ML113340036

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Final Outlines (Folder 3)
ML113340036
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/11/2011
From:
Public Service Enterprise Group
To:
Operations Branch I
JACKSON D RGN-I/DRS/OB/610-337-5306
Shared Package
ML110030673 List:
References
TAC U01830
Download: ML113340036 (21)
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Text

ES-401 PWR EX;3mination Outline Form ES-401-2 Facilitl!: Salem Printed: 09/16/2011 Date Of Exam: 09/26/2011 RO KJA 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 Emergenc

~

2 0 0 0 N/A 0 0 2 2 4

& N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

2 0 0 0 0 0 0 0 0 0 0 0 I 2 1 3

Gi Plant Systems Tier ..,

0 0 0 0 0 0 0 0 0 0 5 .J 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 2 1 2 2 Note:
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than 1v110).
2. The point total for each group and tier in the proposed outline must rr:atch 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 1 and 2 shall bl:; 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 catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

09/16/2011 6:19:02 pm

PWR SRO Examination Outline Printed: 09116/2011 Facility: Salem ES 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group I Form ES-401-2 E/APE # I Name I Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points 000015/000017 RCP Malfunctions / 4 X AA2.10 - When to secure RCPs on loss 3.7 1 of cooling or seal injection 000025 Loss of RHR System / 4 X 2.4.6 - Knowledge ofEOP mitigation 4.7 1 strategies.

000040 Steam Line Rupture - Excessive X AA2.02 - Conditions requiring a reactor 4.7 1 Heat Transfer / 4 trip 000062 Loss of Nuclear Svc Water / 4 X AA2.02 - The cause of possible SWS 3.6 1 loss 000065 Loss ofInstrument Air /8 X 2.1.36 - Knowledge of procedures and 4.1 1 limitations involved in core alterations.

W/E05 Inadequate Heat Transfer - Loss of X 2.4.6 - Knowledge ofEOP mitigation 4.7 1 Secondary Heat Sink / 4 strat<:gies.

KIA Category Totals: 0 0 0 0 3 3 Group Point Total: 6 09/16/2011 6:18:36 pm

PWR SRO Examination Outline Printed: 09116/2011 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 2 Form £S-401-2 E/APE # / Name / Safety Function KI K2 K3 Al A2 G KATopic Imp. Points 000059 Accidental Liquid RadWaste ReI. I X 2.2.36 - Ability to analyze the effect of 4.2 1 9 maintenance activities, such as degraded powE.r sources, on the status ofiimiting

.......... conditions for operations.

WlE07 Inad. Core Cooling I 4 X EA2.1 - Facility conditions and 4.0 1 selection of appropriate procedures during abnormal and emergency operations WiEOS RCS Overcooling - PIS i 4 X EA2.1 - Facility conditions and 4.2 1

... selection of appropriate procedures during abnormal and emergency

          • operations WiE09 Natural Circ. / 4 ~11- Knowkdg' ofobnorrna1 4.2 I dition procedures.

KIA Category Totals: 0 0 0 0 22 Group Point Total: 4 09/16/2011 6:18:41 pm

PWR SRO Examination Outline Printed: 09/16/2011 Facility: Salem Plant Systems - Tier 2/ Group 1 Form ES-40t-2 ES - 401 SyslEvol # / Name Kl K2 K3 K4 K5 K6 At A2 A3 A4 G KA Topic ~

006 Emergency Core Cooling X 2.4.22 - Knowledge of the 4.4 1 bases for prioritizing safety functions during abnormaVemergency operations.

010 Pressurizer Pressure Control X A2.03 - PORV failures 4.2 1 r=gineered Safety Features X A2.03 Rapid 4.7 I 1 Ion depressurization I 064 Emergency Diesel Generator X A2.22 Potential automatic 2.8* 1

. safety sequences (water/C02) and electrical damage (loose wires) 076 Service Water X 2.2.37 - Ability to determine 4.6 1 operability andlor availability of safety related equipment.

KIA Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5

'1 09/16/2011 6:18:46 pm

PWR SRO Examination Outline Printed: 09116/2011 Facility: Salem Plant Systems - Tier 21 Group 2 Form ES-401-2 ES - 401 SyslEvol # / Name Kt K2 K3 K4 K5 K6 At A2 A3 A4 G KA Topic Imp. Points 011 Pressurizer Level Control X A2.01 - Excessive letdown 3.1 1 034 Fuel Handling Equipment X 2.4.35 - Knowledge of local 4.0 1 auxiliary operator tasks during an emergency and the resultant operational effects.

