ML113330777

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Draft - Outlines (Folder 2)
ML113330777
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/15/2011
From:
Public Service Enterprise Group
To:
Operations Branch I
JACKSON D RGN-I/DRS/OB/610-337-5306
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ML110030673 List:
References
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Download: ML113330777 (23)
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Text

ES-401 PWR Examination Outline Form ES401-2 FICUiW:

Salem Printed: 06/13/2011 Date Of Exam:

()9126/2011 RO KIA Category Points aRO-OnlY POin!!:>

Tier Group K'I K2 K3 K4 K5 K6 A1 A2 A3 M G* Total A2 G"

Total

1.

1 0

0 0

0 0

0 0

3 6

Emergenvy

3. Generic Knowledge And 2

0 0

0 N/A 0

0 N/A 0

0 2

2 4

Abnormal Plant Evolutions Tier Totals 0

0 0

0 0

0 0

5 5

10

2.

1 (If 0

0 0

0 0

0 0

0 0

0 0

3 2

5 Plant 2

(:I 0

0 0

0 0

0 0

0 0

0 0

0 I 2

1 Systems Tier Totals 0

0 0

0 0

0 0

0 0

0 0

0 5

3 8

1 2

~~

4 1

2 3

4 0

7 Abilities Categ()ries 0

0 i[)

0 2

1 2

2 Note:

1. Ensure that at least two topics from every applicabfe KiA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in 'ner 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 ftnal point total for each group and tier may deviatEt by +/-1 from that specified in the table based on NRC re'!iisions. The final RO exam must total 75 points and the SRO-only exam must totat 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 justifiE¢ operationally important, site-specific systemslevolutions that are not included on the outline should be addE.>d. 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 sy~~tem or evolution
5. Absent a plant-specific priority, only those KiAs having an importance rating (IR) of 2.5 or higher shaH be selected Use the RO and SRO ratings for the RO and SR().onIy portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded sy'stems and KiA categories.

7." The generic (G) KJAs in Tiers 1 and 2 sha" be selected from Section 2 ofUle KIA Catalog. but the topics must be relevant to the applicable evolution or s~,stem. Refer to Section D.1.b of ES-401 for the applicable K1As.

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 (~egory in the table above; if fuel handling equipment is sampled in other than Category A2 or G" on the SRO-onlyexam. 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 catalClg. 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.

06113/2011 6:00:06 pm

PWR SRO Examination Outline Printed: 06/1312011 Facility:

Salem ES-401 Emergency and Abnormal Plant Evolutions - Tier II Gronp 1 Form ES-401-2 ElAPE # I Name I Safety Function KI K2 K3 Al A2 G

KA Topic Imp.

Points 0000 15/0000 17 RCP Malfunctions /4 X

AA2.10 - When to secure RCPs on loss of cooling or seal injection 3.7 1

000025 Loss of RHR System I 4 X 2.4.6 ~ Knowledge ofEOP mitigation strategies.

4.7 1

000040 Steam Line Rupture - Excessive Heat Transrer I 4 X

AA2.02 - Conditions requiring a reactor trip 4.7 1

000062 Loss ofNuclear Svc Water 14 X

AA2.02-The cause ofpossihle SWS loss 3.6 1

000065 Loss of Instrument Air I 8 X 2.1.36 - Knowledge ofprocedures and limitations involved in core alterations.

4.1 1

W1E0S Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X 2.4.6 - Knowledge ofEOP mitigation strategies.

4.7 1

KIA Category Totals:

0 0

0 0

3 3

Group Point Total:

6 06113/2011 5:59:40 pm 1

PWR SRO Exan,lination Outline Printed: 06/1312011 Facility:

Salem ES-401 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 2 Form ES-401-2 ElAPE # I Name I Safety Function KI Xl 10 Al A2 G

KA Topie Imp.

Points 000059 Accidental Liquid RadWaste ReI. I X 2.236 - Ability to analyze the effect of 4.2 1

9 maintenance activities. such as degraded power sources, on the status oflimiting conditions for operations.

