ML18102A269

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Draft Written Examination and Operating Test Outlines
ML18102A269
Person / Time
Site: Beaver Valley
Issue date: 08/28/2017
From: D'Antonio J
Operations Branch I
To:
FirstEnergy Nuclear Operating Co
Shared Package
ML17068A096 List:
References
U01938
Download: ML18102A269 (30)
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Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: BV2 Date of Examination:

Examination Level: RO D SRO [Zl Operating Test Number:

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

Conduct of Operations D 3AD-24: License Maintenance Conduct of Operations M Reactivity Calculation / Shutdown Margin Equipment Control N Review Tagout of AFW Pump 2AD-023: Review/Approve Liquid Waste Radiation Control D Discharge Emergency Plan M 2AD-015: Classification and PAR 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 and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:s 3 for ROs;::; 4 for SROs and RO retakes)

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

(P)revious 2 exams (:s 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: BV2 Date of Examination:

Examination Level: RO ~ SRO D Operating Test Number:

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

Conduct of Operations D 3AD-24: License Maintenance Conduct of Operations M Reactivity Calculation/ Shutdown Margin Equipment Control N Prepare Tagout of AFW Pump Radiation Control Emergency Plan N Emergency Plan Notifications 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 and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank(::; 3 for ROs;::; 4 for SROs and 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: Beaver Valley Unit 2 Date of Examination: 11/06/2017 Exam Level: RO SRO-I X SRO-U Operating Test No.:

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

a. 2CR-542: 001: CRDS, Nuclear Power Generation/ ATWS A,S,D 1
b. 011: Pressurizer Level Control System, Transfer from manual to A, S, N, 2 automatic, auto fails, transfer back to manual
c. 006 ECCS; 2CR-044; FILL SIS Accumulator A S,D 3 d.
e. 006 A.C.; 2CR-023, Hot bus transfer (2B 4kV bus to 2A SSST S,D 6
f. eves LT-115 fail high, manual makeup S, A,N* 7
g. 008 CCWS; 2CR-157, Pri. Comp. Cooling water pump Test S, D, L 8
h. CS Manual Actuation; 2CR-657 modified A,S,M 5 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. 061 Aux Feed sys; 2PL-172: Align Service Water to MDAFW Pump L, D, E, R*? 4S Suction
j. 2PL-086: Place Instrument Air Bypass Filters in service D 8
k. ELAP DC Load Shed - one building N,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, and in-plant systems and functions may overlap those tested in the control room.

I

  • Type Codes I Criteria for R /SR0-1/SRO-U I

(A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank :s; 9/'5c 8/5c 4 (E)mergency or abnormal in-plant  ;?:1/;?:1/?1 (EN)gineered safety feature  ;?: 1/? 1/? 1 (control room system)

(L )ow-Power/Shutdown  ;?:1/;?:1/?1 (N)ew or (M)odified from bank including 1(A)  ;?: 2/;?: 21? 1 (P)revious 2 exams 5c 3/:s; 3/5c 2 (randomly selected)

(R)CA  ;?:1/;?:1/?1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Beaver Valley Unit 2 Date of Examination: 11/06/2017 Exam Level: RO X SRO-I D SRO-U D Operating Test No.:

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

a. 2CR-542: 001: CRDS, Nuclear Power Generation/ ATWS A,S,D 1
b. 011: Pressurizer Level Control System, Transfer from manual to A,S, N, 2 automatic, auto fails, transfer back to manual
c. 006 ECCS; 2CR-044; FILL SIS Accumulator A S,D 3
d. 005 RHRS; 2CR-136, Swap RHS trains S, D, L* 4P
e. 006 A.C.; 2CR-023, Hot bus transfer (2B 4kV bus to 2A SSST S,D 6
f. eves LT-115 fail high, manual makeup S, A,N* 7
g. 008 CCWS; 2CR-157, Pri. Comp. Cooling water pump Test S, D, L 8
h. CS Manual Actuation; 2CR-657 modified A,S,M 5 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
i. 061 Aux Feed sys; 2PL-172: Align Service Water to MDAFW Pump L, D, E, R*? 4S Suction
j. 2PL-086: Place Instrument Air Bypass Filters in service D 8
k. ELAP DC Load Shed - one building N,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, and in-plant systems and functions may overlap those tested in the control room.
  • Type Codes I Criteria for R /SR0-1/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 21/21/21 (EN)gineered safety feature 2 1/2 1/2 1 (control room system)

