ML16007A430

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301 Draft Administrative Documents
ML16007A430
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/07/2016
From:
Division of Reactor Safety II
To:
Virginia Electric & Power Co (VEPCO)
References
Download: ML16007A430 (24)
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Text

ES-401,Rev.9 PWR Examination Outline Form ES-401-2 Facility: ie Date of Exam: $P TEmLEA?

RO K/A Category Points SRO-OnIy Points Tier Group 1(11(1K K K K{[A A A G A2 G* Total 112j3 4 5 6[1 2 3 4 Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal Plant 2

T*

N/A 2 1 N/A 9 2 2 4 Evolutions Tier Totals 5 5 4 5 27 5 5 10 i 3 2 3 2 2 3 22 3 3 28 3 2 5 L

2.

Plant 2 1 1 1 0 1 1 1 1 1 1 1 10 Lf[i 2 3 Systems TierTotals 4 3 3 3 f- 3 ---- .- 38 4 8

3. Generic Knowledge and Abilities I 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 1 2 I Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., exceptfor one category in Tier 3 ofthe SRO-only outline, the i1er Totals@

in each K/A 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 11 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted andjustified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section 0.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 KIAs 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 I and 2 from the shaded systems and K/A categories.
7. *The generic (G) KIAs in Tiers I and 2 shall be selected from Section 2 ofthe KIA Catalog, butthe topics must be relevant to the applicable evolution or system. Refer to section D.1 .b of ES-401 for the applicable KAs.
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 # I does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to I 0 CFR 55.43..

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor 007EA2.06 Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space 008AA1.04 Accident / 3 000009 Small Break LOCA / 3 009EK3.11 000011 Large Break LOCA / 3 011EK2.02 000015/17 RCP Malfunctions / 4 015AK1.04 000022 Loss of Rx Coolant Makeup / 2 022AK1.04 000025 Loss of RHR System / 4 025AA1.04 000026 Loss of Component Cooling 026AG2.2.44 Water / 8 000027 Pressurizer Pressure Control 027AA2.02 System Malfunction / 3 000029 ATWS / 1 029EA2.01 000038 Steam Gen. Tube Rupture / 3 038EK1.02 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat 040AG2.1.30 Transfer / 4 000054 (CE/E06) Loss of Main 054AK3.05 054AG2.4.18 Feedwater / 4 000055 Station Blackout / 6 055EK3.02 000056 Loss of Off-site Power / 6 056AA2.75 000057 Loss of Vital AC Inst. Bus / 6 057AG2.4.50 000058 Loss of DC Power / 6 058AA1.02 000062 Loss of Nuclear Svc Water / 4 062AA2.04 000065 Loss of Instrument Air / 8 065AG2.4.3 W/E04 LOCA Outside Containment / 3 WE04EK2.2 W/E11 Loss of Emergency Coolant WE11EG2.1.2 Recirc. / 4 BW/E04; W/E05 Inadequate Heat WE05EA2.1 Transfer - Loss of Secondary Heat Sink / 4 l 000077 Generator Voltage and Electric 077AK1.02 l Grid Disturbances / 6 K/A Category Totals: Group Point Total: RO - 18 SRO - 6 18/6 ES-401, Page 22 of 33

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO8AA1 .04 Pressurizer Vapor Space Accident I 3 2.8 2.5 j fl J j j Feedwater pumps 009EK3.1 1 Small Break LOCA I 3 4.4 4.5 j J j Dangers associated with inadequate core cooling j

O11EK2.02 LargeBreakLOCA/3 2.6 2.7 j Pumps AR2.lO RCP Malfunctions I 4 2.8 2.8 J RCP indicators and controls 022AK1 .04 Loss of Rx Coolant Makeup I 2 2.9 3 Reason for changing from manual to automatic control of j j J charging flow valve controller 025AA1 .04 Loss of RHR System /4 2.8 2.6 j j Closed coohng water pumps 027AA2.02 Pressurizer Pressure Control System 8 9 El El El El El El El i El El El Normal values for RCS pressure Malfunction / 3 029EA0l ATWS /1 4.447 Reactor nuclear instrumentation El El El El El El El El El El 038EK1 .02 Steam Gen. Tube Rupture /3 3.2 3.5 El El El El El El El El El El Leak rate vs. pressure drop 040AG2.l .30 Steam Line Rupture Excessive Heat 4.4 4.0 Transfer / 4 El El El El El El El El El El Ability to locate and operate components, incluchngloc controls.

054AK3.05 Loss of Main Feedwater /4 4.64J El El El El El El El El El El HPI/PORV cycling upon total feedwater loss Page 1 of 2 09/22/2014 5:14 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 055EK3.02 Station Blackout I 6 4.3 4.6 J J j j Actions contained in EOP for loss of offsite and onsite power 057AG2.4.50 Loss of Vital AC Inst. Bus I 6 4.2 4.0 J ] Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

058AA1.02 Loss of DCPower I 6 3.1 3.1 j j J Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector 062AA2.04 Loss of Nuclear Svc Water / 4 2.5 2.9 The normal values and upper limits for the temperatures of the components cooled by SWS 077AK1 .02 Generator Voltage and Electric Grid 3.3 3.4 LI LI LI El El Over-excitation Disturbances / 6 WE04EK2.2 LOCA Outside Containment /3 3.840 El El El El El El El El El El Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

well EG2.l .2 Loss of Emergency Coolant Recirc. /4 4.64.6 El El El El El El El El El El Ability to execute procedure steps.

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ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 007EA2.06 Reactor Trip Stabilization

- - Recovery 4.3 4.5 J j j J Occurrence of a reactor trip

/1 026AG2.2.44 Loss of Component Cooling Water / 8 4.2 4.4 j Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 054AG2.4.18 Loss of Main Feedwater/4 3.3 4.0 [] Knowledge of the specific bases for EOPs.

056AA2.75 Loss of Off-site Power /6 3 3.2 J j j J CVCS makeup 065AG2.4.3 Loss of Instrument Air /8 3.7 3.9 El El El El El El El El El El Ability to identify post-accident instrumentation.

WEO5EA2.1 Inadequate Heat Transfer Loss of

- 3.4 4.4 ElElElElElElElElElEl Facility conditions and selection of appropriate Secondary Heat Sink /4 procedures during abnormal and emergency operations.

