ML15009A280

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Final Outlines (Folder 3)
ML15009A280
Person / Time
Site: Salem  PSEG icon.png
Issue date: 11/21/2014
From: David Silk
Operations Branch I
To: Gauding G
Public Service Enterprise Group
Shared Package
ML14174B408 List:
References
TAC U01894
Download: ML15009A280 (24)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility:

Salem Printed: 11/17/2014 Date Of Exam:

12/15/2014 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*

Total

1.

1 0

0 0

0 0

0 0

3 3

6 Emergency 2

0 0

0 N/A 0

0 N/A 0

0 2

2 4

Abnormal Tier Plant Totals 0

0 0

0 0

0 0

5 5

10 Evolutions

2.

1 0

0 0

0 0

0 0

0 0

0 0

0 3

2 5

Plant 2

0 0

0 0

0 0

0 0

0 0

0 0

0 I 2

1 3

Systems Tier 0

0 0

0 0

0 Totals 0

0 0

0 0

0 5

3 8

3. Generic Knowledge And 1

2 3

4 1

2 3

4 0

7 Abilities Categories 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 (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 total75 points and the SRO-only exam must total25 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 K!As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.
  • The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.
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-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 K/As that are linked to 10 CFR 55.43.

11/17/2014 10:36:19 am

PWR SRO Examination Outline Printed: 11/17/2014 Facility:

Salem ES-401 Emergency and Abnormal Plant Evolutions-Tier 1 I Group 1 Form ES-401-2 EIAPE #I Name I Safety Function K1 K2 K3 A1 A2 G

KA Topic Imp.

Points 000007 Reactor Trip - Stabilization -

X 2.4.30- Knowledge of events related to 4.1 1

Recovery I 1 system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

000029 A TWS I 1 X 2.4.41-Knowledge ofthe emergency 4.6 1

action level thresholds and classifications.

000056 Loss of Off-site Power I 6 X 2.1.7-Ability to evaluate plant 4.7 1

performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000062 Loss ofNuclear Svc Water I 4 X

AA2.02-The cause of possible SWS 3.6 1

loss WIE04 LOCA Outside Containment I 3 X

EA2.2-Adherence to appropriate 4.2 1

procedures and operation within the limitations in the facility's license and amendments WIE12-Steam Line Rupture-Excessive X

EA2.1 -Facility conditions and 4.0 1

Heat Transfer I 4 selection of appropriate procedures during abnormal and emergency operations KIA Category Totals:

0 0

0 0

3 3

Group Point Total:

6 11/17/2014 10:35:52 am

PWR SRO Examination Outline Printed: 1111712014 Facility:

Salem ES-401 Emergency and Abnormal Plant Evolutions-Tier 1 I Group 2 Form ES-401-2 EIAPE #I Name I Safety Function Kl K2 K3 Al A2 G

KA Topic Imp.

Points 00000 I Continuous Rod Withdrawal/ 1 X

AA2.05-Uncontrolled rod withdrawal, 4.6 1

from available indications 000003 Dropped Control Rod I 1 X

AA2.01-Rod position indication to 3.9 I

actual rod position 000036 Fuel Handling Accident I 8 X 2.4.11-Knowledge of abnormal 4.2 I

condition procedures.

000060 Accidental Gaseous Radwaste Rel. I X 2.1.32-Ability to explain and apply 4.0 1

9 system limits and precautions.

KIA Category Totals:

0 0

0 0

2 2

Group Point Total:

4 11/17/2014 10:35:58 am

PWR SRO Examination Outline Printed:

11/1712014 Facility:

Salem ES-401 Plant Systems-Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G KA Topic Imp.

Points 005 Residual Heat Removal X

A2.02-Pressure transient 3.7 1

protection during cold shutdown 006 Emergency Core Cooling X 2.4.6-Knowledge ofEOP 4.7 1

mitigation strategies.

026 Containment Spray X

A2.07-Loss of containment 3.9 1

spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding), or sump level below cutoff (interlock) limit 059 Main Feedwater X

A2.03 -Overfeeding event 3.1

limiting conditions for operations and safety limits.