(L )ow-Power/Shutdown 21/21/21 (N)ew or (M)odified from bank including 1(A) 2 2/22/21 (P)revious 2 exams  ::; 3/::; 3/::; 2 (randomly selected)

(R)CA 21/21/21 (S)imulator

ES-401 PWR Examination Outline Form ES-401-2 F;:ir.ilitv: Beaver Vallev Unit 2 Date of Exam: November 6, 2017 SRO-Only Points I

RO KIA Category Points Tier Group K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G* Total A2 G* Total

1. *1 2 3 4 2 4 3 18 6 Emergency and Abnormal Plant 2 1 1 2 N/A 2 1 N/A 2 9 4 Evolutions Tier Totals 3 4 6 4 5 5 27 I I I 10 I 1 3 3 3 3 2 2 3 2 2 2 3 28 5 2.

Plant 2 1 1 1 1 1 0 1 1 1 1 1 10 3 Systems Tier Totals 4 4 4 4 3 2 4 3 3 3 4 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 2 3 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a KlA from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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 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 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 K/A categories.
7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1.b of ES-401 for the applicable K/As.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' 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 a category 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 K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

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 K1 K2 K3 A1 A2 G* KIA Topic(s) JR #

000007 (EPE 7; BW E02&E10; CE E02) X EA2.02 Ability to detennine or interpret the following as 4.3/4 1 Reactor Trip, Stabilization, Recovery/ 1 applied to Rx trip: Proper actions to be taken if the .6 automatic safety functions have not occuITed 000008 (APE 8) Pressurizer Vapor Space X AK3.04: Knowledge of the reasons for RCP tiipping 4.2/4 2 Accident/ 3 requirements as they apply to the Pressmizer Vapor .6 Space Accident 000009 (EPE 9) Small Break LOCA / 3 X G2.4.6: Knowledge of EOP mitigation strategies. 3.7/4 3

.7 000011 (EPE 11) Large Break LOCA / 3 X EAi .06: Ability to operate and monitor the D/Gs as they 4.2/4 4 apply to a Large Break LOCA .2 000015 (APE 15) Reactor Coolant Pump X AK2.07: Knowledge of the inteITelations between the 2.9/2 5 Malfunctions / 4 Reactor Coolant Pump Malfunctions (Loss of RC Flow) .9 and the RCP seals 000022 (APE 22) Loss of Reactor Coolant Makeup/ 2 000025 (APE 25) Loss of Residual Heat X AA2.05: Ability to detennine and interpret the 3.1/3 6 Removal System / 4 limitations on LPI flow and temperature rates of change .5 as they apply to the Loss of Residual Heat Removal System 000026 (APE 26) Loss of Component X G2.2.38: K.J1owledge of conditions and limitations in the 3.6/4 7 Coolino Water/ 8 facility license .5 000027 (APE 27) Pressurizer Pressure Control Svstem Malfunction / 3 000029 (EPE 29) Anticipated Transient X G2.4.49: Ability to perfonn without reference to 4.6/4 8 Without Scram / 1 procedures those actions that require immediate .4 operation of system components and controls.

000038 (EPE 38) Steam Generator Tube X EA2.04: Ability to detennine or interpret radiation levels 3.9/4 9 Ruoture / 3 (MREM/hr) as they apply to a SGTR .2 000040 (APE 40; BW E05; CE E05; W E12) X AK2.02: Knowledge of the inteITelations between the 2.6/2 10 Steam Line Rupture-Excessive Heat Steam Line Rupture and sensors and detectors .6 Transfer/ 4 000054 (APE 54; CE E06) Loss of Main Feedwater /4 000055 (EPE 55) Station Blackout/ 6 X EK3 .0 I: Knowledge of the reasons for the length of time 2.7/3 11 for which battery capacity is designed as it applies to the .4 Station Blackout 000056 (APE 56) Loss of Offsite Power/ 6 X AA2.75: Ability to detennine and interpret CVCS 3.0/3 12 makeup as it applies to the Loss of Offsite Power .2 000057 (APE 57) Loss of Vital AC Instrument Bus/ 6 000058 (APE 58) Loss of DC Power/ 6 X AKI .01: Knowledge of the operational implications of 2.8/3 13 the battery charger equipment and instrumentation as .1 they apply to Loss of DC Power 000062 (APE 62) Loss of Nuclear Service X AK3 .03: K.J1owledge of the reasons for the guidance 4.0/4 14 Water/ 4 actions contained in EOP forloss of nuclear service .2 water as they apply to the Loss of Nuclear Service Water 000065 (APE 65) Loss of Instrument Air/ 8 X AK3 .03: Knowledge of the reasons for the knowing 2.9/3 15 effects on plant operation of isolating certain equipment .4 from instrument air as they apply to the Loss of Instrument Air