Page 1 of 1 09/22/2014 5:14PM

ES-401 3 Form ES-401-2 l ES-401 PWR Examination Outline Form ES-401-2 l Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO) l E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 001AA1.02 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 024AA2.01 000028 Pressurizer Level Malfunction / 2 028AG2.4.47 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 036AG2.2.37 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 060AK1.02 000061 ARM System Alarms / 7 061AA2.03 000067 Plant Fire On-site / 8 067AK3.02 l 000068 (BW/A06) Control Room Evac. / 8 068AA2.10 000069 (W/E14) Loss of CTMT Integrity / 5 069AG2.4.21 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 076AK2.01 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 WE15EG2.4.8 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 WE10EA1.3 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 WE08EK3.3 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: Group Point Total: RO - 9 SRO - 4 9/4 l ES-401, Page 23 of 33

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 AA1 .02 Continuous Rod Withdrawal I 1 3.6 3.4 J j Rod in-out-hold switch 028AG2.4.47 Pressurizer Level Maunction I 2 4.2 4.2 j jAbUity to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Accidental Gaseous Radwaste Rel. I 9 2.5 3.1 J j J j Biological effects on humans of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels 067AK3.02 Plant Fire On-site I 8 2.53.3 j j j j Steps called out in the site fire proteconpn,FPS manual and fire zone manual 068AA2.lO Control Room Evac. I 8 4.2 4.4 j j J Source range count rate 076AK2.O1 High Reactor Coant Activity /9 2.6 3 Process radiation monitors WEO8EK3.3 RCS Overcooling PTS /4

- 3.7 3.8 LI LI LI LI LI LI LI LI LI Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

WE1 OEA1 .3 Natural Circ. With Seam Void/ 4 3.4 3.7 LI LI LI LI LI LI ] LI LI LI LI bsired operating results during abnormal and emergency situations.

wel5EG2.4.8 Containment Floocng /5 3.84.5 LI LI LI LI LI LI LI LI LI LI Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Page 1 of 1 09/22/2014 5:14 PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 024AA2.O1 Emergency Boration / 1 3.8 4.1 Whether boron flow and/or MOVs are malfunctioning from plant conditions 036AG2.2.37 Fuel Handling Accident / 8 3.6 4.6 Ability to deterrne operability and/or availability of safety related equipment AA2.o3 ARM System Alarms /7 3 3.3 Setpoints for alert and high alarms 069AG2.4.21 Loss of CTMT Integrity /5 4O4.6 Knowledge of the parameters and logic used to assess the status of safety functions Page 1 of 1 09/22/2014 5:14PM

l ES-401 4 Form ES-401-2 l ES-401 PWR Examination Outline Form ES-401-2 l Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 003K4.04 004 Chemical and Volume 004K4.03 004A2.35 Control 005 Residual Heat Removal 005K2.03 005K6.03 006 Emergency Core Cooling 006A2.05 006K3.01 007 Pressurizer Relief/Quench 007A2.02 Tank 008 Component Cooling Water 008K1.01 010 Pressurizer Pressure Control 010K6.02 012 Reactor Protection 012K5.02 012G2.4.1 013 Engineered Safety Features 013G2.2.36 013K4.10 Actuation 022 Containment Cooling 022A4.03 022K1.02 022A2.04 025 Ice Condenser 026 Containment Spray 026A3.02 026A2.04 039 Main and Reheat Steam 039K3.04 059 Main Feedwater 059A1.07 059A4.01 061 Auxiliary/Emergency Feedwater 061K1.04 061K5.05 062 AC Electrical Distribution 062A4.04 063 DC Electrical Distribution 063K2.01 064 Emergency Diesel Generator 064K2.03 064G2.1.32 073 Process Radiation 073A1.01 Monitoring 076 Service Water 076G2.1.30 076G2.2.22 078 Instrument Air 078A3.01 103 Containment 103A1.01 l K/A Category Point Totals: Group Point Total: RO - 28 SRO - 5 28/5 ES-401, Page 24 of 33

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K4.04 Reactor Coolant Pump 2.8 3.1 Adequate cooling of RCP motor and seals 004K4.03 Chemical and VcumeControl 2.8 2.9 J J j J j Protection of ion exchangers (high letdown temperature will isolate ion exchangers) 005K2.03 Residual Heat Removal 2.7 2.8 j J RCS pressure boundary motor-operated valves Residual Heat Removal 2.5 2.6 j E LI El RHR heat exchanger 006A2.05 Emergency Core Cooling 3.4 3.5 Improper amperage to the pump motor 006K3.0l Emergency Core Cooling 4i4.2 RCS 007A2.02 Pressurizer Relief/Quench Tank 2.632 Abnormal pressure in the PRT El El El El 008K1 .01 Component Cooling Water 3.1 3.1 SWS El El El El El [

0l0K02 Pressurizer Pressure Contr 323.5 PZR 012K5.02 Reactor Protection 3.1 3 El El El El El El El El El El Power density 013G2.2.36 EngineeredSafetyFeaturesActuafion 3.1 4.2 El El El El El El El El El El Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Page 1 of 3 09/22/2014 5:14PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 013K4.lO Engineered Safety Features Actuation 3.3 3.7 j j j j J Safeguards equipment control reset 022A4.03 Containment Cooling 3.2 3.2 j Dampers in the CCS 022K1 .02 Containment Cooling 3.7 3.5 j J SEC/remote monitoring systems 026A3.02 Containment Spray 3.9 4.2 J j J VerWcatknthatcooling water is supplied to the containment spray heat exchanger 039K3.04 Main and Reheat Steam 2.5 2.6 MFW pumps 059A1 .07 Main Feedwater 2.5 2.6 El El El El El Feed Pump speed, including normal control speed for CS 059A4.01 Main Feedwater 3.1 3.1 El El El El El El El El El [] El MEW turbine trip indication 061 Ki .04 Auxiliary/Emergency Feedwater 3.9 4.1 El El El El El El El El El El 061 K5.05 Auxiliary/Emergency Feedwater 2.7 3.2 El El El El Feed line voiding and water hammer El El El El El El 062A4.04 AC Electrical Distribution a6 2.7 El El El El El El El El El [] El Local operation of breakers 063K2.01 DC Electrical Distribution 2.9 3.1 El El El El El El El El El El Major DC loads Page2of3 09/22/2014 5:14PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064K2.03 Emergency Diesel Generator 3.2 3.6 LI Control power 073A1 .01 Process Radiation Monitoring 3.2 3.5 Radtion levels 076G2.1 .30 Service Water 4.4 4.0 LI [1 Ability to locate and operate components, including local controls.