KIA Category Totals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

5 11/17/2014 10:36:03 am

PWR SRO Examination Outline Printed:

11117/20 14 Facility:

Salem ES-401 Plant Systems-Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 002 Reactor Coolant X 2.1.20- Ability to interpret 4.6 1

and execute procedure steps.

033 Spent Fuel Pool Cooling X

A2.02 -Loss of SFPCS 3.0 1

041 Steam Dump/Turbine Bypass X

A2.02 - Steam valve stuck 3.9 1

Control open KIA Category Totals:

0 0

0 0

0 0

0 2

0 0

1 Group Point Total:

3 11/17/2014 10:36:09 am

Facility:

Salem Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 12/03/2014 Form ES-401-3 Gcneric-eate~:or~-- ----- ---- ---------- --EA-

-~--- ---- - --------- -----

J>oints Conduct of Operations Radiation Control Emergency Procedures/Plan 2.1.20 Ability to interpret and execute procedure steps; 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Category Total:

2:2:1 r - Knowledge oftne*processfononn*ol!ing temporary design changes.

2.2.25 Knowledge of the bases in Technical Specifications for lbniting conditions for operations and safety lhnits.

Category Total:

2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiatiotl areas, aligning filters, etc.

Category Total:

2.4.18 Knowledge of!he specific bases_ for EOPs.

2.4.29 Knowledge ofthe emergency plan.

Category Total:

Generic Total:

4.6 1

4.2 1

2

--*-3;3 --

j--

4.2 2

3.7 1

1 4.0 1

4.4 1

2 7

ES-401 PWR Examination Outline Form ES-401-2 Facility:

Salem Printed: 09/17/2014 Date Of Exam:

12/15/2014

=-~--=-= --=---=-~:::-

    • -Ro~'r\\/A~Gate-gory *Prnnts --- *

-~**----:-

s Ru=urYiy-Points-~-~-

lier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*

1.

1 3

3 3

3 3

3 18 0

0 Emergency 2

2 2

1 2

2 0

9 0

0 N/A N/A Abnormal Tier Plant Evolutions Totals 5

5 4

5 5

3 27 0

0

2.

1 2

2 3

3 3

2 2

3 2

3 3. 28 0

0 Plant 2

1 1

1 1

1 1

l 1

1 1

0 10 0 I *0 0

Systems Tier 3

3 4

4 4

3 Totals 3

4 3

4 3

38 0

0

3. Generic Knowledge And 1

2 3

4 1

2 3

4 10 Abilities Categories 3

3 2

2 0

0 0

0 Note:

1.

Ensure that at least two topics from every applicable KJA 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 KJA 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 Total 0

0 0

0 0

0 0

based on NRC revisions. The final RO exam must total75 points and the SRO-only exam must total25 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 KJA 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 K/As 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 K/A categories.

7.* The generic (G) K/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 K/As.

8.

On the following pages, enter the K/A 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-only exams.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals(#) on Form ES-401-3.

Limit SRO selections to K/As that are linked to 10 CFR 55.43.

09/17/2014 2:33:33 pm

PWR RO Examination Outline Printed: 0911712014 Facility:

Salem ES-401 Emergency and Abnormal Plant Evolutim,1S-Tier 11 Group 1 E/APE #I Name I Safety Function Kl K2 K3 Al Af ;.5J KA Topic

--~-=-==-=-c--.,......,~--- -**------==-=--o----=------,--* -

--=o*---==== -

  • =----=-

000007 Reactor Trip-Stabilization -

Recovery 11 000008 Pressurizer Vapor Space Accident I 3

000011 Large Break LOCA I 3 0000151000017 RCP Malfunctions I 4 000022 Loss ofRx Coolant Makeup 12 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water I 8

000027 Pressurizer Pressure Control System Malfunction I 3 000029 ATWS I 1 000038 Steam Gen. Tube Rupture I 3 000040 Steam Line Rupture - Excessive Heat Transfer I 4 000055 Station Blackout I 6 000057 Loss of Vital AC Inst. Bus 16 000058 Loss of DC Power 16 000065 Loss of Instrument Air I 8 000077 Generator Voltage and Electric Grid Disturbances I 6 W lEOS Inadequate Heat Transfer-Loss of Secondary Heat Sink I 4 09117/2014 2:33:04 pm X

