ML15007A395

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Final Outlines (Folder 3)
ML15007A395
Person / Time
Site: Millstone Dominion icon.png
Issue date: 10/30/2014
From: Cote M
Dominion Nuclear Connecticut
To: Peter Presby
Operations Branch I
Shared Package
ML14043A009 List:
References
U01891
Download: ML15007A395 (33)
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Text

{{#Wiki_filter:2014 Millstone Unit 2 Op-Test Change Summary Part B- Control Room /In-Plant JPMS

  • Replaced JPM S-7
  • Replaced JPM S-8 Part C- Dynamic Scenario #3
  • Deleted one critical task, replaced another critical task
  • Replaced Events 2, 7 and 8

ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 2 (MP2 Date of Exam: October2014 RO KJA Category Points I\ SRO-Only Points I 

                                                                                                                                            ~

Tier Group K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G

  • Total \ G*

v

1. 1 2 3 3 5 2 3 18 \ 6 Emergency &

Abnormal 2 2 2 2 N/A 1 1 N/A 1 9 1\ I 4 Plant Evolutions Tier Totals 4 5 5 6 3 4 27 y_ 10 1 2 3 5 3 2 I 3 3 3 I 2 28 v I \ 5 2. Plant 2 I I 0 3 I 2 0 I 0 I 0 10 / \ 3 Systems Tier Totals 3 4 5 6 3 3 3 4 3 2 2 38 I \a

3. Generic Knowledge and Abilities Note:

Categories 1 2 2 3 3 2 4 3 10 I/ 1/ 2 3 4 

                                                                                                                                              \
1. Ensure that at least two topics from every applicable KJA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KJA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KJA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KJA categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 K/As.

8. On the following pages, enter the KJA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KJA catalog, and enter the KJA 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.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emerqenc and Abnormal Plant Evolutions- Tier 11Group 1 (RO I SRQ) EIAPE #I Name I Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000007 (BWIE02&E10; CEIE02) Reactor X EA1.2 Ability to operate and I or monitor 3.3 1 Trip - Stabilization - Recovery I 1 the following as they apply to the (Reactor Trip Recovery): Operating behavior characteristics of the facility. 000008 Pressurizer Vapor Space X AK3.01 Knowledge of the reasons for the 3.7 2 Accident I 3 following responses as they apply to the Pressurizer Vapor Space Accident: Why PZR level may come back on scale ifRCS is saturated. EKl.Ol Knowledge of the operational 000009 Small Break LOCA I 3 X 4.2 3 implications of the following concepts as they apply to the small break LOCA: Natural circulation and cooling, including reflux boiling 2.4.9 Knowledge of low power I shutdown 000011 Large Break LOCA I 3 X 3.8 4 implications in accident (e.g. LOCA or loss of RHR) mitigation strategies. 000015117 RCP Malfunctions I 4 X AA2.01 Ability to determine and interpret 3.0 5 the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Cause ofRCP failure 000022 Loss of Rx Coolant Makeup I 2 X AK3.02 Knowledge of the reasons for the 3.5 6 following responses as they apply to the Loss of Reactor Coolant Makeup: Actions contained in SOPs and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging AK2.05 Knowledge of the interrelations 000025 Loss of RHR System I 4 X 2.6 7 between the Loss of Residual Heat Removal System and the following: Reactor building sump QQQQ:le bess ef GemJ:leReRI GeeliR§J - - - - - - Randomly Deselected - - WaleF,I g QQQQ:l7 c-. . PFess~oJFi..:eF PFess~oJFe 

             "*           . .,      GeRIFel     -  -  -   -  -     -   Randomly Deselected                             -      -

000029 ATWS I 1 X 2.1.23 Ability to perform specific system 4.3 8 and integrated plant procedures during all modes of plant operation. 000038 Steam Gen. Tube Rupture I 3 X 2.1.7 Ability to evaluate plant performance 4.4 9 and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000040 (BWIE05; CEIE05; WIE12) X EK2.2 Knowledge of the interrelations 3.7 10 Steam Line Rupture - Excessive Heat between the (Excess Steam Demand) and Transfer I 4 the following: Facility's 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 000054 (CEIE06) Loss of Main X EA1.3 Ability to operate and I or monitor 3.2 11 Feedwater I 4 the following as they apply to the (Loss of Feedwater): Desired operating results during abnormal and emergency situations 000055 Station Blackout I 6 X EA1.04 Ability to operate and monitor the 3.5 12 following as they apply to a Station Blackout: Reduction of loads on the battery 000056 Loss of Off-site Power I 6 X AK1.04 Knowledge of the operational 3.1 13 implications of the following concepts as they apply to Loss of Offsite Power: Definition of saturation conditions, implication for the systems 000057 Loss of Vital AC lnst. Bus I 6 X AA1.02 Ability to operate and I or monitor 3.8 14 the following as they apply to the Loss of Vital AC Instrument Bus: Manual control ofPZR level 000058 Loss of DC Power I 6 X AA1.03 Ability to operate and I or monitor 3.1 15 the following as they apply to the Loss of DC Power: Vital and battery bus components 000062 Loss of Nuclear Svc Water I 4 AA2.06 Ability to determine and interpret X 2.8 16 the following as they apply to the Loss of Nuclear Service Water: The length of time after the loss of SWS flow to a component before that component may be damaged 000065 Loss of Instrument Air I 8 AK3.03 Knowledge of the reasons for the X 2.9 17 following responses as they apply to the Loss oflnstrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air VWEQ4 bGGA G~o~tsiae GentaiRFHeRt ,1 J - - - - - - Removed for CE Plant - - WIE~ ~ bess ef Effie~ensy Geelant - - - - - - Removed for CE Plant - - ResiFs. ,1 4 BlOUEQ4* lOUEQi ...... * " '