041 Steam Dump/Turbine Bypass X ....

A2.02 - Steam valve stuck 3.9 I Control open KIA Category Totals: 0 0 0 o~ 0 0 2 0 0 1 Group Point Total: 3 09/16/2011 6:18:51 pm

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 09/16/20 II Facilitv: Salem "Form ES-401-3 Generic Cateliorv KA Topic Conduct of Operations 2.1.23 Ability to perform specific system and integrated 4.4 I plant procedures during all modes of plant operation.

2.1.32 Ability to explain and apply system limits and 4.0 I precautions.

Category Total: 2 Equipment Control 2.2.23 Ability to track Technical Specification limiting 4.6 1 conditions for operations.

Category Total: 1 Radiation Control 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: 2 Emergency Procedures/Plan 2.4.27 Knowledge of "fire in the plant" procedure.

2.4.38 Ability to take actions called for in the facility 4.4 1 emergency plan, including supporting or acting as emergency coordinator if required.

Category Total: 2 Generic Total: 7 09/16/2011 6:18:57 pm

\

PWR Examination Outline Form ES-401-2 EStW1 Ea~ Salem Printed: 09/16/2011 Date Of Exam: 09/26/2011 r---\":-.~.,'\

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 "

.J 3 -'" .J 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 3 2 3 2 28 0 0 0 2.

Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 0 , 0 0 0 Systems Tier .., 0 0 0 4 3 4 4 3 3 4 4 .J 4 ')

.:.. 38 Totals 1 2 3 4 1 2 3 4 3, Generic Knowledge And 10 0 Abilities Categories ..,

2 .J 2 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 SRO-only outlines (Le" 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 0.1. 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 f(jAs 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 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 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 paint totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

09/16/2011 3:34:46 pm

PWR RO Examination Outline Printed: 09/16/2011 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function Kl K2 K3 Al 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 of less than or equal 3.9 1 3 to one hour Technical Specification action statements for systems.

000009 Small Break LOCA / 3 X EK3.28 - Manual ESFAS initiation 4.5 1 requirements 000011 Large Break LOCA / 3 X 2.1.8 - Ability to coordinate persomlel 3.4 1 activities outside the control room.

000015/000017 RCP Malfunctions /4 X AK2.07 - RCP seals 2.9 1 000022 Loss ofRx Coolant Makeup /2 X AKl.Ol- Consequences of thermal 2.8 1 shock to RCP seals 000025 Loss of RHR System / 4 X AKl.Ol- Loss ofRHRS during all 3.9 1 modes of operation 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 X AAl.03 - Pressure control when on a 3.6 1 Malfunction / 3 steam bubble

..., ')*

000029 ATWS / 1 X EA2.04 - CVCS centrifugal charging .J._ 1 pump operating indication 000038 Steam Gen. Tube Rupture / 3 X EKl.02 - Leak rate vs. pressure drop 3.2 1 000040 Steam Line Rupture - Excessive X AK2.01 - Valves 2.6* 1 Heat Transfer / 4 000054 Loss of Main Feedwater / 4 X AK3.01- Reactor and/or turbine trip, 4.1 1 manual and automatic 000056 Loss of Off-site Power / 6 X AAl.08 - HV AC chill water pump and 2 .J-* 1 unit 000062 Loss of Nuclear 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 I 3 X EA1.2 - Operating behavior 3.6 1 characteristics of the facility W/E11 Loss of Emergency Coolant Recirc. / X EK2.1 - Components, and functions of 3.6 1 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 09/16/2011 3:34:17 pm

PWR RO Examination Outline Printed: 09il6/20 11 Facility: Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 2 Form ES-401-2 EIAPE # I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000003 Dropped Control Rod / 1 X AK3.09 - Recording of group bank 3.0* 1 position for dropped rod (reference point used to withdraw dropped rod to equal height with other rods in the bank) 000032 Loss of Source Range NI I 7 X .....

. AKl.OI- Effects of voltage changes on 2.5 1

, .. performance 000033 Loss of Intermediate Range ).JI I 7 X AA2.01- Equivalency between 3.0 I source-range, intermediate-range, and power-range channel readings I*..**.