X X

X X

X X

X X

  • ~~~; EA2.05-Reactor trip first-out *

~;;.{ indication

\\0;~! EK3.12-Actions contained in EOP for i-~
* *~~ emergency LOCA (large break)

<:;1< ~~1';~ AKl.O 1 - Consequences of thermal

. 1:;. c, shock to RCP seals

  • I.r AK2.02 - LPI or Decay Heat

. :,, ;-},}; RemovaliRHR pumps X h~~i; 1::,;~~~ AA1.02-Loads on the CCWS in the r~::;j 1:~:::~ control room IJ';~~;~ :,~~~ AK2.03 -Controllers and positioners

!ti;%1: ;:>~'~, 2.4.50- Ability to verify system alarm

);1:) :~;;~,,t setpoints and operate controls identified

5f
*,;2~*~, in the alarm response manual.

[':';?'1 iy:.:; AK3.01-Actions contained in EOP for I' (;\\ ;;; > loss of vital ac electrical instrument bus J:.~£~~ 't~~ 2.4.46-Ability to verify that the alarms f*'H;::~ ** ~>;:_ 1,'f,!',,,z<""*' are consistent with the plant conditions.

" ~**.

i:r~*p;o: F'%T 2.1.7-Ability to evaluate plant

[~~~* *:~:) performance and make operational

  • >~.; 1 ?.;: judgments based on operating
(?*' I ;-'
  • characteristics, reactor behavior, and

~;~~*.; I *~;1~ instrument interpretation.

  • ~~~ :E:;~.* AA2.02-Voltage outside the generator

.j~i !_. capability curve

'iF.,~! ; EK1.2-Nonnal, abnormal and I ;~-F r:; emergency operating procedures I ~:;;,,

associated with Loss of Secondary I-I eat Ji',.:; Sink I,';:~:I,>;'

,:::1*******:

Form ES-401-2 Imp.

Points 3.4 3.6 4.4 2.6 2.8 3.2~

3.2 2.6 4.2 3.6*

4.1 4.3 4.1 4.2 4.4 3.5 3.9

PWR RO Examination Outline Printed: 09/17/2014 Facility:

Salem ES-401 Emergency and Abnormal Plant Evolutions-Tier 1 I Group 1 Form ES-401-2 EIAPE #I Name I Safety Function W/Ell Loss of Emergency Coolant Recirc./

4 KIA Category Totals:

09/17/2014 2:33:04 pm 3

3 3

3 KA Topic Imp.

Points

~-~--

.-_--*=--~--

---,o--==-~:---:o--

=----.,----=...--"'"*--= ----=-- --- --=-*-=- ~

~ ~-

--==-=--=--.:-

EA2.1 - Facility conditions and selection of appropriate procedures during abnonnal and emergency operations 3.4 Group Point Total:

18 2

PWR RO Examination Outline Printed: 09117/2014 Facility:

Salem ES-401 Emergency and Abnormal Plant Evolutions-Tier 1 I Group 2 Form ES-401-2 000005 Inoperable/Stuck Control Rod I 1 000024 Emergency Boration I 1 X

000032 Loss of Source Range NI /7 X

000036 Fuel Handling Accident I 8 X

000076 High Reactor Coolant Activity /9 W/E03 LOCA Cooldown-Depress. I 4 X

W/E07 Inad. Core Cooling /4 X

W/E08 RCS Overcooling-PTS I 4 WIElD Natural Circ./4 K/A Category Totals:

2 2

1 09/17/2014 2:33:11 pm i :X;~*~-~;f* AA2.03-Required actions if more than

  • ';'(];; i'!.~t! AK3.0 1-Startup termination on

.'Hn 11.. ~{ source-range loss

  • ~~

[0~f AK1.01-Radiation exposure hazards X

  • ~~ii " ~t AA1.04-Failed fuel-monitoring 11:~~ >~ ~( equipment

'