WlE07 Inad. Core Cooling 14 X

EA2.l - FacUity conditions and 4.0 1

selection ofappropriate procedures during abnormal and emergency operations WlE08 RCS Overcooling - PTS 14 X

EA2.1 - FacUity conditions and 4.2 I

selection ofappropriate procedures during abnormal and emergency operations W IE09 Natural Cire. 14 X 2.4.11 - Koowledge of abnormal 4.2 I

condition procedures.

KIA Category Totals:

0 0

0 0

2
2 Group Poiot Total:

4 06113/2011 5:59:45 pm 1

PWR SRO Examina1tion Outline Printed:

0611312011 Facility:

Salem ES ~ 401 Plant Systems - Tier 11 Group 1 Form ES-401-2 SyslEvol # I Name Kl Kl K3 K4 KS K6 Al AZ A3 A4 G KA Topic Imp. Points 006 Emergency Core Cooling X 2.4.22 - Knowledge ofthe bases for prioritizing safety functions during abnonnaJJemergency operations.

4.4 1

010 Pressurizer Pressure Control X

A2.03 - PORV failures 4.2 I

013 Engineered Safety Features Actuation X

A2.03 - Rapid depressurization 4.7 I

064 Emergency Diesel Generator 076 Service Water X

X A222 - Potential automatic safuty sequences (water/C02) and electrical damage (loose wires) 2.2.37 - Ability to determine operability and/or availability of safety related equipment 2.8*

4.6 1

1 KIA Category Totals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

S 06/1312011 5:59:51 pm

PWR SRO Examination Outline Printed:

06/1312011 Facility:

Salem ES-401 Plant Systems - Tier 21 Group 2 Form E8-401-2 SyslEvol # I Name 002 Reactor Coolant Kl KZ K3 K4 K5 K6 Al Al X

AJ A4 G KA Topic A2.03 - Loss of forted circulation Imp.

43 Points 1

oII Pressurizer Level Control X

A2.0 1 - Excessive letdown 3.1 1

034 Fuel Handling Equipment X 2.4.35 - Knowledge oflocal auxiliary operator tasks during an emergency and the resultant operational effects.

4.0 1

KIA Category Totals:

0 0

0 0

0 0

0 2

0 0

1 Group Point Total:

3 06/1312011 5:59:56 pm

(:ieneric Knowledge and Abilities Outline (Tier 3)

Facility!

Salem Gcgeric Catqory Conduct of Operations Equipment Control RAdiation Control Emergency ProcedureslPlan PWR SRO Examination Outline Printed: 06/1312011 Form E8-401*3 J(ATopie 2.1.23 Ability to pcrlorm specific system and integrated 4.4 I

plant procedures during all modes ofplant operation.

2.1.43 Ability to use procedures to determine the effects 4.3 I

on reactivity of plant changes, such as reactor coolant system temperatun:, secondary plant, fuel depletion, etc.

Category Total:

1 2.2..23 Ability to track Technical Specification limiting 4.6 1

conditions for operations.

Category Total:

1 2.3.4 Knowledge of radiation exposure limits under 3.7 1

normal or emergency conditions.

2.3.14 Knowledge ofradiation or contamination hazards 3.8 1

that may arise during normal, abnormal, or emergency conditions or activities.

Category Total:

1 2.4.27 Knowledge of "fire in the plant" procedure.

3.9 1

2.4.38 Ability to take actions called for in the facility 4.4 1

emergency plan, including supporting or acting as emergency coordinator ifrequired.

Category Total:

2 Generic Total:

7 06/1312011 6:00:01 pm

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

Salem Printed: 06/14/2011 Date Of Exam:

09/26/2011 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 3

3 3

I 3 3

3 18 0

0 0

Emergency 2

2 2

2 1

2 0

9 0

0 0

NIA NIA Abnormal Tier Plant Totals 5

5 5

4 5

3 27 0

0 0

Evolutions 1

3 2

3 3

2 2

.) "

3 2

3 2

28 0

0 0

2.