000077 (APE 77) Generator Voltage and X AK 1.01: Knowledge of the operational implications of 3.3/3 16 Electric Grid Disturbances / 6 the definition oftenns: volts, watts, amps, VARs, power .5 factor as they apply to Generator Voltage and Elecllic G1id Disturbances (W E04) LOCA Outside Containment/ 3 X EA 1.1: Ability to operate and / or monitor components, 4.0/4 17 and functions of control and safety systems, including .0 instlumentation, signals, interlocks, failure modes, and automatic and manual features as they apply to the (LOCA Outside Containment)

(W E11) Loss of Emergency Coolant X EK2.2: Knowledge of the intenelations between the 3.9/4 18 Recirculation / 4 (Loss of Emergency Coolant Recirculation) and the .3 facility's heat removal systems, including p1ima1y coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facilitv (BW E04; W E05) Inadequate Heat Transfer-Loss of Secondary Heat Sink/ 4 KIA Cater.iory Totals: 2 3 4 2 4 3 Group Point Total: 18

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions-Tier 1/Group 2 (RO/SRO)

E/APE # / Name/ Safety Function K1 K2 K3 A1 A2 G* KIA Topic(s) IR #

000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 X AA 1.16: Ability to operate and/ or 3.3/3 19 monitor the T-ave meters as they .2 apply to Emergency Boration 000028 (APE 28) Pressurizer (PZR) Level Control X G2.4.46: Ability to ve1ify that the 4.2/4 20 Malfunction / 2 alanns are consistent with the plant .2 conditions.

000032 (APE 32) Loss of Source Range Nuclear X AK2.0l: Knowledge of the 2.7/3 21 Instrumentation / 7 intenelations between the Loss of .I Source Range Nuclear Instrumentation and the power supplies, including proper switch positions 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents/ 8 000037 (APE 37) Steam Generator Tube Leak/ 3 X AK3.06: Knowledge of the reasons 3.6/4 22 for the nonnal operating precautions .I to preclude or minimize SGTR as they apply to the Steam Generator Tube Leak 000051 (APE 51) Loss of Condenser Vacuum/ 4 X G2.4. l I: Knowledge of abnonnal 4.0/4 23 condition procedures. .2 000059 (APE 59) Accidental Liquid Radwaste Release/ 9 000060 (APE 60) Accidental Gaseous Radwaste Release/ 9 000061 (APE 61) Area Radiation Monitoring System Alarms X AK3 .02: Knowledge of the reasons 3.4/3 24

/7 for the guidance contained in almm .6 response for ARM system as they apply to the Area Radiation Monitming (ARM) System Alanns 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation/ 8 000069 (APE 69; W E14) Loss of Containment Integrity/ 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling/ X EA2.03: Ability to detennine or 3.8/4 25 4 interpret the availability of turbine .I bypass valves for cooldown as they apply to Inadequate Core Cooling 000076 (APE 76) High Reactor Coolant Activity/ 9 X AA 1.04: Ability to operate and/or 3.2/3 26 monitor the failed fuel-monitoring .4 equipment as they apply to the High Reactor Coolant Activity 000078 (APE 78*) RCS Leak/ 3 (W E01 & E02) Rediagnosis & SI Termination/ 3 (W E 13) Steam Generator Overpressure/ 4 (W E15) Containment Flooding/ 5 (W E16) High Containment Radiation /9 X EKl .3: Knowledge of the operational 3.0/3 27 implications of the annunciators and .3 conditions indicating signals, and remedial actions associated with the (High Containment Radiation) as they apply to the (High Containment Radiation)