  • EK1.2-Normal, abn01mal and

~~~~.~ emergency operating procedures 1 ;; *. ( ;'*J1,( associated with LOCA Cooldown and 1'}0:: * ;'*}~;: Depressurization i~;, EK2.2 -Facility's heat removal systems,

~:~.:~ including primary coolant, emergency

~.<:;:1 f.i;; coolant, the decay heat removal

1. **

': systems, and relations between the f[~~~i.* proper operation of these systems to the b*,< operation of the facility

"if: EA2.2 -Adherence to appropriate I' {': procedures and operation within the

,:::, limitations in the facility's license and

>*~ amendments X pp
~ ~*::~;: EA 1.3 - Desired operating results k~, ::;V during abnormal and emergency 1,;,~~;;

,'>;{. situations 3.5 2.7 3.2 3.5 3.2 3.6 3.5 3.5 3.4 Group Point Total:

1 9

Facility:

Salem ES-401 Sys/Evol #I Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 0 1 0 Pressurizer Pressure Contra 1 0 12 Reactor Protection 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 022 Containment Cooling 026 Contaiment Spray 039 Main and Reheat Steam 039 Main and Reheat Steam 059 Main Feedwater 09/17/2014 2:33:17 pm PWR RO Examination Outline Printed:

09/17/2014 Plant Systems-Tier 2 I Group 1

~.>~>

x:~"'"

Kl K2 K3 K4 KS K6 Al }\\~ A3 A4

.~** KA Topic X

X X

X X

X X

i;i*** X 11*~ T<:o:0£1.- Containment * **

  • 1*;r;;~: isolation valves affecting
  • " RCP operation 1\\'
    i K2.02-CCW pumps 1 ;r:_* A2.30- Reduction of boron

..,; concentration in the letdown

! ::;y flow; i:s effects on reactor 1{'( operatwn

"' K2.01-RHR pumps X ;:~ A4.01-Pumps

-~. 2.4.46 - Ability to verify that

>,* the alarms are consistent

);,. with the plant conditions.

'.: A2.0 1-Stuck-open PORV l

or code safety 1':~* 2.2.37-Ability to detetmine

    • . operability and/or 1~*-Y availability of safety related It,: equipment.

1',~,* K3.01 - RCS IS.~: K5.02-Constant enthalpy

! ;~.f expansion through a valve i;C~ K4.02-Automatic reactor

~

1 trip when RPS setpoints are exceeded for each RPS

.. function; basis for each

~

\\ 2.4.9-Knowledge of!ow power/shutdown

~ implications in accident

'\\'. (e.g., loss of coolant

" ', accident or loss of residual

.:c:~ heat removal) mitigation

1. :. t strategies.

~-~t A 1.04-Cooling water flow fj' A2.04-Loss of service lj :? water X ii~. A4.05-Contaimnent spray 1 :::;:"'. reset switches 1 '/ K5.08-Effect of steam

'{, ;. removal on reactivity

-;;, A3.02-Isolation of the

(

MRSS X 1 A4.03 - Feedwater control during power increase and decrease I*

I<orm ES-401-2 Imp.

Points L..8 2.5*

3.3 3.0 4.1 4.2 3.9 3.6 3.8 2.6 3.9 3.8 4.4 3.2 2.9*

3.5 3.6 3.1 2.9*

Facility:

Salem ES-401 Sys/Evol #I Name

  • uo1AiixiliaJy7Einergellcy Feed water 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air l 03 Containment KIA Category Totals:

09/17/2014 2:33:17 pm PWR RO Examination Outline Printed:

0911712014 Plant Systems-Tier 2 I Group 1 Form ES-401-2 Kl K2 K3 K4 KS K6 Al At. A3 A4 i ~; KA Topic Imp. Points X

X X

X X

X l"i~i' K3.01-Major system loads

?

!:;,; Kl.03-Battery charger and I *;.., battery

~

~ A3.05 - Operation of the governor control of I***

frequency and voltage 1**:-:f: control in parallel operation I'~?~J K5.02-Radiation intensity

' ; : changes with source distance f A1.01 -Radiation levels

~;i, K4.01-Conditions initiating

[;,;

automatic closure of closed h~) cooling water auxiliary 1;:~+* building header supply and f~: :;:. return valves W Kl.02-Service air l~i* K4.06-Containment 1*.:~/ isolation system 3.5 2.9 2.8 2.5 3.2 2.5*

2.7*

3.1 Group Point Total:

2 28

PWR RO Examination Outline Printed: 09/17/2014 Facility:

Salem ES-401 Plant Systems-Tier 2/ Group 2 Form ES-401-2

";';(,"

Sys/Evol #I Name

" ;.* ~ ;,-*,, __

Kl K2 K3 K4 K5 K6 Al 1\\_:r A3 A4 c* KA Topic Imp. Points

  • om'Cof'ftrol~RO'Cl~Dfivc --.-.--=~-==-

--:-~.*-

-c"C"" --)<F-

-~-:~