2 1

1 1

1 1

1 1

1 1

1 0

10 0

0 0

0 I

Plant Tier Systems 4

3 4

4 3

3 4

4

.)

4 2

38 0

0 0

Totals 1

2 3

4 1

2 3

4

3. Generic Knowledge And 10 0

Abilities Categories

~.

2 3

.I..

3 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 SRQ..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 ES-401 for guidance regarding the elimination of inappropriate I<.JA statements.
4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group befom selecting a second topic for any system or evolution.

5. Absent a plant-sp~cific priority, only those KlAs having,m importance rating (lR) 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) 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 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-only exams.
9.

For Tier 3, select topics from Section 2 of the KIA catalcg, 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.

06/14/2011 11:58:32 am

PWR RO Examination Outline Printed: 06114/20 II Facility:

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

KA Topic Imp.

Points 000007 Reactor Trip - Stabilization -

X EA2.03 - Reactor trip breaker position 4.2 1

Recovery /1 000008 Pressurizer Vapor Space Accident /

X 2.2.39 - Knowledge ofless than or equal 3.9 1

3 to one hour Technical Specification action statements for systems.

000009 Small Break LOCA ! 3 EK3.28 - Manual ESF AS initiation 4.5 1

requireme':1ts 000015/000017 RCP Malfunctions / 4 AK2.07 RCP seals 2.9 1

ttl 000022 Loss ofRx Coolant Makeup 12 X

AKl.Ol-Consequences ofthermal 2.8 1

shock to RCP seals 000025 Loss ofRHR System /4 X

AKl.OI-Loss ofRHRS during all 3.9 1

modes ofoperation 000026 Loss of Component Cooling Water /

X 2.1.32 - Ability to explain and apply 3.8 1

8 system limits and precautions.

000027 Pressurizer Pressure Control System AAl.03 - Pressure control when on a 3.6 1

Malfunction / 3 steam bubble 000029 A TWS / 1 X

EA2.04 - CVCS centrifugal charging 3.2*

1 pump operating indication 000038 Steam Gen. Tube Rupture / 3 X

EK 1.02 - Leak rate vs. pressure drop 3.2 1

000040 Steam Line Rupture - Excessive X

AK2.0 1 - Valves 2.6*

I Heat Transfer / 4 000054 Loss of Main Feedwater / 4 X

AK3.01-Reactor and/or turbine trip, 4.1 I

I manual and automatic 000056 Loss ofOff-site Power / 6 X

AA 1.08 - HVAC chill water pump and 2.5*

1 unit 000058 Loss of DC Power / 6 X 2.4.6 - Knowledge of EOP mitigation 3.7 1

strategies.

000062 Loss ofNuclear Svc Water / 4 X

AA2.06 - The length of time after the 2.8*

1 loss of SWS flow to a component before that component may be damaged 000065 Loss of Instrument Air / 8 X

AK3.08 - Actions contained in EOP for 3.7 1

loss of instrument air WiE04 LOCA Outside Containment / 3 X

EA 1.2 - Operating behavior 3.6 1

characteristics ofthe facility W/EII Loss of Emergency Coolant Recirc.!

X EK2.1 - Components, and functions of 3.6 1

4 control and safety systems, induding instrumentation, signals, interlocks,

failure modes, and automatic and
  • .... '; manual features KIA Category Totals:

3 3

3 3

3 3

Group Point Total:

18 06/14/2011 11:58:01 am

PWR RO Examination Outlline Printed: 06114/2011 Facility:

Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 E/APE # I Name I Safety Function 000003 Dropped Control Rod I 1 000032 Loss of Source Range NI I 7 000033 Loss of Intermediate Range Nl I 7 000051 Loss of Condenser Vacuum I 4 000060 Accidental Gaseous Radwaste ReI. I 9

000074 Inad. Core Cooling I 4 W/E03 LOCA Cooldown - Depress.. 14 WIE 13 Steam Generator Over-pressure I 4 W/E16 High Containment Radiation I 9 K/A Category Totals:

Kl K2 K3 Al A2 G

KA Topic Imp.