076G2.2.22 Service Water 4.0 4.7 LI LI LI LI LI LI LI LI LI LI Knowledge of limiting conditions for operations and safety limits.

078A3.0l Instrument Air 3.1 3.2 LI LI LI LI LI LI LI LI Air pressure LI LI 103A1.01 Containment 3.7 4.1 LI LI LI LI LI LI [I LI LI LI LI Containment pressure, temperature and humidity Page3of3 09/2212014 5:14PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IA Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

. RO SRQ 004A2.35 Chemical and Volume Control 3.3 3.8 LI LI LI LI LI LI Reactor trip 012G2.4.l Reactor Protection 64.8 LI LI LI [ [] [] [] [] [] Knowledge of EOP entry conditions and immediate action steps.

022A2.04 Containment Cooling 2.9 3.2 Loss of service water 026A2.04 Containment Spray 9 4.2 LI LI LI LI LI LI LI LI LI LI Failure of spray pump 064G2.1.32 Emergency Diesel Generator 3.8 4.0 LI LI LI LI LI LI LI LI LI LI Ability to explain and apply all system limits and precautions.

Page 1 of 1 09/2212014 5:14PM

ES-401 5 Form ES-401-2 l ES-401 PWR Examination Outline Form ES-401-2 l Plant Systems - Tier 2/Group 2 (RO / SRO) l System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 001K6.03 002 Reactor Coolant 002G2.2.25 011 Pressurizer Level Control 011K2.02 014 Rod Position Indication 014K5.01 015 Nuclear Instrumentation 015G2.4.47 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 017A1.01 027 Containment Iodine Removal 027A4.04 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 029G2.4.3 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 035A2.05 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 045K3.01 055 Condenser Air Removal 055A3.03 056 Condensate l 068 Liquid Radwaste 068K1.07 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection 086A2.04 K/A Category Point Totals: Group Point Total: RO - 10 SRO - 3 10/3 l ES-401, Page 25 of 33

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 K6.03 Control Rod Drive 3.7 4.2 J Reactor trip breakers, including controls j J 0111<2.02 Pressurizer Level Control 3.1 3.2 j j PZR heaters

] j 014K5.Ol Rod Position Indication 273.0 J J J j Reasons for differences between RPIS and step counter j

01 7A1 .01 In-core Temperature Monitor 3.73.9 Core exit temperature j Ej J EJ J El 027A4.04 Containment Iodine Removal 2.8 2.9 j Filter temperature 029G2.4.3 Containment Purge 3.73.9 El El El El El El El El El El Ability to identify post-accident instrumentation.

035A2.05 Steam Generator a23.4 El El El El El El El El El El Unbalanced flows to the 5/Gs 045K3.01 Main Turbine Generator 932 El El El El El El El El El El Remainder of the plant 055A3.03 Condenser Air Removal 5 2.7 El El El El El El El El El El Automatic dkersion of CARS exhaust 068K1 .07 Liquid Radwaste 2.7 2.9 El El El El El El El El El El Sources of liquid wastes for LRS Page 1 of 1 09/2212014 5:14 PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002G2.2.25 Reactor Coolant 3.2 4.2 El El El El El El El El El El Knowledge of the bases in Technical Specifications for

. limiting conditions for operations and safety limits.

015G2.4.47 Nuclear Instrumentation 4.2 4.2 ElElElElElElElElElEl Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

086A2.04 Fire Protection 3.3 3.9 Failure to actuate the FPS when requed, resulting in fire DDDDDDDE1E1L1 damage Page 1 of 1 09/22/2014 5:14PM

l ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

l Category K/A # Topic RO SRO-Only l IR # IR #

2.1. G2.1.23 l 1. 2.1. G2.1.7 Conduct 2.1. G2.1.14 of Operations G2.1.38 2.1.

2.1.

2.1.

l Subtotal 2.2. G2.2.6 2.2. G2.2.7 l 2. 2.2. G2.2.1 Equipment Control 2.2. G2.2.21 2.2.

2.2.

l Subtotal 2.3. G2.3.13 2.3. G2.3.14 l 3. 2.3. G2.3.4 Radiation Control 2.3. G2.3.11 2.3.

2.3.

l Subtotal 2.4. G2.4.21 l 4. 2.4. G2.4.29 Emergency 2.4. G2.4.43 Procedures /

Plan 2.4. G2.4.12 2.4. G2.4.23 2.4.

l Subtotal l Tier 3 Point Total RO - 10 SRO - 7 10 7 ES-401, Page 26 of 33

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .23 Conduct of operations 4.3 4.4 J J Ability to perform specific system and integrated plant procedures during all modes of plant operation.

G2.1 .7 Conductofoperations 4.4 4.7 j j J j Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

G2.2.6 Equipment Control 3.03.6 j Knowledge of the process for making changes to procedures G2.2.7 Equipment Control 2.9 3.6 j j j Knowledge of the process for conducting special or infrequent tests G2.3.13 Radiation Control 3.4 3.8 j j Knowledge of radiological safety procedures pertning to licensed operator duties G2.3.14 RadtionControl 3.4 3.8 j j j j j Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 El El El Knowledge of radiation exposure limits under normal and emergency conditions G2.4.21 Emergency Procedures/Plans 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions G2.4.29 Emergency Procedures/Puns 3.1 4.4 El El El El El El El El El El Knowledge of the emergency plan.

G2.4.43 Emergency Procedures/Plans 3.2 3.8 El El El El El El El El El El Knowledge of emergency communications systems and techniques.

Page 1 of 1 09/22/2014 5:14PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .14 Conduct of operations 3.1 3.1 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.

G2.1 .38 Conduct of operations 3.7 3.8 Knowledge of thestations requirements for verbal communication when im plamenting procedures G2.2.1 Equipment Control 4.5 Ability to pertorm pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.21 Equipment Control 2.9 4.1 Knowledge of pre- and post-maintenance operability requirements.