2.8* 1 000051 Loss of Condenser Vacuum I 4 X .  :. ,:>. AK3.01- Loss of steam dump capability upon loss of condenser vacuum 000060 Accidental Gaseous Radwaste ReI. I X AK2.02 - Auxiliary building ventilation 2.7 1 9 ............ system 000074 lnad. Core Cooling I 4 X . EK2.01 - RCP 3.6 1 W/E03 LOCA Cooldovvn - Depress. / 4 X EKl.l - Components, capacity, and 3.4 1  !

function of emergency systems W/E13 Steam Generator Over-pressure / 4 X ". EA 1.2 - Operating behavior 3.0 1 characteristics of the facility W/El6 High Containment Radiation / 9 X EA2.2 - Adherence to appropriate 3.0 I procedures and operation within the limitations in the facility's license and

.... amendments KIA Category Totals: 2 2 2 1 2 0 Group Point Total: 9 09/16/2011 3:34:23 pm

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PWR RO Examination Outline Printed: 09116/20 II Facility: Salem Plant Systems - Tier 2/ Group 1 Form E8-401-2 ES - 401 8ys/Evoi # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K6.04 - Containment 2.S 1 isolation valves affecting RCP operation 003 Reactor Coolant Pump X K3.02 - S/G 3.5 1 004 Chemical and Volume Control X K6.05 - Sensors and 2.5 1 detectors I 005 Residual Heat Removal X 2.4.46 - Ability to verifY that 4.2 1 the alarms are consistent

. ,.: with the plant conditions .

005 Residual Heat Removal X CCWS 006 'rgen...] Core Cooling X K4.06 - Recirculation of 2.7 1 minimum flow through 007 Pressurizer Relief/Quench Tank ITT X m pumps A3.0J- Components which discharge to the PRT 2.7* 1 OOS Component Cooling Water X K4.02 - Operation of the 2.9 1 surge tank, including the associated valves and controls 010 Pressurizer Pressure Control X ***** K3.01 - RCS 3.S!=I=

010 Pressurizer Pressure Control X A4.03 - PORV and block 4.0 1

,' valves 012 Reactor Protection X 2.4.6 - Knowledge ofEOP 3.7 1 mitigation strategies .

012 Reactor Protection X . :** :. K4.06 - Automatic or 3.2 1 manual enable/disable of RPS trips 013 Eng. Safety Features X A4.0 1- ESF AS-initiated 4.5 1 Actuation equipment which fails to actuate 013 Fl.,;;' 'IOU. Safety Features X A 1.04 - S/G level 3.4 1 Actuation 022 Containment Cooling X K3.02 - Containment 3.0 1 instrumentation readings 026 Containment Spray X A4.01 - CSS controls 4.5 1 026 Containment Spray X A3.01- Pump starts and 4.3 1 correct MOV positioning 039 Main and Reheat Steam 039 Main and Reheat Steam D+/- X X Al.06 - Main steam pressure K5.01- Definition and causes of steam/water 3.0 2.9 1

1 hammer 059 Main Feedwater X A2.l2 - Failure offeedwater 3.1* 1

  • regulating valves 061 AuxiliaryiEmergency X j K5.03 - Pump head effects 2.6 f1 Feedwater 062 AC Electrical Distribution X I*****

ill .... when control valve is shut KI.OJ - DC d;str;bution 3.5 1 09/16/2011 3:34:29 pm

P\VR RO Examination Outline Printed: 09il6/20 11 Facility: Salem Plant Systems - Tier 2 / Group 1 Form ES-401-2 SyslEvol # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 063 DC Electrical Distribution X A2.0 I - Grounds 2.5 1 064 Emergency Diesel Generator X K2.02 - Fuel oil pumps 2.8* 1 073 Process Radiation Monitoring X A2.01- Erratic or failed 2.5 1 power supply 076 Service Water X K2.0 1 - Service water 2.7* I 078 Instrument Air X Kl.04 - Cooling wa 1 compressor 103 Containment X I A 1.0 1 - Containment 3.7 I I ..

pressure, temperatW'e, and humidity KIA Category Totals: 3 2 3 3 2 EJ::13 2 3 2 Group Point Total: 28 09/16/2011 3:34:29 pm 2