Points X

AK3.07 - Tech-Spec limits for T-ave 3.8*

1 X

AKl.Ol-Effects of voltage changes on 2.5 1

performance X

AA2.0 I - Equivalency between 3.0 1

source-range, intermediate-range, and power-range channel readings X

AK3.01-Loss of steam dump 2.8*

1 capability upon loss of condenser vacuum X

AK2.02 - Auxiliary building ventilation 2.7 1

system X

EK2.0l - RCP 3.6 1

X EKl.l - Components, capacity, and 3.4 1

function of emergency systems X

EA 1.2 - Operating behavior 3.0 1

characteristics ofthe facility X

EA2.2 - Adherence to appropriate 3.0 1

procedures and operation within the limitations in the facility's license and amendments 2

2 2

1 2

0 Group Point Total:

9 06/14/2011 11 :58:08 am

PWR RO Examination Outline Printed:

06114/2011 Facility:

Salem ES - 401 Plant Systems - Tier! / Group 1 Sys/Evol # 1Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic 003 Reactor Coolant Pump X

K6.04 - Containment isolation valves affecting RCP operation 003 Reactor Coolant Pump X

K3.02 - S/G 004 Chemical and Volume Control X

K6.29 - Reason for excess letdown and its relationship to CCWS 005 Residual Heat Removal X 2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.

005 Residual Heat Removal X

Kl.OI - CCWS 006 Emergency Core Cooling X

K4.06 - Recirculation of minimum flow through

_0' pumps 007 Pressurizer Relief/Quench X

A3.0 1-Components which Tank discharge to the PRT 008 Component Cooling Water X

K4.02 - Operation of the surge tank, including the associated valves and controls 010 Pressurizer Pressure Control X

K3.01 - RCS 010 Pressurizer Pressure Control X

A4.03 - PORV and block valves 012 Reactor Protection X

K4.06 - Automatic or manual enable/disable of RPS trips 012 Reactor Protection 013 Engineered Safety Features Actuation t

X X 2.4.6 - Knowledge ofEOP mitigation strategies.

A 1.04 - S/G level 013 Engineered Safety Features X

A4.01-ESFAS-initiated Actuation equipment which fails to

- actuate 022 Containment Cooling X

K3.02 Containment instrumentation readings 026 Containment Spray X

\\i A4.01 - CSS controls 026 Containment Spray X

, A3.0I-Pump starts and correct MOV positioning 039 Main and Reheat Steam X

A 1.06 - Main steam pressure 039 Main and Reheat Steam X

K5.01-Definition and causes of stearn/water hammer 1059 Main Feedwater X

A2.12 - Failure of feedwater 061 AuxiliarylEmergency Feedwater X

Ii ~ Pump head eff,,'"

ontrol valve is shut 062 AC Electrical Distribution X

Kl.03 DC distribution I

Form ES-401-2 Imp.

Points 2.8 1

3.5 1

2.7 I

4.2 1

3.2 1

2.7 I

2.7*

I 2.9 I

3.8 1

4.0 I

3.2 1

3.7 I

3.4 1

4.5 I

3.0 1

4.5 1

f--

4.3 I

1 3.0 1

2.9 1

3.

2 3.5 1

06/14/2011 11:58:15 am

PWR RO Examination Outline Printed:

06114/2011 Facility:

Salem ES - 401 Plant Systems - Tier 2 I Group I Form ES-401-2 Sys/Evol # / Name 063 DC Electrical Distribution Kl A2 X

A3 A4 G KA Topic A2.0 1 - Grounds Imp.