G2.3.1 1 Radiation Control 3.8 4.3 Ability to control radiation releases G2.4.12 Emergency Procedures/Plans 4.0 4.3 Knowledge of general operating crew responsibilities during emergency operations.

G2.4.23 Emergency Procedures/Plans 3.4 DDE DDE D ED Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

Page 1 of 1 09/22/2014 5:14PM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Surry________________________ Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: _SR 15-301_

Administrative Topic (see Note) Type Describe activity to be performed Code*

Complete Reactivity Summary Sheet Conduct of Operations K/A: G2.1.37 Knowledge of procedures, guidelines, or R/D limitations associated with reactivity management.

RO: 4.3/SRO: 4.7 Calculate Primary to Secondary leakage and determine ramp rate in accordance with 0-OSP-Conduct of Operations C/N RC-002 K/A: G2.1.23 Ability to perform specific system and integrated plant procedure during all modes of plant operation. RO: 4.3/SRO: 4.4 Equipment Control Calculate stay time Radiation Control K/A: G2.3.4 Knowledge of radiation exposure limits under R/M normal or emergency conditions. RO: 3.2/SRO: 3.7 Complete EPIP-2.01 for Alert, and Transmit Emergency Plan K/A: G2.4.39 Knowledge of RO responsibilities in S/D emergency plan implementation. RO: 3.9/SRO: 3.8 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ____Surry________________________ Date of Examination: _____________

Exam Level: RO SRO-I SRO-U Operating Test No.: _ SR 15-301_____

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Perform AP-3.00 to Emergency Borate the RCS During ES-0.1 N/S/A/L/E 1 (Faulted) (pre-brief)
b. Depressurize RCS with Normal Spray (Faulted) D/S/A/L/E 2
c. Respond to spurious Containment Spray Actuation. D/S/EN 3
d. Initiate RCS Feed and Bleed M/S/A/L/E 4
e. Respond to Secondary Transient M/S/A 7
f. Manually start Cont. Spray pumps per Attachment 1 M/S/EN/L 5
g. Align the Emergency Bus in accordance with AP-10.07 D/S/E 6 Attachment 4
h. Waste Gas Tank Release (Faulted) 9 N/S/A In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Manually makeup to SFP D/E/R/A 8
j. Locally establish Ch Pump X-tie to Unit 2 D/E/L/R 4P
k. Transfer Semi-vital bus power supply D/E 6
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 / Actual A)lternate path 4-6 / 6 (C)ontrol room (D)irect from bank 9 / 6 (E)mergency or abnormal in-plant 1 / 7 (EN)gineered safety feature 1 / 2 (control room system)

(L)ow-Power / Shutdown 1 / 5 (N)ew or (M)odified from bank including 1(A) 2 / 5 (P)revious 2 exams 3 / 0 (randomly selected)

(R)CA 1 / 8 (S)imulator

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry________________________ Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: _ SR 15-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

Complete Reactivity Summary Sheet Conduct of Operations K/A: G2.1.37 Knowledge of procedures, guidelines, or R/D limitations associated with reactivity management.

RO: 4.3/SRO: 4.7 Calculate Primary to Secondary leakage and determine ramp rate in accordance with 0-OSP-Conduct of Operations C/N RC-002 K/A: G2.1.23 Ability to perform specific system and integrated plant procedure during all modes of plant operation. RO: 4.3/SRO: 4.4 Review 1-OPT-CH-002 Equipment Control K/A: G2.2.37 Ability to determine operability and/or R/D availability of safety related equipment.

Calculate stay time Radiation Control K/A: G2.3.4 Knowledge of radiation exposure limits under R/M normal or emergency conditions. RO: 3.2/SRO: 3.7 Classify EAL and Approve Notification Emergency Plan R/D K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications. RO: 2.9 / SRO: 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Surry_________________________ Date of Examination: _____________

Exam Level: RO SRO-I SRO-U Operating Test No.: _ SR 15-301_____

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Perform AP-3.00 to Emergency Borate the RCS During ES-0.1 N/S/A/L/E 1 (Faulted) (pre-brief)
b. Depressurize RCS with Normal Spray (Faulted) D/S/A/L/E 2
c. Respond to spurious Containment Spray Actuation. D/S/EN 3
d. Initiate RCS Feed and Bleed M/S/A/L/E 4
e. Respond to Secondary Transient M/S/A 7
f. Manually start Cont. Spray pumps per Attachment 1 M/S/EN/L 5
g. Align the Emergency Bus in accordance with AP-10.07 D/S/E 6 Attachment 4 h.

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

i. Manually makeup to SFP D/E/R/A 8
j. Locally establish Ch Pump X-tie to Unit 2 D/E/L/R 4P
k. Transfer Semi-vital bus power supply D/E 6
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 SRO-I / Actual A)lternate path 4-6 / 5 (C)ontrol room (D)irect from bank 8 / 6 (E)mergency or abnormal in-plant 1 / 7 (EN)gineered safety feature 1 / 2 (control room system)

(L)ow-Power / Shutdown 1 / 5 (N)ew or (M)odified from bank including 1(A) 2 / 4 (P)revious 2 exams 3 / 0 (randomly selected)

(R)CA 1 / 7 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Surry_________________________ Date of Examination: _____________

Exam Level: RO SRO-I SRO-U Operating Test No.: _ SR 15-301_____

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Perform AP-3.00 to Emergency Borate the RCS During ES-0.1 N/S/A/L/E 1 (Faulted) (pre-brief)
b. Depressurize RCS with Normal Spray (Faulted) D/S/A/L/E 2
c. Respond to spurious Containment Spray Actuation. D/S/EN 3 d.

e.

f.

g.

h.

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

i. Manually makeup to SFP D/E/R/A 8
j. Locally establish Ch Pump X-tie to Unit 2 D/E/L/R 4P k.
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 SRO-U / Actual A)lternate path 2-3 / 3 (C)ontrol room (D)irect from bank 4 / 4 (E)mergency or abnormal in-plant 1 / 4 (EN)gineered safety feature 1 / 1 (control room system)

(L)ow-Power / Shutdown 1 / 3 (N)ew or (M)odified from bank including 1(A) 1 / 1 (P)revious 2 exams 2 / 0 (randomly selected)

(R)CA 1 / 3 (S)imulator

ES-401,Rev.9 PWR Examination Outline Form ES-401-2 Facility: ie Date of Exam: $P TEmLEA?