(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 AO?) Flooding/ 8 (BW E03) Inadequate Subcooling Margin / 4 (BW E08; W E03) LOCA Cooldown-Depressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A 11 **; W E08) RCS Overcooling-Pressurized Thermal Shock/ 4 (CE A16) Excess RCS Leakage/ 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout/ 4

~ O ' Y Po;ot Tota IS' 9/4 I I 2 2 I 2 Group Point Total:

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S ,stems-Tier 2/Group 1 /RO/SRO)

Svstem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* KIA Topic(s) IR #

003 (SF4P RCP) Reactor Coolant X A3.05: Ability to monitor automatic operation of 2.7/2. 28 Pump the RCPS, including RCP lube oil and bearing lift 6 pumps 004 (SF1; SF2 CVCS) Chemical and X K6.07: Knowledge of the effect ofa loss or 2.7/2. 29 Volume Control malfunction on the following CVCS components: 8 Heat exchangers and condensers 005 (SF4P RHR) Residual Heat X X KS.OS: Knowledge of the operational implications 30 Removal of the plant response dming "solid plant": pressure change due to the relative incompressibility of 2.7/3.

water as they apply the RHRS I G2.2.42: Ability to recognize system parameters 3.9/4.

6 31 that are entry-level conditions for Technical Specifications.

006 (SF2; SF3 ECCS) Emergency X Kl .07: Knowledge of the physical connections 2.9/3. 32 Core Cooling and/or cause-effect relationships between the ECCS 3 and the MFW system 007 (SF5 PRTS) Pressurizer X KS.02: Knowledge of the operational implications 3.1/3. 33 Relief/Quench Tank of the method of forming a steam bubble in the 4 pressurizer as the apply to Pressmizer Relief Tank System 008 (SF8 CCW) Component Cooling X X Kl .02: Knowledge of the physical connections 3 .3/3. 35 Water and/or cause-effect relationships between the 4 CCWS and the Loads cooled by CCWS Al .04: Ability to predict and/or monitor changes in 36 parameters (to prevent exceeding design limits) associated with operating the CCWS controls including surge tank level. 3.1/3.

2 01 O (SF3 PZR PCS) Pressurizer X K4.01: Knowledge of Pressurizer Pressure Control 2.7/2. 37 Pressure Control System design feature(s) and/or interlock(s) which 9 provide for the spray valve wann-up 012 (SF? RPS) Reactor Protection X X K3.03: Knowledge of the effect that a loss or 3.1/3. 38 malfunction of the RPS will have on the steam 3 dump system (SDS)

A3 .05: Ability to monitor automatic operation of the RPS, including single and multiple channel trip 3.6/3.

indicators 7 39 013 (SF2 ESFAS) Engineered X X K4.13: Knowledge of the Engineered Safety 3.7/3. 40 Safety Features Actuation Features Actuation System (ESFAS) design 9 feature(s) and/or interlock(s) which provide for the MFW isolation/reset.

K6.0l: Knowledge of the effect of a loss or malfunction on the sensors and detectors will have on the ESFAS 2.7/3.

I 41

022 (SF5 CCS) Containment Cooling X A2.03: Ability to (a) predict the impacts of fan 2.6/3. 42 motor thennal overload/high-speed operation on the 0 CCS; and (b) based on those predictions, use procedures to COITect, control, or mitigate the consequences of fan motor thcnnal overload/high-speed operation 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray X X AK2. I: Knowledge of bus power supplies to the 3 .4/3. 43 Containment Spray pumps 6 A2.04: Ability to (a) predict the impacts of the failure of spray pump on the CCS; and (b) based on 44 those predictions, use procedures to c01Tect, 3.7/4.

control, or mitigate the consequences of the Failure I of spray pump when first going on recirculation.

039 (SF4S MSS) Main and Reheat X A4.07: Ability to manually operate and/or monitor 2.8/2. 45 Steam in the control room the steam dump valves 9 059 (SF4S MFW) Main Feedwater X K3.02: Knowledge of the effect that a loss or 3.6/3. 46 malfunction of the MFW will have on the AFW 7 system 061 (SF4S AFW) X Kl .07 knowledge of physical connections or 3.6/3. 47 Auxiliary/Emergency Feedwater cause/effect relationships between AFW and 8 emergencv water source.