~~~

--='-=--

1~

-r{'S-:0&-c Effects -ufcontrol~~- -- 3-:-&== ~.;.1*-~-

rod motion on axial offset 002 Reactor Coolant

! -".;;** X

f;y: A3.03-Pressure, 4.4 1

temperatures, and flows 011 Pressurizer Level Control X

I~

K6.06-CotTelationof 2.5*

1

!~'

demand signal indication on charging pump flow valve

!~r controller to the valve

\\;

position 015 Nuclear Instrumentation X

[*'<

-v: K4.02-Rod motion inhibits 3.7 1

017 In-core Temperature Monitor X

K3.01-Natural circulation 3.5*

1 indications 028 Hydrogen Recombiner and X

. b'~ K2.01-Hydrogen 2.5*

1 Purge Control

_f;

  • recombiners 033 Spent Fuel Pool Cooling

.X;

'
i-A2.01 -Inadequate SDM 3.0 1

045 Main Turbine Generator X [<7r

~~:l A1.06-Expected response 3.3 1

of secondary plant 1~;;11' lli parameters following T/G trip 056 Condensate X

I'"Y Kl.03-MFW 2.6*

1 068 Liquid Radwaste

_:;}

X 0i; A4.04 -Automatic isolation 3.8 1

KIA Category Totals:

1 1

1 1

1 1

1 :_-tk

:.. o*

1 1 !):

Group Point Total:

10 09/17/2014 2:33:23 pm

Facilitv:

Salem Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan 09/17/2014 2:33:28 pm Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

2.1.27 Knowledge of system purpose and/or function.

2.1.42 Knowledge of new and spent fuel movement procedures.

Category Total:

2.2.13 Knowledge of tagging and clearance procedures.

2.2.22 Knowledge of limiting conditions for operations and safety limits.

2.2.40 Ability to apply Technical Specifications for a system.

Category Total:

2.3.7 Ability to comply with radiation work pennit requirements during normal or abnormal conditions.

2.3.13 Knowledge of radiological safety procedures 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:

2.4.14 Knowledge of general guidelines for EOP usage.

2.4.29 Knowledge of the emergency plan.

Category Total:

Generic Total:

Printed: 09/17/2014 Form ES-401-3 4.1 1

3.9 1

2.5 1

3 4.1 I

4.0 1

3.4 1

3 3.5 I

3.4 1

2 3.8 1

3.1 1

2 10

ES-401 Tier/Group Randomly Selected KIA SRO 1/1 025 AA2.04 SROIII 056 2.1.44 SRO 1/1 E05 2.1.40 SRO 1/2 005 2.4.6 SRO 21I 039 A2.04 SRO 2/1 076 2.3.11 SRO 2/2 072 A2.01 SRO 2/2 017 2.4.26 SR03 2.3.5 ROlli 054 2.1.39 RO 1/1 062 AA1.03 RO 1/1 065 2.2.17 RO 1/1 E04 2.1.45 ROlli 054 2.1.25 ROlli E04 2.1.2 RO 1/1 056 2.2.43 RO 112 068 2.1.39 R

. ' --* d of Reiected K/As Sal -*** 13-01 NRC E F

........ -**** ES-401-4 Reason for Rejection Sampled on CERT exam.

(ES-401, D.l.b)

I Refueling admin requirements NA to Loss of Secondary Heat Sink Oversampling of rod/rod control problem. Already have 001 cont rod withdraw! and 003 dropped rod on outline.