RO K/A Category Points SRO-OnIy Points Tier Group 1(11(1K K K K{[A A A G A2 G* Total 112j3 4 5 6[1 2 3 4 Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal Plant 2

T*

N/A 2 1 N/A 9 2 2 4 Evolutions Tier Totals 5 5 4 5 27 5 5 10 i 3 2 3 2 2 3 22 3 3 28 3 2 5 L

2.

Plant 2 1 1 1 0 1 1 1 1 1 1 1 10 Lf[i 2 3 Systems TierTotals 4 3 3 3 f- 3 ---- .- 38 4 8

3. Generic Knowledge and Abilities I 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 1 2 I Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., exceptfor one category in Tier 3 ofthe SRO-only outline, the i1er Totals@

in each K/A 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 11 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. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted andjustified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section 0.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 KIAs 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 I and 2 from the shaded systems and K/A categories.
7. *The generic (G) KIAs in Tiers I and 2 shall be selected from Section 2 ofthe KIA Catalog, butthe topics must be relevant to the applicable evolution or system. Refer to section D.1 .b of ES-401 for the applicable KAs.
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 # I does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to I 0 CFR 55.43..

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor 007EA2.06 Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space 008AA1.04 Accident / 3 000009 Small Break LOCA / 3 009EK3.11 000011 Large Break LOCA / 3 011EK2.02 000015/17 RCP Malfunctions / 4 015AK1.04 000022 Loss of Rx Coolant Makeup / 2 022AK1.04 000025 Loss of RHR System / 4 025AA1.04 000026 Loss of Component Cooling 026AG2.2.44 Water / 8 000027 Pressurizer Pressure Control 027AA2.02 System Malfunction / 3 000029 ATWS / 1 029EA2.01 000038 Steam Gen. Tube Rupture / 3 038EK1.02 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat 040AG2.1.30 Transfer / 4 000054 (CE/E06) Loss of Main 054AK3.05 054AG2.4.18 Feedwater / 4 000055 Station Blackout / 6 055EK3.02 000056 Loss of Off-site Power / 6 056AA2.75 000057 Loss of Vital AC Inst. Bus / 6 057AG2.4.50 000058 Loss of DC Power / 6 058AA1.02 000062 Loss of Nuclear Svc Water / 4 062AA2.04 000065 Loss of Instrument Air / 8 065AG2.4.3 W/E04 LOCA Outside Containment / 3 WE04EK2.2 W/E11 Loss of Emergency Coolant WE11EG2.1.2 Recirc. / 4 BW/E04; W/E05 Inadequate Heat WE05EA2.1 Transfer - Loss of Secondary Heat Sink / 4 l 000077 Generator Voltage and Electric 077AK1.02 l Grid Disturbances / 6 K/A Category Totals: Group Point Total: RO - 18 SRO - 6 18/6 ES-401, Page 22 of 33

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO8AA1 .04 Pressurizer Vapor Space Accident I 3 2.8 2.5 j fl J j j Feedwater pumps 009EK3.1 1 Small Break LOCA I 3 4.4 4.5 j J j Dangers associated with inadequate core cooling j

O11EK2.02 LargeBreakLOCA/3 2.6 2.7 j Pumps AR2.lO RCP Malfunctions I 4 2.8 2.8 J RCP indicators and controls 022AK1 .04 Loss of Rx Coolant Makeup I 2 2.9 3 Reason for changing from manual to automatic control of j j J charging flow valve controller 025AA1 .04 Loss of RHR System /4 2.8 2.6 j j Closed coohng water pumps 027AA2.02 Pressurizer Pressure Control System 8 9 El El El El El El El i El El El Normal values for RCS pressure Malfunction / 3 029EA0l ATWS /1 4.447 Reactor nuclear instrumentation El El El El El El El El El El 038EK1 .02 Steam Gen. Tube Rupture /3 3.2 3.5 El El El El El El El El El El Leak rate vs. pressure drop 040AG2.l .30 Steam Line Rupture Excessive Heat 4.4 4.0 Transfer / 4 El El El El El El El El El El Ability to locate and operate components, incluchngloc controls.

054AK3.05 Loss of Main Feedwater /4 4.64J El El El El El El El El El El HPI/PORV cycling upon total feedwater loss Page 1 of 2 09/22/2014 5:14 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 055EK3.02 Station Blackout I 6 4.3 4.6 J J j j Actions contained in EOP for loss of offsite and onsite power 057AG2.4.50 Loss of Vital AC Inst. Bus I 6 4.2 4.0 J ] Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

058AA1.02 Loss of DCPower I 6 3.1 3.1 j j J Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector 062AA2.04 Loss of Nuclear Svc Water / 4 2.5 2.9 The normal values and upper limits for the temperatures of the components cooled by SWS 077AK1 .02 Generator Voltage and Electric Grid 3.3 3.4 LI LI LI El El Over-excitation Disturbances / 6 WE04EK2.2 LOCA Outside Containment /3 3.840 El El El El El El El El El El Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

well EG2.l .2 Loss of Emergency Coolant Recirc. /4 4.64.6 El El El El El El El El El El Ability to execute procedure steps.

Page2of2 09/22/2014 5:14PM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 007EA2.06 Reactor Trip Stabilization

- - Recovery 4.3 4.5 J j j J Occurrence of a reactor trip

/1 026AG2.2.44 Loss of Component Cooling Water / 8 4.2 4.4 j Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 054AG2.4.18 Loss of Main Feedwater/4 3.3 4.0 [] Knowledge of the specific bases for EOPs.

056AA2.75 Loss of Off-site Power /6 3 3.2 J j j J CVCS makeup 065AG2.4.3 Loss of Instrument Air /8 3.7 3.9 El El El El El El El El El El Ability to identify post-accident instrumentation.

WEO5EA2.1 Inadequate Heat Transfer Loss of

- 3.4 4.4 ElElElElElElElElElEl Facility conditions and selection of appropriate Secondary Heat Sink /4 procedures during abnormal and emergency operations.

