) t PZR Relief Tank (PRT) Level and pressure 007 A4.04 RO-2.6 SRO-2.6 D,S 5

!:jJ Respond to a loss of Control Air APE 065 AA2.06 RO 3.6 SRO 4.2 A,N,S 8 h) Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System (and respond to High Radiation with failure of A,D,S 9 2WL51 to automatically shutJ 068 A4.03 RO-3.9, SRO-3.8 stems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Locally Borate the RCS APE 068 AA1.08 RO- 4.2 SRO- 4.2 D,E,R 2 I

Start and synch EDG Start and synchronize an EDG 064 A2.09 RO-3.1 SRO-3.3 D,R 6

~P k) Start the SBO Air Compressor Generic 2.1.23 RO-4.3 SRO-4.4 I 8

@ 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:

- Criteria for RO I SRO-II SRO-U

{A)lternate path 4-6/ 4-6 1 2-3 (C)ontrol room (D)irect from bank .::: 9 1 .:::8 I.::: 4 (E)mergency or abnormal in-plant >1 I .::: 1 I.::: 1 (EN)gineered safety feature - I - 1 .::: 1 (control room system)

(L)ow-Power I Shutdown .:::1 I ':::1 1 .:::1 (N)ewor (M)odified from bank including 1 (A) .::: 2 I .::: 2 I.::: 1 (P)revious 2 exams .:::3/.:::3/.:::2 (randomly selected)

(R)CA .:::1 1 .::: 11 .::: 1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-1 Op-Test No.: 11-01 NRC Examiners: Operatol's:

Initial Conditions: 100% power, EOL. PZR Pressure channel II is O/S for calibration.

Turnover: Maintain current power. Perform 1ST Room Cooler Valves Modes 1-6 lAW S2.0P-ST.SW 0014.

Event Malf. No. Event Event Type*

No. Description N

1 Safety Related Room cooler surveillance (TS)

CRS/PO 2 SGOO95A I SG NR Ch failure (TS)

TA0314 R,C 3 Stator Water runback wI subsequent auto rod control failure RD0061 ALL C

4 O/R CF12 MS10 failure in automatic CRS/PO RP0176A M Inadvertent SI, 2C 4KV vital bus UV following Rx trip, 5 C812/C809 ALL LBLOCA RCOOO1 6 C RP318A1,2 , Lo Head ECCS fails to actuate ALL I C

7 RP0277A,B I CS fails to actuate CRSRO i C

8 CV62B Charging pump cavitation RO I CT's: Init Cont Spray, initiate Lo head ECCS, xfer to CLR, trip cavitating charging pp.

  • (N)ormal, (R)eactlVlty, (I)nstrument, (C)omponent, (M)alor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-2 Op-Test No.: 11-01 NRC Examiners: Operators:

Initial Conditions: 75% power, MOL. Power was reduced 30 minutes ago due to a short duration oscillation on 21SGFP speed. PZR PORV 2PR1 was declared inoperable 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago due to control circuit problems, and its motor operated block valve 2PR6 is shut and power is removed from its breaker to com ply with TSAS ~1.4.5 action b.

Turnover: Maintain current power.

Event Malf. No. Event Event Type*

No. Description I

1 RC0014B 22 RC Loop Tavg Channel failure (TS)

CRSRO C

2 SG0078C 500 gpd SGTL on 23 SG. (TS)

ALL R

3 Power reduction ALL M

4 SG0078C SGTRon 23SG ALL Loss of Off Site power during SGTR RCS cooldown 5 C EL0134 (ROfCRS restart safeguards loads, PO re-establish RCS ALL cooldown via SG atmospheric reliefs)

C Only available PZR PORV 2PR2 fails to open results in 6 VL0298 CRS RO SGTR without RCS pressure control CTs: 1. Isolate feedwater into and steam flow out of 23 SG,

2. Cooldown and maintain CET Target temperature.
  • (N)ormal, (R)eactivity, (I)nstrument, (C}omponent, (M)aJor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-3 Op-Test No.: 11-01 NRC Examiners: Operators:

Initial Conditions: 47%, BOL , Rod control is in manual for insertion of new NI currents, currently performing SC.IC-DC.NIS-0021 for 21\J41. 21 Charging pump is crr due to bio-fouling. 22 charging pump is in service. 23 charging pump is inoperable but available. 21 SGFP O/S for speed control troubleshooting, HOPs O/S, calorimetric just performed SAT lAW requirement of S2.0P-10.ZZ-0004, Power Operations. 21 and 22 condensate pumps in service. 23A Circulator crr for corrective maintenance. Minor CW grassing has been occurring.

Turnover: Raise power to 51 %@ 10% per hour, place all HDP lIS, continue power ascension to 60%

at 10% per hour, all IAWIOP-4.

Event Malt. No. Event Event Type*

No. Description N

1 Raise power ALL AN3855 2 AN0023 CRS 2A1 125VDC batter charger trip (TS)

DAOO3D I

3 PROO16A I

CRS RO l PZR Press Inst fails hi (during first 1% power up) (TS)

C325 I C I Loss of Circ Water Bus Section 2'3 causes loss of 2 more 4

CN0086B .

i CRS PO l "An circulators, degrading Condenser Vacuum R

5 I ALL I Power reduction.

M 21 Condensate pump trip causes loss of only operating 6 I CN0117A ALL SGFP -l- Manual Rx trip AF0181B 7 C AF0181A Sequential loss of all AFW-l-FRHS Red Path CRS PO B606 C FRHS Bleed and Feed initiation (no centrifugal charging 8 CV0208B

! ALL pumps available) Cond pump recovery.

CT#1 Establish AFW flow CT#2 Establksh RCS Bleed and Feed I

  • (N)ormal, (R)eactlVlty, (I)nstrument, (C)omponent, (M)aJor Appendix 0, Page 38 of 39
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