062 (SF6 ED AC) AC Electrical X A 1.0 I: Ability to predict and/or monitor changes in 3.4/3. 48 Distribution parameters (to prevent exceeding design limits) 8 associated with operating the ac distribution system controls including significance ofD/G load limits 063 (SF6 ED DC) DC Electrical X G2.2.39: Knowledge ofless than or equal to one 3.9/4. 49 Distribution hour Technical Specification action statements for 5 systems.

064 (SF6 EDG) Emergency Diesel X X K2.03: Knowledge of bus power supplies to control 3.2/3. 50 Generator power 6 K4.0 I: Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for 51 trips while loading the ED/G (frequency, voltage, 3.8/4.

speed) I 073 (SF? PRM) Process Radiation X A4.0 I: Ability to manually operate and/or monitor 3.9/3. 52 Monitorin~ effluent release in the control room 9 076 (SF4S SW) Service Water X K2.08: Knowledge of bus power supplies to the 3.1/3. 53 ESF-actuated MOVs. 3 078 (SF8 IAS) Instrument Air X K3.02: Knowledge of the effect that a loss or 3.4/3. 54 malfunction of the lnstrnment Air System (IAS) 6 will have on systems having pneumatic valves and controls.

103 (SF5 CNT) Containment X A 1.0 I: Ability to predict and/or monitor changes in 3.7/4. 55 parameters (to prevent exceeding design limits) I associated with operating the containment system controls including containment pressure, temperature, and humidity.

G2.4.4: Ability to recognize abnonnal indications 4.5/4.

X for system operating parameters that are ent1y-level 7 34 condi'tions for emergency and abnonnal operating i procedures 053 (SF1; SF4P ICS*) Integrated Control

IIIIIIIIIIII I I KIA Category Point Totals:

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S 1stems Tier 2/Grouo 2 /RO/SRO)

Svstem #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* KIA Topic(s) IR #

001 (SF1 CRDS) Control Rod Drive X K2.05: Knowledge of bus power supplies to the 3.1/3. 56 M/G sets 5 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer A4.03: Ability to manually operate and/or monitor X PZR heaters in the control room 3.3/3. 57 Level Control 1 014 (SF1 RPI) Rod Position X Al .04: Ability to predict and/or monitor changes in 3.5/3. 58 Indication 8 parameters (to prevent exceeding design limits) associated with operating the RPlS controls, including axial and radial power distribution.

015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature 3.1/3. 59 X A2.01: Ability to (a) predict the impacts of the Monitor thennocouple open and sho1t circuits on the !TM 5 system; and (b) based on those predictions, use procedures to con-ect, control or mitigate the consequences ofthennocouple open and shmt circuits.

027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Puroe Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool X K4.03: Knowledge of design feature(s) and/or 2.6/2. 61 Cooling interlock(s) which provide for anti-siphon devices 9 034 (SF8 FHS) Fuel-Handling X G2. I .27: Knowledge of system pu1pose and/or 3.9/4. 62 Equipment function. 0 035 (SF 4P SG) Steam Generator KS.03: Knowledge of operational implications of X 2.8/3. 63 the shrink and swell concept as the apply to the I S/Gs.

041 (SF4S SOS) Steam K3.02: Knowledge of the effect that a loss or X 3.8/3. 60 Dump/Turbine Bypass Control malfunction of the SOS will have on the RCS. 9 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste X A3.02: Ability to monitor automatic operation of 3.6/3. 64 the Liquid Radwaste System including automatic 6 isolation.

071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation X Kl.OS: Knowledge of the physical connections 2.8/2. 65 Monitoring and/or cause- effect relationships between the ARM 9 system and the Main and Reheat Steam System 075 (SF8 CW) Circulating Water

079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation IEtegory Point Totals:

I I I I I 0 I I I I l Group Point Total: 10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Beaver Valley Unit 2 Date of Exam: November 6, 2017 Category K/A# Topic RO SRO-only IR # IR #

2.1.1 Knowledge of facility requirements for controlling 2.5 66 3 vital/controlled access.

2.1.3 Knowledge of shift or short-term relief turnover practices. 3.7 67

1. Conduct of 2.1.

Operations 2.1.