Page 1 of 1 09/22/2014 5:14PM

ES-401 3 Form ES-401-2 l ES-401 PWR Examination Outline Form ES-401-2 l Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO) l E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 001AA1.02 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 024AA2.01 000028 Pressurizer Level Malfunction / 2 028AG2.4.47 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 036AG2.2.37 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 060AK1.02 000061 ARM System Alarms / 7 061AA2.03 000067 Plant Fire On-site / 8 067AK3.02 l 000068 (BW/A06) Control Room Evac. / 8 068AA2.10 000069 (W/E14) Loss of CTMT Integrity / 5 069AG2.4.21 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 076AK2.01 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 WE15EG2.4.8 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 WE10EA1.3 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 WE08EK3.3 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: Group Point Total: RO - 9 SRO - 4 9/4 l ES-401, Page 23 of 33

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 AA1 .02 Continuous Rod Withdrawal I 1 3.6 3.4 J j Rod in-out-hold switch 028AG2.4.47 Pressurizer Level Maunction I 2 4.2 4.2 j jAbUity to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Accidental Gaseous Radwaste Rel. I 9 2.5 3.1 J j J j Biological effects on humans of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels 067AK3.02 Plant Fire On-site I 8 2.53.3 j j j j Steps called out in the site fire proteconpn,FPS manual and fire zone manual 068AA2.lO Control Room Evac. I 8 4.2 4.4 j j J Source range count rate 076AK2.O1 High Reactor Coant Activity /9 2.6 3 Process radiation monitors WEO8EK3.3 RCS Overcooling PTS /4

- 3.7 3.8 LI LI LI LI LI LI LI LI LI Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

WE1 OEA1 .3 Natural Circ. With Seam Void/ 4 3.4 3.7 LI LI LI LI LI LI ] LI LI LI LI bsired operating results during abnormal and emergency situations.

wel5EG2.4.8 Containment Floocng /5 3.84.5 LI LI LI LI LI LI LI LI LI LI Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Page 1 of 1 09/22/2014 5:14 PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 024AA2.O1 Emergency Boration / 1 3.8 4.1 Whether boron flow and/or MOVs are malfunctioning from plant conditions 036AG2.2.37 Fuel Handling Accident / 8 3.6 4.6 Ability to deterrne operability and/or availability of safety related equipment AA2.o3 ARM System Alarms /7 3 3.3 Setpoints for alert and high alarms 069AG2.4.21 Loss of CTMT Integrity /5 4O4.6 Knowledge of the parameters and logic used to assess the status of safety functions Page 1 of 1 09/22/2014 5:14PM

l ES-401 4 Form ES-401-2 l ES-401 PWR Examination Outline Form ES-401-2 l Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 003K4.04 004 Chemical and Volume 004K4.03 004A2.35 Control 005 Residual Heat Removal 005K2.03 005K6.03 006 Emergency Core Cooling 006A2.05 006K3.01 007 Pressurizer Relief/Quench 007A2.02 Tank 008 Component Cooling Water 008K1.01 010 Pressurizer Pressure Control 010K6.02 012 Reactor Protection 012K5.02 012G2.4.1 013 Engineered Safety Features 013G2.2.36 013K4.10 Actuation 022 Containment Cooling 022A4.03 022K1.02 022A2.04 025 Ice Condenser 026 Containment Spray 026A3.02 026A2.04 039 Main and Reheat Steam 039K3.04 059 Main Feedwater 059A1.07 059A4.01 061 Auxiliary/Emergency Feedwater 061K1.04 061K5.05 062 AC Electrical Distribution 062A4.04 063 DC Electrical Distribution 063K2.01 064 Emergency Diesel Generator 064K2.03 064G2.1.32 073 Process Radiation 073A1.01 Monitoring 076 Service Water 076G2.1.30 076G2.2.22 078 Instrument Air 078A3.01 103 Containment 103A1.01 l K/A Category Point Totals: Group Point Total: RO - 28 SRO - 5 28/5 ES-401, Page 24 of 33

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K4.04 Reactor Coolant Pump 2.8 3.1 Adequate cooling of RCP motor and seals 004K4.03 Chemical and VcumeControl 2.8 2.9 J J j J j Protection of ion exchangers (high letdown temperature will isolate ion exchangers) 005K2.03 Residual Heat Removal 2.7 2.8 j J RCS pressure boundary motor-operated valves Residual Heat Removal 2.5 2.6 j E LI El RHR heat exchanger 006A2.05 Emergency Core Cooling 3.4 3.5 Improper amperage to the pump motor 006K3.0l Emergency Core Cooling 4i4.2 RCS 007A2.02 Pressurizer Relief/Quench Tank 2.632 Abnormal pressure in the PRT El El El El 008K1 .01 Component Cooling Water 3.1 3.1 SWS El El El El El [

0l0K02 Pressurizer Pressure Contr 323.5 PZR 012K5.02 Reactor Protection 3.1 3 El El El El El El El El El El Power density 013G2.2.36 EngineeredSafetyFeaturesActuafion 3.1 4.2 El El El El El El El El El El Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Page 1 of 3 09/22/2014 5:14PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 013K4.lO Engineered Safety Features Actuation 3.3 3.7 j j j j J Safeguards equipment control reset 022A4.03 Containment Cooling 3.2 3.2 j Dampers in the CCS 022K1 .02 Containment Cooling 3.7 3.5 j J SEC/remote monitoring systems 026A3.02 Containment Spray 3.9 4.2 J j J VerWcatknthatcooling water is supplied to the containment spray heat exchanger 039K3.04 Main and Reheat Steam 2.5 2.6 MFW pumps 059A1 .07 Main Feedwater 2.5 2.6 El El El El El Feed Pump speed, including normal control speed for CS 059A4.01 Main Feedwater 3.1 3.1 El El El El El El El El El [] El MEW turbine trip indication 061 Ki .04 Auxiliary/Emergency Feedwater 3.9 4.1 El El El El El El El El El El 061 K5.05 Auxiliary/Emergency Feedwater 2.7 3.2 El El El El Feed line voiding and water hammer El El El El El El 062A4.04 AC Electrical Distribution a6 2.7 El El El El El El El El El [] El Local operation of breakers 063K2.01 DC Electrical Distribution 2.9 3.1 El El El El El El El El El El Major DC loads Page2of3 09/22/2014 5:14PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064K2.03 Emergency Diesel Generator 3.2 3.6 LI Control power 073A1 .01 Process Radiation Monitoring 3.2 3.5 Radtion levels 076G2.1 .30 Service Water 4.4 4.0 LI [1 Ability to locate and operate components, including local controls.