2.5 Points K2.02 - Fuel oil pumps 2.8*

073 Process Radiation Monitoring 076 Service Water X

A2.0 1 - Erratic or failed power supply K2.0 1 - Service water 2.5 2.7*

078 Instrument Air 103 Containment X

K 1.04 - Cooling water to compressor Al.OI-Containment pressure, temperature, and humidity 2.6 3.7 1

KIA Category Totals:

3 2

3 3

2 2

3 3

2 3

2 Group Point Total:

28 06/14/2011 11:58:15 am 2

PWR RO Examination Outline Printed:

06/14/20 II Facility:

Salem Plant Systems - Tier.2 1Group 2 Form ES-401-2 ES - 401 Sys/Evol # I Name KI K2 K3 K4 K5 K6 At A2 A3 A4 G KA Topic Imp.

001 Control Rod Drive t

X I

K3.02 - RCS 3.4*

011 Pressurizer Level Control X

K2.02 - PZR heaters 3.1 033 Spent Fuel Pool Cooling X

Kl.05 - RWST 2.7*

035 Steam Generator X

AI.OI-S/G wide and 3.6 narrow range level during startup, shutdown, and normal operations 041 Steam Dump/Turbine Bypass X

K6.03 - Controller and 2.7 Control positioners, including ICS, SIG, CRDS 045 Main Turbine Generator X

A4.06 - Turbine stop valves I 2.8 056 Condensate X

A2.04 - Loss ofcondensate 2.6 pumps 071 Waste Gas Disposal X

K5.04 - Relationship of 2.5 hydrogen/oxygen concentrations to 072 Area Radiation Monitoring X

flammability K4.03 - Plant ventilation 3.2*

systems 086 Fire Protection X

A3.02 - Actuation ofthe 2.9 FPS KIA Category Totals:

I 1

1 1

1 I

1 1

1 1

0 Group Point Total:

Points I

I 1

1 1

I 1

1 1

1 10 06/14/2011 11:58:20 am

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outlin<<~

Printed: 06/14/2011 Facility:

Salem Form ES-401-3 Generic Catel!orv KA KA Topic Imp Points Conduct of Operations 2.1.36 Knowledge ofprocedures and limitations 3.0 1

involved in c:ore alterations.

2.1.37 Knowledge ofprocedures, guidelines, or 4.3 1

limitations associated with reactivity management.

Category Total:

2 Equipment Control 2.2.12 Knowledge of surveillance procedures.

3.7 1

2.2.22 Knowledge oflimiting conditions for operations 4.0 1

and safety limits.

2.2.42 Ability to recognize system parameters that are 3.9 I

entry-level conditions for Technical Specifications.

Category Total:

3 Radiation Control 2.3.4 Knowledge of radiation exposure limits under

" ')

I j.

normal or emergency conditions.

2.3.11 Ability to control radiation releases.

3.8 1

Category Total:

2 Emergency ProcedureslPlan 2.4.18 Knowledge ofthe specific bases for EOPs.

3.3 I

2.4.27

)f "fire in the plant" procedure.

3.4 1

2.4.43 Knowledge ofemergency communications 3.2 1

systems and techniques.

Category Total:

3 Generic Total:

10 06/14/2011 11:58:26 am

ES-401 Record of Rejected KlAs Salem 09-01 NRC Exam Form ES-401-4 TierlGroup Randomly Reason for Rejection Selected KIA R0211 003 K3.05 Salem does not have an ICS. Automatically randomly replaced with 003 K3.02.

R02/I 076 A4.04 Sampled on CERT Exam. Automatically randomly replaced with 013 AI.04.

Salem does not have a "core protection calculator". Automatically randomly replaced with 003 RO 211 012 K6.07 K6.04 R0212 034 K4.01 Sampled on CERT Exam. Automatically randomly replaced with 072 K4.03 j Salem docs not have reactor building closed loop cooling water system. l\\utomatically randomly R02/I 076 K2.04 replaced with 076 K 2. 0 1 _

Knowledge ofnew and spent fuel movement procedures does not apply to a SG tube leak.

SRO 111 0372.1.42 Automatically randomly replaced with E15 2.2.7.

Generic KA (knowledge ofthe process for conducting special or infrequent tests) does not apply to SRO 111 b152.2.7 containment f100ding. Automatically randomly replaced with 059 2.2.36.