PWR RO Examination Outline Printed: 09116/2011 Facility: Salem ES - 401 Plant Systems - Tier 2 1 Group 2 Form ES-401-2 SyslEvol # 1 Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K3.02 - RCS 3.4* 1 011 Pressurizer Level Control X K2.02 - PZR heaters 3.1 1 033 Spent Fuel Pool Cooling X I, K1.0S - RWST 2.7* 1 03 S Steam Generator I I X A 1.0 1 - S/G wide and 3.6 1 narrow range level during startup, shutdown, and I

normal operations 04 1 Steam Dump/Turbine Bypass I I

X K6.03 - Controller and 2.7 1 Control positioners, including rcs,

'I S/G, CRDS I

045 Main Turbine Generator i X A4.06 - Turbine stop valves 2.8 1 OS6 Condensate :1 X A2.04 - Loss of condensate 2.6 1 I pumps 071 Waste Gas Disposal Xl, KS.04 - Relationship of 2.S 1 i

II hydrogen/oxygen i

concentrations to

'I flammability 072 Area Radiation Monitoring X K4.03 - Plant ventilation 3.2* 1

1 systems 086 Fire Protection X A3.02 - Actuation of the 2.9 I I FPS KIA Category Totals: 1 1 1 1 1 1 1 1 1 1 0 Group Point Total: 10 09/16/2011 3:34:35 pm

Generic Knowledge and Abilities Outline (Tier 3)

P\VR RO Examination Outline Pnnted: 09116/2011 Facility: Salem Form ES-401-3 Generic Catellorv KA Topic Conduct of Operations 2.1.36 Knowledge ofproceclures and limitations 3.0 1 involved in core alterations.

2.1.37 Know ledge of procedures, guide lines, 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 of limiting conditions for operations 4.0 1 ard safety limits.

2.2.42 Ability to recognize system parameters that are 3.9 I entry-level conditions for Technical S peci fications.

Category Total: 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.

2.3.11 Ability to control radiation releases. 3.8 1 Category Total: 2 Emergency ProcedureslPlan 2.4.18 Knowledge of the specific bases for EOPs. 3.3 1 2.4.27 Knowledge of "fire in the plant" procedure. 3.4 1 2.4.43 Knowledge of emergency communications 3.2 1 systems and techniques.

Category Total: 3 Generic Total: 10 09/16/2011 3:34:41 pm

ES-301 Administrative Outline Form ES-301-1 Facility: SALEM Date of Examination: 09/19/11 Examination Level:

  • RO SRO Operating Test Number: 09-01 NRC I

Administrative Describe activity 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 I 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 i operations, and supporting instrumentation. RO-3.9 Prepare a manual tagout.

Equipment Control R,M 2.2.13 Knowledge of tagging 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 Knowled~le of ROs responsibilities in Emergency Plan tmplementation.

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)il1ulator, or Class(R)oom (D)irect from bank, (.:::3 for ROs;.:::4 for SROs & RO retakes)

(N)ewor (M)odified from bank (;::1)

(P)revious 2 exams (.:::1; randomly selected)

ES-301 Administrative Outline Form ES-301-1 Facility: ~AII=M 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}

Code*

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,D 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,M 2.2.12 Knowledge of' surveillance procedures SRO 4.1 Select release path (and mark up prints) for Radioactive Liquid Release.

Radiation Control R,D I

2.3.6 Ability to approve release permits SRO-3.8 Classify Emergency I Non-Emergency Events, and complete the ICMF.

Emergency Plan S,M,P 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 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 SystemQl:I~l_in_e______ Fo_r_m_E_S_-3_0_1_-_2 Facility: SALEM Date of Examination: 09/19/11 Exam Level: SRO-I 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)

System I JPM Title Type Code* Safety Function a) Respond to successive dropped control rods at power (003 AA2.03 RO-3.6 SRO-3.8) A,D,S,P 1 Raise ECCS Accumulator Level with a Safety Injection Pump (006 A4.07 RO-4.4 SRO- 4.4) D,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) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using head vent valves) A,L,N,S 4 (pri)

(EPE E05 EA 1.1 RO-4.1 SRO-4.0) e) TCAF Turbine Trip <P-9 (Loss ofTAC 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.