076G2.2.22 Service Water 4.0 4.7 LI LI LI LI LI LI LI LI LI LI Knowledge of limiting conditions for operations and safety limits.

078A3.0l Instrument Air 3.1 3.2 LI LI LI LI LI LI LI LI Air pressure LI LI 103A1.01 Containment 3.7 4.1 LI LI LI LI LI LI [I LI LI LI LI Containment pressure, temperature and humidity Page3of3 09/2212014 5:14PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IA Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

. RO SRQ 004A2.35 Chemical and Volume Control 3.3 3.8 LI LI LI LI LI LI Reactor trip 012G2.4.l Reactor Protection 64.8 LI LI LI [ [] [] [] [] [] Knowledge of EOP entry conditions and immediate action steps.

022A2.04 Containment Cooling 2.9 3.2 Loss of service water 026A2.04 Containment Spray 9 4.2 LI LI LI LI LI LI LI LI LI LI Failure of spray pump 064G2.1.32 Emergency Diesel Generator 3.8 4.0 LI LI LI LI LI LI LI LI LI LI Ability to explain and apply all system limits and precautions.

Page 1 of 1 09/2212014 5:14PM

ES-401 5 Form ES-401-2 l ES-401 PWR Examination Outline Form ES-401-2 l Plant Systems - Tier 2/Group 2 (RO / SRO) l System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 001K6.03 002 Reactor Coolant 002G2.2.25 011 Pressurizer Level Control 011K2.02 014 Rod Position Indication 014K5.01 015 Nuclear Instrumentation 015G2.4.47 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 017A1.01 027 Containment Iodine Removal 027A4.04 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 029G2.4.3 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 035A2.05 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 045K3.01 055 Condenser Air Removal 055A3.03 056 Condensate l 068 Liquid Radwaste 068K1.07 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection 086A2.04 K/A Category Point Totals: Group Point Total: RO - 10 SRO - 3 10/3 l ES-401, Page 25 of 33

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 K6.03 Control Rod Drive 3.7 4.2 J Reactor trip breakers, including controls j J 0111<2.02 Pressurizer Level Control 3.1 3.2 j j PZR heaters

] j 014K5.Ol Rod Position Indication 273.0 J J J j Reasons for differences between RPIS and step counter j

01 7A1 .01 In-core Temperature Monitor 3.73.9 Core exit temperature j Ej J EJ J El 027A4.04 Containment Iodine Removal 2.8 2.9 j Filter temperature 029G2.4.3 Containment Purge 3.73.9 El El El El El El El El El El Ability to identify post-accident instrumentation.

035A2.05 Steam Generator a23.4 El El El El El El El El El El Unbalanced flows to the 5/Gs 045K3.01 Main Turbine Generator 932 El El El El El El El El El El Remainder of the plant 055A3.03 Condenser Air Removal 5 2.7 El El El El El El El El El El Automatic dkersion of CARS exhaust 068K1 .07 Liquid Radwaste 2.7 2.9 El El El El El El El El El El Sources of liquid wastes for LRS Page 1 of 1 09/2212014 5:14 PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002G2.2.25 Reactor Coolant 3.2 4.2 El El El El El El El El El El Knowledge of the bases in Technical Specifications for

. limiting conditions for operations and safety limits.

015G2.4.47 Nuclear Instrumentation 4.2 4.2 ElElElElElElElElElEl Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

086A2.04 Fire Protection 3.3 3.9 Failure to actuate the FPS when requed, resulting in fire DDDDDDDE1E1L1 damage Page 1 of 1 09/22/2014 5:14PM

l ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

l Category K/A # Topic RO SRO-Only l IR # IR #

2.1. G2.1.23 l 1. 2.1. G2.1.7 Conduct 2.1. G2.1.14 of Operations G2.1.38 2.1.

2.1.

2.1.

l Subtotal 2.2. G2.2.6 2.2. G2.2.7 l 2. 2.2. G2.2.1 Equipment Control 2.2. G2.2.21 2.2.

2.2.

l Subtotal 2.3. G2.3.13 2.3. G2.3.14 l 3. 2.3. G2.3.4 Radiation Control 2.3. G2.3.11 2.3.

2.3.

l Subtotal 2.4. G2.4.21 l 4. 2.4. G2.4.29 Emergency 2.4. G2.4.43 Procedures /

Plan 2.4. G2.4.12 2.4. G2.4.23 2.4.

l Subtotal l Tier 3 Point Total RO - 10 SRO - 7 10 7 ES-401, Page 26 of 33

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .23 Conduct of operations 4.3 4.4 J J Ability to perform specific system and integrated plant procedures during all modes of plant operation.

G2.1 .7 Conductofoperations 4.4 4.7 j j J j Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

G2.2.6 Equipment Control 3.03.6 j Knowledge of the process for making changes to procedures G2.2.7 Equipment Control 2.9 3.6 j j j Knowledge of the process for conducting special or infrequent tests G2.3.13 Radiation Control 3.4 3.8 j j Knowledge of radiological safety procedures pertning to licensed operator duties G2.3.14 RadtionControl 3.4 3.8 j j j j j Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 El El El Knowledge of radiation exposure limits under normal and emergency conditions G2.4.21 Emergency Procedures/Plans 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions G2.4.29 Emergency Procedures/Puns 3.1 4.4 El El El El El El El El El El Knowledge of the emergency plan.

G2.4.43 Emergency Procedures/Plans 3.2 3.8 El El El El El El El El El El Knowledge of emergency communications systems and techniques.

Page 1 of 1 09/22/2014 5:14PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .14 Conduct of operations 3.1 3.1 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.

G2.1 .38 Conduct of operations 3.7 3.8 Knowledge of thestations requirements for verbal communication when im plamenting procedures G2.2.1 Equipment Control 4.5 Ability to pertorm pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.21 Equipment Control 2.9 4.1 Knowledge of pre- and post-maintenance operability requirements.