Essentially the same KA as 041 A2.02 on this exam. (Malfunctioning steam dump/stuck open steam dump)

(ES-401, D.l.b)

ARM erratic power supply not conducive to SRO level question.

Facility protection requirements NA to In core temp monitoring system.

Neither SRO level nor written exam conducive to use radiation monitors.

(ES-401, D.l.b)

SWS system cannot be used as backup to CCW System.

(ES-401, D.l.b)

(ES-401, D.l.b)

(ES-401, D.l.b)

(ES-401, D.l.b)

(ES-401, D.l.b)

(ES-401, D.l.b)

~--

ES-40 1, Page 27 of 33 Page 1 of 2

ES-401 R01/2 060 2.2.7 RO 2/1 006 A2.06 R02/1 007 2.2.4 R02/1 008 2.2.6 R02/1 039 K4.07 R02/1 022 2.4.28 R02/1 073 2.1.40 R02/1 003 K5.03 R02/1 039 A4.04 R02/2 041 K2.01 R02/2 086 2.1.17 R03 2.2.41 R03 2.3.5 SR03 2.2.19 SR03 2.2.5 R

-* d of Reiected Kl As Sal -*** 13-01 NRC E F

I

-*I I I ES-401-4 (ES-401, D.l.b)

Water hammer in ECCS system not addressed in procedures.

No unit difference in PRT systems.

(ES-401, D.l.b)

Salem does not have a Reactor Building. MSLI is applicable to containment isolation.

(ES-401, D.l.b)

(ES-401, D.l.b)

Sampled on CER T exam.

Salem does not have Emergency Feedwater pumps turbines Salem does not have an ICS.

(ES-401, D.l.b)

Cannot "obtain" drawings during a written exam. More suitable for operating exam.

Very close to 2.3.13 on this exam. Oversampling of radiation monitors/alarms. Also more suited to Operating exam.

Could not write SRO level question. Deleted after Prep Week.

Oversampling of design changes, Kl A 2.2.11 also on this exam.

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

SALEM Date of Examination:

12/08/14 Examination Level:

  • RO SRO Operating Test Number:

13-01 NRC Administrative Type Describe activity to be performed Topic (See Note)

Code*

Conduct of R,N Calculate leakrate into containment sump.

Operations 2.1.25 (RO 3.9)

Calculate Quadrant Power Tilt Ratio Conduct of R,M 2.1.43 Ability to use procedures to determine the effects on reactivity of plant Operations changes, such as reactor coolant temperature, secondary plant, fuel depletion, etc.

(RO 4.1)

Equipment Control R,D,P Prepare a manual tagout.

2.2.13 Knowledge of tagging and clearance procedures. R04.1.

Radiation Control NA NA Emergency S,M Activate EROS during an ALERT Procedures I Plan 2.4.43 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 Topics Outline Form ES-301-1 Facility:

SALEM Date of Examination:

12/08/14 Examination Level:

RO

  • SRO Operating Test Number:

13-01 NRC Administrative Type Describe activity to be performed Topic (See Note)

Code*

Conduct of R,M Operate the Chilled Water System (Identify and Isolate Non-Essential Heat Loads)

Operations 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Conduct of Review completed QPTR Operations R,M 2.1.18 Ability to make accurate,clear, and concise logs, records, status boards, and reports. SRO 3.8 Evaluate a tagging request.

Equipment Control R,D 2.2.13 Knowledge of tagging and clearance procedures SRO 4.3 Radiation Control R,M Authorize a Radioactive Gas Release.

2.3.6 Ability to approve release permits. SR0-3.8 Emergency R,N Make an Emergency Classification Protective Action Recommendation (PAR)

Procedures I Plan 2.4.44 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 Control Room Systems/In-Plant System Outline Form ES-30 ': <:

Facility:

SALEM Date of Examination:

12/8/14 I

Exam Level:

SR0-1 SRO-U Operating Test No.:

13-01 NRC Control Room Systems@ (8 for RO; 7 for SR0-1; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function a) Perform a Boration Flow Capability to the RCS Surveillance Test (004 A4.18 R0-4.3 SR0-4.4)