(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 1 MS52 (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 I SRO-II SRO-U (A)lternate path 4-61 4-6 / 2-3 (C)ontrol room (D)irectfrom bank  :;::9 / :;::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 ~1 I ~11 ~1 (N)ewor (M)odified from bank including 1 (A) 2:2 I 2:2/2:'"

(P)revious 2 exams < 3 I < 3 I < 2 (randomly selected)

(R)CA 2:1 I 2: 11 2: 1 (S)imulator

ES-301 Control Room Systems/In-Plant System Outline Form ES-301-2 Facility: SALEM Date of Examination: 09/19/11 Exam Level: RO ISRO-II 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)

System 1 ~IPM Title Type Code* Safety Function a) Respond to successive dropped control rods at power (003 AA2.03 RO-3.6 SRO-3.8) A,D,S,P 1 b) Raise ECCS Accumulator Level with a Safety Injection Pump (006 A4.07 RO-4.4 SRO- 4.4) D,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) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using head vent valves) A,L,N,S 4 (pri)

(EPE E05 EA 1.1 RO-4.1 SRO-4.0) 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 EA1.05 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 SHO-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 1 MS52 (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 dilferent 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 1 SRO-II SRO-U (A)lternate path 4-61 4-6 1 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 Systemslln-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)

System / JPM Title I Safety Function a) b)

c) Respond to a PZR Spray Valve Failure (010 A4.01 RO-3.7 SRO-3.5) A. 0, L, S, P 3 d)

F 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, 0, 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.

  • T~pe Codes: Criteria for RO 1 SRO-II SRO-U (A)lternate path 4-6/ 4-6 I 2-3 (C)ontrol room (D)irect from bank :s 9 / :s8 1:s4 (E)mergency or abnormal in-plant >1 / > 1 I ~ 1 (EN)gineered safety feature / - 1 ~ 1 (control room system)

(L)ow-Power / Shutdown ~1 / / ~1 (N)ewor (M)odified from bank including 1 (A)  ;::2 / ~ 2 / > 1 (P)revious 2 exams .:::3/:s3 / :s 2 (randomly selected)

(R)CA > 1 / > 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, BOl. 21 AFW pp CIT for oil leak repair. 21 CFCU is CIT. PZR Pressure channel II is O/S for calibration.

Turnover: Maintain 100% power.

Event Malf. No. Event Event Type*

No. Description I

1 PROO17A Controlling PZR level ch failure (TS)

CRS/RO C

2 RCOOO2 I=<CS leak (TS)

ALL N

3 Power Reduction (directed based on RCS leak)

All M

4 RCOO02 SBlOCA (-100 gpm)

ALL RP0342 C 5 Failure of automatic High Head injection RP0343 CRS/RO AF0182A C

6 RP318E2 AFW fails to automatically actuate CRS/PO O/R B606 C

7 O/R C206 SEC fails to reset CRS/PO C

8 RCOOO2 SBlOCA escalation (ECCS flow re-initiation in TRIP-3)

CRS/RO CT's 1. Establish hi head ECCS. 2. Initiate AFW flow.

3.Re-start ECCS pps

  • (N)ormal, (R)eactlVlty, (I)nstrument, (C)-omponent, (M)aJor O/R ::: Override 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. 25 Service Water pump is CIT for strainer work.

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

Event Malf. No. Event Event Type* I No. Description N

1 Raise Power ALL C

2 O/RAG04 In service A8V Exhaust fan trip (TS)

CRS/PO I

3 NI0193A PR NI Channel fails (TS)

ALL 4 BF0105A C 21 SGFP oil leak EH0327 R 21 SGFP trip, MT fails to auto runback (PO manually 5

O/R 8433 I ALL initiates turbine runback, RO uses manual rod control) i M 6 SGOO78B 22 SG Tube leak I tube rupture ALL RP0058 RPOO59A RPOO598 7 C O/R 8440 ATWT/FRSM ALL OIR 8441 O/R C310 O/R C510 CNOO86 C 8 I Loss of condenser vacuum during SGTR cooldown MSOO93 CRS/PO 3 CT, insert neg reactivity, isolate rupt SG, cooldown to i

target temp I I il

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I

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.

Turnover: Secure the Containment Pressure Relief in progress. Maintain current power.

Event Malf. No. Event Event Type*

No. Description N 2VC5 (CIV) fails to shut when securing containment 1 CC0172B CRS/PO pressure relief. (TS)

O/R C80a C Loss of 2B 4KV bus (TS) and subsequent failure of 22 AFW 2

O/R C80S ALL pump to stop.

R 3 Power reduction to <100%.

All 4 MSOO88Cr M StE~am leak in containment.

I C

S RPOO58 ATWT, (auto demand-no trip-manual trip works)

RO MSOO90Cr M

6 VlO420 MSLI fails, Multiple SG depressurization, All 423 I 7 RP0276A,B C Auto CS & Phase B isolation fails.

RP0277A,B CRSRO Recovery of single SG in lOSC-2.

CTs man init trip, man inti phase B, lower AFW flow to nit 1 E41bm/hr

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