SRO 2/2 056 A2.04 Sampled on RO exam. Automatically randomly replaced with 011 A2.01.

SRO 2/2 002 A2.03 Oversample ofnatural circulation (loss of forced flow in RCS)operations. Automatically randomly replaced with 041, A2.02.

r---------

ES-401, Page 27 of 33

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

SALEM Date of Examination:

09/19/2011 Examination Level:

RO

  • SRO Operating Test Number:

09-01 NRC Administrative Describe activity to be performed Type Topic (See Note)

Cocle*

Determine the required actions based on abnormal Secondary Plant chemistry Conduct of R, N conditions.

Operations 2.1.34 Knowledge of primary and secondary plant chemistry limits. SRO-3.5 Determine the TSAS for a dropped rod and complete the applicable log Conduct of R,O 2.1.18 Ability to make accurate, clear, and consise logs, records, status boards, Operations and reports. SRO-3.8 Review completed Shutdown Margin calculation.

Equipment Control R,II/I 2.2.12 Knowledge of surveillance procedures SRO 4.1 Select release path (and mark up prints) for Radioactive Liquid Release.

Radiation Control R,O 2.3.6 Ability to approve release permits SRO-3.8 Classify Emergency / Non-Emergency Events, and complete the ICMF.

Emergency Plan S,IVII,P 2.4.29 Knowledge of the I::mergency Plan SRO 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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:

09/19/11 Examination Level:

RO SRO Operating Test Number:

09-01 NRC Administrative Describe activlity to be performed Type Topic (See Note)

Code*

Respond to a Void in the Reactor Vessel (calculate RPV Head vent time)

Conduct of R,D 2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc.

Operations RO-3.9 TCAF a Loss of Spent Fuel Pool Cooling. (Calculate the time at which Spent Fuel Pool temperature will exceed Design Bases)

Conduct of 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as R,N Operations responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supportin!~ instrumentation. RO-3.9 Prepare a manual tagout.

Equipment Control R,M 2.2.13 Knowledge of tag~ling and clearance procedures. RO 4.1.

Radiation Control N/A Perform the duties of the Secondary Communicator during an Alert Emergency S,D,P 2.4.39 Knowledge of ROs responsibilities in Emergency Plan implementation.

Procedures I Plan RO 3.9 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/lin-Plant System Outline Form ES-301-2 Facility:

SALEM Date of Examination:

09/19/11 Exam Level: RO SRO-I ISRO-ul Operating Test No.:

09-01 NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

AA 1.23, AA 1.27 All KJA values >2.5 System / JPM Title Type Code*

Safety Function a) b)

c)

Respond to a PZH Spray Valve Failure (010 A4.01 RO-3.7 SRO-3.5)

A,D,L,S, P 3

d) e) TCAF Turbine Trip <P-9 (Loss of Tank exp tank level)

(Generic 2.4.31 RO-4.2 SRO-4.1)

A,N,S 4(sec) f)

g) h) TCAF loss of the CCW system.

(008 A4.01 RO-3.3 SRO-3.1)

N,EN,S 8

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

Locally control Charging Flow (APE 068 AA1.22 RO-4.0 SRO-4.3 D,E, R 2

j)

NA k) TCAF Control Room Evacuation (Trip the Main Turbine, Open the Main Generator Exciter Field Breaker, Trip the SGFPs.) APE 068 AA1.04, D, E 6

@ 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 / SRO-I / SRO-U (A)lternate path 4-6/ 4-6 / 2-3 (C)ontrol room (D)irect from bank

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

~1 /

~ 1 / ~ 1 (EN)gineered safety feature

- / - / ~ 1 (control room system)

(L)ow-Power / Shutdown

~1 / ~1 /

~1 (N)ewor (M)odified from bank including 1 (A)

~2 /

~ 2 / ~ 1 (P)revious 2 exams

~3/~3 / ~ 2 (randomly selected)