D,S 1

b) Transfer to Cold Leg Recirc wl a cont sump suet valve failure A,D,EN,S 2

c) TCAF PZR Pressure Malfunction (Isolate leaking PZR PORV)

N,S 3

d) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using Rx Head Vent Valves)

A,D,P,S 4 (pri) e) Perform RCS cooldownldepressurization lAW EOP-TRIP-4 Natural Circulation Cooldown M,A,S 4 (sec) f)

Perform a CFCU Operability and Service Water Flow Verification M,S 5

g) Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx SIU (012 A4.03 R0-3.6 SR0-3.6)

A,D,L,S 7

h) Start a CCW pump lAW EOP-APPX-1.

A,EN,L,M,S 8

In-Plant Systems (3 for RO; 3 for SR0-1; 3 or 2 for SRO-U) i)

Unload and shutdown an EDG.

D,R 6

j)

Transfer PZR BU heaters to emergency power source during LOOP D,E 3

k)

Commence a radioactive liquid waste release, and respond to high activity during the release.

A,D,R 9

@ All RO and SR0-1 control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions ; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes:

Criteria for RO I SR0-11 SRO-U (A)Iternate path 4-61 4-6 I 2-3 (C)ontrol room (D)irect from bank

_:::9 I _:::8 I ::5.4 (E)mergency or abnormal in-plant

_::::1 I

~ 1 1.:::_ 1 (EN)gineered safety feature

- I - I ~ 1 (control room system)

(L)ow-Power I Shutdown

~1 I ~1 I

~1 (N)ew or (M)odified from bank including 1 (A)

_::::2 I

.:::_ 2 I~ 1 (P)revious 2 exams

5.3 I ::5.3 I ::5.2 (randomly selected)

(R)CA

~1 I

.::: 11.::: 1 1SJimulator

ES-301 Control Room Systems/In-Plant System Outline Form ES-30 ~ -.~

1 Facility:

SALEM Date of Examination:

12/8/14 II II Exam Level : RO llsRo-111 SRO-U Operating Test No.:

13-01 NRC Control Room Systems@ (8 for RO; 7 for SR0-1; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function a) Perform a Boration Flow Capability to the RCS Surveillance Test (004 A4.18 R0-4.3 SR0-4.4)

D,S 1

b) Transfer to Cold Leg Recirc wl a cant sump suet valve failure A,D,EN,S 2

c) TCAF PZR Pressure Malfunction (Isolate leaking PZR PORV)

N,S 3

d) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using Rx Head Vent Valves)

A,D,P,S 4 (pri) e)

f)

Perform a CFCU Operability and Service Water Flow Verification M,S 5

g) Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx SIU (012 A4.03 R0-3.6 SR0-3.6)

A,D,L,S 7

h) Start a CCW pump lAW EOP-APPX-1.

A,EN,L,M,S 8

In-Plant Systems (3 for RO; 3 for SR0-1; 3 or 2 for SRO-U) i)

Unload and shutdown an EDG.

D,R 6

j)

Transfer PZR BU heaters to emergency power source during LOOP D,E 3

k)

Commence a radioactive liquid waste release, and respond to high activity during the release.

A,D,R 9

@ All RO and SR0-1 control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions ; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes:

Criteria for RO I SR0-1 I SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

_:::9 I _:::8 I~ 4 (E)mergency or abnormal in-plant

~1 I

~ 1 I~ 1 (EN)gineered safety feature

- I - I ~ 1 (control room system)

(L)ow-Power I Shutdown 2:1 I 2:1 I ::::1 (N)ew or (M)odified from bank including 1 (A)

~2 I 2:2 I 2: 1 (P)revious 2 exams

~ 3 I~ 3 1~2 (randomly selected)

(R)CA 2:1 I

11 ~ 1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility:

SALEM 1 & 2 Scenario No.:

ESG-1 Op-Test No.: 13-01 NRC Examiners:

Operators:

Initial Conditions: 90% power, EOL.

Turnover: Raise Rx power to 98.5%@ 10% per hour lAW IOP-4, Power Operation.

Event Malf. No.

Event Type*

Event No.