G2.3.1 1 Radiation Control 3.8 4.3 Ability to control radiation releases G2.4.12 Emergency Procedures/Plans 4.0 4.3 Knowledge of general operating crew responsibilities during emergency operations.

G2.4.23 Emergency Procedures/Plans 3.4 DDE DDE D ED Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

Page 1 of 1 09/22/2014 5:14PM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Surry________________________ Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: _SR 15-301_

Administrative Topic (see Note) Type Describe activity to be performed Code*

Complete Reactivity Summary Sheet Conduct of Operations K/A: G2.1.37 Knowledge of procedures, guidelines, or R/D limitations associated with reactivity management.

RO: 4.3/SRO: 4.7 Calculate Primary to Secondary leakage and determine ramp rate in accordance with 0-OSP-Conduct of Operations C/N RC-002 K/A: G2.1.23 Ability to perform specific system and integrated plant procedure during all modes of plant operation. RO: 4.3/SRO: 4.4 Equipment Control Calculate stay time Radiation Control K/A: G2.3.4 Knowledge of radiation exposure limits under R/M normal or emergency conditions. RO: 3.2/SRO: 3.7 Complete EPIP-2.01 for Alert, and Transmit Emergency Plan K/A: G2.4.39 Knowledge of RO responsibilities in S/D emergency plan implementation. RO: 3.9/SRO: 3.8 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ____Surry________________________ Date of Examination: _____________

Exam Level: RO SRO-I SRO-U Operating Test No.: _ SR 15-301_____

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Perform AP-3.00 to Emergency Borate the RCS During ES-0.1 N/S/A/L/E 1 (Faulted) (pre-brief)
b. Depressurize RCS with Normal Spray (Faulted) D/S/A/L/E 2
c. Respond to spurious Containment Spray Actuation. D/S/EN 3
d. Initiate RCS Feed and Bleed M/S/A/L/E 4
e. Respond to Secondary Transient M/S/A 7
f. Manually start Cont. Spray pumps per Attachment 1 M/S/EN/L 5
g. Align the Emergency Bus in accordance with AP-10.07 D/S/E 6 Attachment 4
h. Waste Gas Tank Release (Faulted) 9 N/S/A In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Manually makeup to SFP D/E/R/A 8
j. Locally establish Ch Pump X-tie to Unit 2 D/E/L/R 4P
k. Transfer Semi-vital bus power supply D/E 6
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 / Actual A)lternate path 4-6 / 6 (C)ontrol room (D)irect from bank 9 / 6 (E)mergency or abnormal in-plant 1 / 7 (EN)gineered safety feature 1 / 2 (control room system)

(L)ow-Power / Shutdown 1 / 5 (N)ew or (M)odified from bank including 1(A) 2 / 5 (P)revious 2 exams 3 / 0 (randomly selected)

(R)CA 1 / 8 (S)imulator

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry________________________ Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: _ SR 15-301 Administrative Topic (see Note) Type Describe activity to be performed Code*

Complete Reactivity Summary Sheet Conduct of Operations K/A: G2.1.37 Knowledge of procedures, guidelines, or R/D limitations associated with reactivity management.

RO: 4.3/SRO: 4.7 Calculate Primary to Secondary leakage and determine ramp rate in accordance with 0-OSP-Conduct of Operations C/N RC-002 K/A: G2.1.23 Ability to perform specific system and integrated plant procedure during all modes of plant operation. RO: 4.3/SRO: 4.4 Review 1-OPT-CH-002 Equipment Control K/A: G2.2.37 Ability to determine operability and/or R/D availability of safety related equipment.

Calculate stay time Radiation Control K/A: G2.3.4 Knowledge of radiation exposure limits under R/M normal or emergency conditions. RO: 3.2/SRO: 3.7 Classify EAL and Approve Notification Emergency Plan R/D K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications. RO: 2.9 / SRO: 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Surry_________________________ Date of Examination: _____________

Exam Level: RO SRO-I SRO-U Operating Test No.: _ SR 15-301_____

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Perform AP-3.00 to Emergency Borate the RCS During ES-0.1 N/S/A/L/E 1 (Faulted) (pre-brief)
b. Depressurize RCS with Normal Spray (Faulted) D/S/A/L/E 2
c. Respond to spurious Containment Spray Actuation. D/S/EN 3
d. Initiate RCS Feed and Bleed M/S/A/L/E 4
e. Respond to Secondary Transient M/S/A 7
f. Manually start Cont. Spray pumps per Attachment 1 M/S/EN/L 5
g. Align the Emergency Bus in accordance with AP-10.07 D/S/E 6 Attachment 4 h.

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

i. Manually makeup to SFP D/E/R/A 8
j. Locally establish Ch Pump X-tie to Unit 2 D/E/L/R 4P
k. Transfer Semi-vital bus power supply D/E 6
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 SRO-I / Actual A)lternate path 4-6 / 5 (C)ontrol room (D)irect from bank 8 / 6 (E)mergency or abnormal in-plant 1 / 7 (EN)gineered safety feature 1 / 2 (control room system)

(L)ow-Power / Shutdown 1 / 5 (N)ew or (M)odified from bank including 1(A) 2 / 4 (P)revious 2 exams 3 / 0 (randomly selected)

(R)CA 1 / 7 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ___Surry_________________________ Date of Examination: _____________

Exam Level: RO SRO-I SRO-U Operating Test No.: _ SR 15-301_____

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Perform AP-3.00 to Emergency Borate the RCS During ES-0.1 N/S/A/L/E 1 (Faulted) (pre-brief)
b. Depressurize RCS with Normal Spray (Faulted) D/S/A/L/E 2
c. Respond to spurious Containment Spray Actuation. D/S/EN 3 d.

e.

f.

g.

h.

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

i. Manually makeup to SFP D/E/R/A 8
j. Locally establish Ch Pump X-tie to Unit 2 D/E/L/R 4P k.
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 SRO-U / Actual A)lternate path 2-3 / 3 (C)ontrol room (D)irect from bank 4 / 4 (E)mergency or abnormal in-plant 1 / 4 (EN)gineered safety feature 1 / 1 (control room system)

(L)ow-Power / Shutdown 1 / 3 (N)ew or (M)odified from bank including 1(A) 1 / 1 (P)revious 2 exams 2 / 0 (randomly selected)

(R)CA 1 / 3 (S)imulator

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