(R)CA

~1 /

~ 1/ ~ 1 (S)imulator

ES-301 Control Room Systems/ln-Plant System Outline Form ES-301-2 Facility:

SALEM Date of Examination:

09/19/11 Exam Level:

RO

~]J SRO-U Operating Test No.:

09-01 NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Safety Function System / JPM Title Type Code*

a) Respond to successive dropped control rods at power (003 AA2.03 RO-~L6 SRO-3.8)

A,D,S,P 1

b) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using head vent valves)

A,L,N,S 2

(EPE E05 EA 1.1 HO-4.1 SRO-4.0}

c)

Respond to a PZR Spray Valve Failure (010 A4.01 RO-3.7 SRO-3.5)

A,D, L,S, P 3

d) TCAF Loss of RHR w/second loop available (APE 025 AA 1.09 RO-3.2 SRO-3.1)

D,L,S 4(pri) e) TCAF Turbine Trip <P-9 (Loss of Tank exp tank level)

(Generic 2.4.31 RO-4.2 SRO-4.1)

A,N,S 4(sec) f) N/A g) TCAF Undercompensated IRNI in TRIP-2 (EPE 007 EA 1.05 RO-4.0 SRO-4.1 A,L,D,S 7

h) TCAF loss of the CCW system.

(008 A4.01 RO-3.3 SRO-3.1}

N,EN,L,S 8

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

Locally control Charging Flow (APE 068 AA1.22 RO-4.0 SRO-4.3 D,E, R 2

j)

Reset TDAFW pump steam inlet trip valve 2MS52 (APE 068 AA1.02 RO-4.3 SRO-4.5)

D, E, R, P 4 (sec) k)

TCAF Control Room Evacuation (Trip the Main Turbine, Open the Main Generator Exciter Field Breaker, Trip the SGFPs.) APE 068 AA1.04, D, E 6

AA1.23, AA1.27 All KIA values >2.5

@ 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 / SRO-I / SRO-U (A)lternate path 4-6/ 4-6 / 2-3 (C)ontrol room (D)irect from bank

~9 / ~8 / ~ 4 (E)mergency or abnormal in-plant

.:=:1

/

.:=: 1 /.:=: 1 (EN)gineered safety feature

- / - /.:=: 1 (control room system)

(L)ow-Power / Shutdown

.:=:1

/.:=:1 /.:=:1 (N)ewor (M)odified from bank including 1 (A)

.:=:2 /

.:=: 2 /.:=: 1 (P)revious 2 exams

~:3/~3 / ~ 2 (randomly selected)

(R)CA

.:=:1

/

.:=: 1/.:=: 1 (S)imulator

ES-301 Control Room Systems/In-Plant System Outline Form ES-301-2 Facility:

SALEM Date of Examination:

09/19/11 Operating Test No.:

09-01 NRC Exam Level:

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

M 1.23, M 1.27 All KIA values >2.S System 1JPM Title Type Code*

Safety Function a) Respond to successive dropped control rods at power (003 M2.03 RO-3.6 SRO-3.8)

A,D,S,P 1

b) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using head vent valves)

(EPE EOS EA1.1 RO-4.1 SRO-4.01 A,L,N,S 2

c)

Respond to a PZR Spray Valve Failure (010 A4.01 RO-3.7 SRO-3.5)

A,D,L,S,P 3

d) TCAF Loss of RHR w/second loop available (APE 025 AA 1.09 RO-3.2 SRO-3.1)

D,L,S 4{pri) e) TCAF Turbine Trip <P-9 (Loss of Tank exp tank level)

(Generic 2.4.31 RO-4.2 SRO-4.1)

A,N,S 4{sec) f)

Transfer 4KV Group busses to APT, trip Rx upon ATWT (062 A4.01 RO-3.3 SRO-3.1)

A,N,S 6

g) TCAF Undercompensated IRNI in TRIP-2 (EPE 007 EA1.05 RO-4.0 SRO-4.1 A,L,D,S 7

h) TCAF loss of the CCW system.