2.1.

2.1.

Subtotal 2 2.2.1 Knowledge of tagging and clearance procedures. 4.1 68 3

2.2.6 Knowledge of the process for making changes to procedures. 3.0 69 2.2.1 Knowledge of surveillance procedures. 3.7 70

2. Equipment 2 Control 2.2.

2.2.

2.2.

Subtotal 3 2.3.4 Knowledge ofradiation exposure limits under normal or 3.2 71 emergency conditions 2.3.1 Knowledge of radiological safety principles pertaining to 3.2 72 2 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked

3. Radiation high-radiation areas, aligning filters, etc.

Control 2.3.

2.3.

2.3.

2.3.

Subtotal 2 2.4.2 Knowledge of fire protection procedures. 3.3 73 5

2.4.1 Knowledge of EOP terms and definitions. 3.9 74 7

4. Emergency 2.4.2 Knowledge of the emergency plan. 3.1 75 Procedures/Plan 9 2.4.

2.4.

2.4.

Subtotal 3 Tier 3 Point Total Tier 3 10 7 Point Total

ES-401 PWR Examination Outline Form ES-401-2 Facilitv: Beaver Valley Unit 2 Date of Exam: November 6, 2017 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 18 3 3 6 Emergency and Abnormal Plant 2 N/A N/A 9 3 1 4 Evolutions Tier Totals 27 6 4 10 1 28 2 3 5 2.

Plant 2 10 1 2 3 Systems Tier Totals 38 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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 (JR) 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 D.1.b of ES-401 for the applicable KlAs.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' 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 a category 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 K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

G* Generic K/As

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

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 K1 K2 K3 A1 A2 G* KIA Topic(s) IR #

000007 (EPE 7; BW E02&E10; CE E02)

Reactor Trip, Stabilization, Recoverv / 1 000008 (APE 8) Pressurizer Vapor Space Accident/ 3 000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump X 2.4.35 Knowledge of local auxiliary operator tasks 3.8/4 76 Malfunctions / 4 during an emergency and the resultant operational .0 effects.

000022 (APE 22) Loss of Reactor Coolant Makeup/ 2 000025 (APE 25) Loss of Residual Heat Removal Svstem / 4 000026 (APE 26) Loss of Component Cooling Water/ 8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient X EA2.09 Ability to determine or interpret the 4.4/4 77 Without Scram / 1 occurrence of a main turbine/reactor trip as it .5 applies to an ATWS 000038 (EPE 38) Steam Generator Tube Rupture/ 3 000040 (APE 40; BW E05; CE E05; W E 12)

Steam Line Rupture-Excessive Heat Transfer/ 4 000054 (APE 54; CE E06) Loss of Main X 2.4.6 Knowledge of EOP mitigation strategies. 3.7/4 78 Feedwater /4 .7 000055 (EPE 55) Station Blackout/ 6 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus/ 6 000058 (APE 58) Loss of DC Power/ 6 X 2.4.11 Knowledge of abnormal condition 4.0/4 79 procedures .2 000062 (APE 62) Loss of Nuclear Service X AA2.01 Ability to determine and interpret the 2.9/3 80 Water I 4 location of a leak in the SWS as it applies to the .5 Loss of Nuclear Service Water 000065 (APE 65) Loss of Instrument Air/ 8 000077 (APE 77) Generator Voltage and Electric Grid Disturbances/ 6 (W E04) LOCA Outside Containment/ 3 (W E 11) Loss of Emergency Coolant X EA2.1 Ability to determine and interpret facility 3.4/4 81 Recirculation/ 4 conditions and selection of appropriate procedures .2 during abnormal and emergency operations as it applies to Loss of Emergency Coolant Recirculation.