Description 1

R CRS/RO Raise power N PO c

2 AN0266 CRS EDG Air Receiver low pressure (TS) 3 CC0172C c

CCW pump trip w I failure of standby pump to start (TS)

CC0361B CRS/PO 4

RC007D c

RCP seal degradation CRS/RO 5

MS0092H M

Steam leak in containment ALL 6

MS0092 c

MSLI failure (Loss of Secondary Coolant)

E-H ALL 7

RP318L 1 c

Containment Spray pumps fail to start on SEC signal RP318L2 CRS/RO CT's: 1. Stop RCP with seal failure 2 Start minimum complement of containment cooling.

2. Minimize AFW flow
  • (N)ormal, (R)eact1v1ty, (l)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39

Appendix 0 Scenario Outline Form ES-D-1 Facility:

SALEM 1 & 2 Scenario No.:

ESG-3 Op-Test No.: 13-01 NRC Examiners:

Operators:

Initial Conditions: 100% power, MOL.

Turnover: Maintain current power. Perform weekly Vacuum Pump swap lAW S2.0P-SO.AR-0001.

Event Malf. No.

Event Type*

Event No.

Description 1

N Swap condenser vacuum pumps PO 2

VL0336 c

Loss of condenser vacuum (recoverable)

VL0337 CRS/PO 3

EL0144 c

Loss of 2A 4160 volt vital bus (TS)

ALL 4

TU0055 I

Turbine Inlet steam pressure transmitter (PT-505) failure ALL (TS) 5 MS0302 M

Steam dump failure with single MSIV failing to shut ALL 6

RP0108 c

Failure of automatic Safety Injection (steam line D/P)

CRS/RO 7

AF0181B c

Loss of All AFW flow-FRHS condensate pump recovery AF0183 ALL CT's: #1 Initiate manual Safety Injection

  1. 2 Establish Condensate flow in FRHS
  • (N)ormal, (R)eact1V1ty, (l)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-4 Op-Test No.: 13-01 NRC Examiners:

Operators:

Initial Conditions: 4% power, BOL. Unit is returning from forced outage to repair all 4 RCP diffuser vanes bolting issue. 24 SW pump is CIT for strainer repair.

Turnover: Raise power to 18% @1 0% per hour.

Event Malf. No.

Event Type*

Event No.

Description 1

R Raise power ALL 2

SW0216A c

  1. 2 SW bay leak (TS)

ALL 3

RC0002 c

RCS leak (TS)

ALL 4

CV0208A c

Centrifugal charging pump fails during swap from PDP while CV0208B CRS/RO responding to RCS leak. (TS) 5 RC0002 M

SBLOCA CRS/RO 6

EL0134 c

LOOP coincident with Sl initiation ALL 7

0/R A701 B c

2C SEC fails to initiate Dl CRS/PO 8

RP318S1 c

High head ECCS fails to inject (one pump failed from Event RP318S2 CRS/RO 4 above, other pump doesn't start)

CT's: #1 Establish High Head ECCS

  1. 2 Start minimum SW pumps
  • (N)ormal, (R)eact!VIty, (l)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-5 Op-Test No.: 13-01 NRC Examiners:

Operators:

Initial Conditions: 75% power MOL. Power was reduced 30 minutes ago due to 21 SGFP Governor problems. 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 intermittent control circuit anomalies, and the PORV Block valve 2PR6 was shut and deenergized to comply with TSAS 3.4.5 action b.

Turnover: Maintain current power Event Malf. No.

Event Type*

Event No.

Description 1

CV0035 c

Charging Master Flow Controller fails low CRS/RO 2

PR0017C Non-controlling PZR level Channel Ill fails (TS) 3 SG0078C c

90 gpd SGTL (TS)

ALL 4

RCRS/RO Down power N PO 5

SG0078C M

SGTR ALL 6

AF0182B c

22 AFW pp pressure override failure CRS/PO 7

RC0003C c

23 RCP trip during cooldown ALL 8

VL0298 c

PZR PORV fails shut/SGTR depress unavail --.SGTR-5 CRS/RO CT's: #1 Isolate AFW

  1. 2 C/D to, and maintain, RCS temp
  • (N)ormal, (R)eactiVIty, (l)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39
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