I (008 A4.01 RO-3.3 SRO-3.1)

N,EN,L,S 8

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

Locally control Charging Flow (APE 068 M 1.22 RO-4.0 SRO-4.3 D,E, R 2

j)

Reset TDAFW pump steam inlet trip valve 2MSS2 (APE 068 M1.02 RO-4.3 SRO-4.5)

D,E,R,P 4 (sec) k) TCAF Control Room Evacuation (Trip the Main Turbine, Open the Main Generator Exciter Field Breaker, Trip the SGFPs.) APE 068 M1.04, D,E 6

@ 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 / 2-3 (C)ontrol room (D)irect from bank

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

>1 /

~ 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~ 1

{P)revious 2 exams

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

(R)CA

~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.: 09-01 NRC Examiners:

Operators:

Initial Conditions: 100% power. Personnel are in containment investigating elevated unidentified RCS leakrate, currently 0.3 gpm. 21 AFW pp CIT for oil leak repair.

Turnover: Maintain 100% power.

Event Malf. No.

Event Event Type*

No.

Description I

1 Controllin~l PZR level ch failure (TS)

CRS/RO C

2 RCS leak (TS)

ALL N

3 Power Reduction (directed based on RCS leak)

ALL M

4 SBLOCA (-200 gpm)

ALL C

5 Failure of ;3utomatic High Head injection CRS/RO I

C 6

AFW fails to automatically actuate CRS/PO C

7 SEC fails to reset CRS/PO C

8 SBLOCA escalation (ECCS flow re-initiation in TRIP-3)

CRS/RO

  • (N)ormal, (R)eactlvity, (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-2 Op-Test No.: 09-01 NRC Examiners:

Operators:

Initial Conditions: 70% power, MOL.

Turnover: Raise power to 75% at 10% per hour, place 3rd Condensate pump lIS, continue power ascension to 90%power.

Event Malf. No.

Event I

Event Type" No.

Description I

I I

I N

1 Raise Powl~r ALL C

2 In service ABV Exhaust fan trip (TS)

CRS/PO I

3 PR NI Channel fails (TS)

ALL 4

C 21 SGFP oil leak 5

R ALL 21 SGFP trip, MT fails to auto runback (PO manually intiates turbine runback, RO uses manual rod control) 6 M

ALL 22 SG Tubl~ leak I tube rupture 7

C ALL ATWT/FRSM 8

C CRS/PO Loss of condenser vacuum during SGTR cooldown I

I I

I

  • (N)ormal, (R)eactlVlty, (I)nstrument, (C)omponl~nt, (M)qJor 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.: 09-01 NRC Examiners:

Operators:

Initial Conditions: 100%, EOL. 21 CFCU is CIT. PZR Pressure channell! is O/S for calibration.

Turnover: Maintain current power.

Event Malf. l'Jo.

Event Event Type*

No.

Description I

C 1

CCW pump trip (TS) (standby pp fails to auto start)

CRS/RO C

2 Loss of 2B 4KV bus (TS)

ALL I

R 3

Power reduction to <100%.

ALL 4

M Steam Leak in containment C

5 ATWT, (auto demand-no trip-manual trip works)

RO C

6 MSLI fails, Multiple SG depressurization ALL I

PZR Pressure Channel IV fails high. PORV PR2 opens (after CRSRO PORV Status CAS in LOSC-2 is read.)

  • (N)ormal, (R)eactJvlty, (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-4 (Spare)

Op-Test No.: 09-01 NRC Examiners:

Operators:

Initial Conditions: 100% power, EOl. 21 CFCU is CIT Turnover: Maintain current power.

I Event No. I Malf. No.

I Event Type* I Event Description I

1 I

PO SG NR Ch failure (TS) 2 R

All Stator Water run back (AFD TS) 3 C

CRS/RO RCS leak M

4 lBlOCA CRSJRO C

5 CS fails to actuate CRSRO C

6 lo Head ECCS fails to actuate All C

7 Charging pump cavitation RO

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