(BW E04; W E05) Inadequate Heat Transfer-Loss of Secondary Heat Sink/ 4

I K/A Category Totals: 3 3 Group Point Total: 6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emerqencv and Abnormal Plant Evolutions Tier 1/Group 2 (RO/SRO\

E/APE # / Name/ Safety Function K1 K2 K3 A1 A2 G* KIA Topic(s) IR #

000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 X AK2.05 Knowledge of the 2.5/2 82 interrelations between the .8 Dropped Control Rod and control rod drive power supplies and logic circuits 000005 (APE 5) Inoperable/Stuck Control Rod/ 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction/ 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation/ 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents/ 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release/ 9 X AK2.02 Knowledge of the 2.7/2 83 interrelations between the .8 Accidental Liquid Radwaste Release and Radioactive-liquid monitors 000060 (APE 60) Accidental Gaseous Radwaste Release/ 9 X G2.4.30: Knowledge of which 2.2/3 84 events related to system .6 operations/status should be reported to outside agencies 000061 (APE 61) Area Radiation Monitoring System Alarms 17 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation/ 8 000069 (APE 69; W E14) Loss of Containment Integrity/ 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling/

4 000076 (APE 76) High Reactor Coolant Activity/ 9 000078 (APE 78*) RCS Leak/ 3 (W E01 & E02) Rediagnosis & SI Termination/ 3 X EA2.1 Ability to determine and 3.3/4 85 interpret facility conditions and .2 selection of appropriate procedures during abnormal and emergency operations as it applies to SI termination.

(W E13) Steam Generator Overpressure/ 4 (W E15) Containment Flooding/ 5 (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 AO?) Flooding / 8 (BW E03) Inadequate Subcooling Margin/ 4 (BW E08; W E03) LOCA Cooldown-Depressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A 11 **; W E08) RCS Overcooling-Pressurized Thermal Shock/ 4 (CE A16) Excess RCS Leakage/ 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout/ 4 IKIA Category Point Totals: I I I I I I I I I I I I I I I 13 I1 IGroup PointTotal: I 14 I

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems-Tier 2/Grouo 1 (RO/SRO)

System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* KIA Topic(sl IR #

003 (SF4P RCP) Reactor Coolant Pump 004 (SF1; SF2 CVCS) Chemical and Volume Control 005 (SF4P RHR) Residual Heat Removal 006 (SF2; SF3 ECCS) Emergency Core Cooling 007 (SF5 PRTS) Pressurizer X A2.01 Ability to (a) predict the impacts of a 3.9/4 86 Relief/Quench Tank stuck-open PORV or code safety on the PRTS; .2 and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of a stuck-open PORV or code safety.

008 (SF8 CCW) Component Cooling Water 010 (SF3 PZR PCS) Pressurizer Pressure Control 012 (SF? RPS) Reactor Protection X 2.4.41 Knowledge of the Emergency Action 2.9/4 87 Level thresholds and classifications. .6 013 (SF2 ESFAS) Engineered X 2.2.37 Ability to determine operability and/or 3.6/4 88 Safety Features Actuation availability of safety related equipment. .6 022 (SF5 CCS) Containment Cooling 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 039 (SF4S MSS) Main and Reheat Steam 059 (SF4S MFW) Main Feedwater X A2.11 Ability to (a) predict the impacts of the 3.0/3 90 failure of feedwater control system on the .3 MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of the failure of feedwater control system 061 (SF4S AFW)

Auxiliary/Emerqencv Feedwater 062 (SF6 ED AC) AC Electrical X G2.2.22 Knowledge of LCOs and safety limits 4.04. 89 Distribution 7 063 (SF6 ED DC) DC Electrical Distribution 064 (SF6 EDG) Emergency Diesel Generator 073 (SF? PRM) Process Radiation Monitorinq 076 (SF4S SW) Service Water 078 (SF8 IAS) Instrument Air

103 (SF5 CNT) Containment 053 (SF1; SF4P ICS*) Integrated Control K/A Cateoorv Point Totals: 2 3 Group Point Total: 5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S .tstems Tier 2/Grouo 2 (RO/SRO\

Svstem #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* KIA Topic(s) IR #

001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position X A2.06 Ability to (a) predict the impacts of the 2.6/3 91 Indication loss of LVDT; and (b) based on those on those .0 predictions, use procedures to correct, control, or mitigate the consequences of the loss of LVDT 015 (SF? NI) Nuclear Instrumentation 016 (SF? NNI) Nonnuclear Instrumentation 017 (SF? ITM) In-Core Temperature X 2.2.22 Knowledge of limiting conditions for 4.0/4 92 Monitor operations and safety limits. .7 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Coolina 034 (SF8 FHS) Fuel-Handling Equioment 035 (SF 4P SG) Steam Generator 041 (SF4S SOS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF? ARM) Area Radiation Monitorina 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection X 2.4.11 Knowledge of abnormal condition 4.0/4 93 procedures. .2 050 (SF 9 CRV*) Control Room Ventilation i = g o r y Point Totals:

IIIIIIIIIIII 1 2 Group PointTotal: '3 II

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Beaver Valley Unit 2 Date of Exam: November 6, 2017 Category KIA# Topic RO SRO-onlv IR # JR #

2.1.3 Knowledge of fuel handling responsibilities of SROs 3.9 94 5

2.1.3 Knowledge of primary and secondary plant chemistry 3.5 95 4 limits

1. Conduct of 2.1.

Operations 2.1.

2.1.

2.1.

Subtotal 2.2.3 Ability to analyze the effect of maintenance activities, 4.2 96 6 such as degraded power sources, on the status of limiting conditions for operations.

2.2.1 Knowledge of surveillance procedures. 4.1 97 2

2. Equipment Control 2.2.

2.2.

2.2.

2.2.

Subtotal 2.3.7 Ability to comply with radiation work permit requirements 3.6 98 during normal or abnormal conditions.

2.3.

3. Radiation 2.3.

Control 2.3.

2.3.

2.3.

Subtotal 2.4.4 Knowledge of emergency response facilities 3.8 99 2

2.4.2 Knowledge of the bases for prioritizing safety functions 4.4 100 2 durinq abnormal/emerqency operations

4. Emergency Procedures / 2.4.

Plan 2.4.

2.4.

2.4.

Subtotal Tier 3 Point Total 10 7 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier/Group Randomly Reason for Rejection Selected KIA

ES-401 Record of Rejected K/ As Form ES-401-4 Tier/ Randomly Reason for Rejection Group Selected KIA 1/1 #12 056 AA2.25 Overlaps with already written question #46. Reselecting in same system and selected AA2.75 1/2 #20 028 G2.l.19 Reselecting on basis of overlap with operating test scenarios. Selecting a new generic in the same system. Selected G2.4.46 2/1 #34 007 G2.4.4 Overlaps with already written question #86. There are several questions on PRTs. Randomly Reselecting a new system in same tier/group that hasn't been selected twice with a generic. Selected 103 Containment G2.4.4 2/1 #44 026 CS A3.0l Reselecting based on the overlap with an operating test JPM. Reselected in the same system. Only other A3 KIA (A3.02) would also overlap with JPM. JPM is to align CS system. Therefore reselected in A2 due to being light in A2 and heavy in A3"7randomly reselected A2.0l 2/1 #54 078 K3.03 BV cannot cross tie units. Reselecting within the same system and Kl A category. Randomly reselected K3.02 2/2 #60 028 K3.0l Hydrogen recombiners are retired in place and only have purgers.

Randomly Reselected system 075 Circulating Water K3.07 due to it being the only one :2:2.5 1/2 #84 060 G2.l.25 Not an SRO function. Randomly re-selected another generic to be G2.4.4 l on the same system.

2/2 #92 075 G2.2.22 There is no LCO or safety limit for Circulating water. Used this Kl A on a random sampling of the remaining eligible Tier 2 Group systems and used it on 017 In-Core Temperature Monitor.

2/1 #44 026 A2.0l Not operationally valid. Too difficult to write a question for. Randomly reselected A2.04 2/2 #60 075 K3.07 Circulating Water does not have any inputs into ESF AS. Reselected System 041 Steam Dump/Turbine Bypass Control K3 .02 1/2 #84 060 G2.4.41 G2.4.4 l was already used on question 87 and too similar of a question.

Reselected G2.4.30 1/2 #83 059 AK 2.01 Gas monitor KA in Liquid Waste system 2/2 #89 022 G 2.2.3 Multi Unit license KA, NA BV2 1/1 #1 007 EA 2.05 Seen in every sim scenario 2/1 #47 061 K 1.10 No connection between AFW and diesel fuel oil

ES-401 Record of Rejected K/As Form ES-401-4

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