  • tr lnaae~:~~o~ate Flea!
                                               - - - - - - Removed for CE Plant                           -       -

000077 Generator Voltage and Electric X AK2.02 Knowledge of the interrelations 3.1 18 Grid Disturbances I 6 between Generator Voltage and Electric Grid Disturbances and the following: Breakers, relays KIA Cateqory Totals: 2 3 3 5 2 3 Group Point Total: 1816

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 I SRG) E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000001 Continuous Rod Withdrawal/1 X 2.4.46 Ability to verify that the 4.2 19 alarms are consistent with the plant conditions. QQQQQ:3 Qre1313e8 GeRtFel Res t~ - - - - - - Randomly Deselected - - 000005 Inoperable/Stuck Control Rod /1 X AKl.Ol Knowledge of the 3.1 20 operational implications of the following concepts as they apply to Inoperable I Stuck Control Rod: Axial power imbalance QQQQ24 ~lfleF§eAsy BeFatieR I~ - - - - - - Randomly Deselected - - QQQQ28 F!Fess~o~ri;;,er be11el Malf~o~RstieA /. 2 - - - - - - Randomly Deselected - - 000032 Loss of Source Range Nl/7 X AK3.01 Knowledge of the reasons 3.2 21 for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss ggggaa bess sf IAterlfleEliate RaR§e Nl ,1 7 - - - - - - Randomly Deselected - - 000036 (BW/A08) Fuel Handling Accident I 8 X AK3.03 Knowledge of the reasons 3.7 22 for the following responses as they apply to the Fuel Handling Incidents: Guidance contained in EOP for fuel handling incident QQQQ37 Stealfl GeReFater +~o~l:le beal~ fa - - - - - - Randomly Deselected - - 000051 Loss of Condenser Vacuum I 4 X AKl.Ol Knowledge of the 2.4 23 operational implications of the (LER 2010 following concepts as they apply to 003. 1R Loss of Condenser Vacuum: 20100 Relationship of condenser vacuum to 05.1R 20110 circulating water, 02) flow rate, and temperature QQQQ§9 AssiEleR!al bi(1~o~i8 RaElWaste Rei. ,1 9 - - - - - - Randomly Deselected - - QQQQlQ AssiEleRtal Gasee~o~s Rasv..aste Rei. t 9 - - - - - - Randomly Deselected - - 000061 ARM System Alarms I 7 X AAl.Ol Ability to operate and I or 3.6 24 monitor the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation QQQQ97 PlaRt FiFe GA site t 8 - - - - - - Randomly Deselected - - QQQQ98 tBl,o,l,l,A,Qej GeRtml Reelfl ~*~as. ,l 8 - - - - - - Randomly Deselected - -

000069 (WIE14) Loss of CTMT Integrity I 5 X AA2.02 Ability to determine and 3.9 25 interpret the following as they apply to the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity 000074 (WIE06&E07) lnad. Core Cooling I 4 X EK2.05 Knowledge of the 3.9 26 interrelations between the and the following Inadequate Core Cooling: LPI pumps QQQQ7e Fli§JR ReastaF GaalaRt ll.sti>1ity ,1 9 - - - - - - Randomly Deselected - - lNIEG~ & EQ2 ReEiia§!Rasis & Sl +eFFRiRatiaR I a - - - - - - Removed for CE Plant - - WIE~d SteaFR GeReFateF GveF j3FeSSliFe I 4 - - - - - - - - Removed for CE Plant l..WEH~ GaRtaiRFReR! FleaEiiR§ f. a - - - - - - Removed for CE Plant - - Wf.E~e Fli§JR GaRtaiRFReRt RaEiiatiaR ,1 g - - - - - - - - Removed forCE Plant e!l,lW,A.Q~ 121aRt RliRI:lask ,1 ~ - - - - - - - - Removed for CE Plant BW,lAQ2&AQ.3 bass ef ~J~JI XJ.¥ ,1 7 - - - - - - - - Removed for CE Plant E!V\WI.Q4 =l=liFI:liRe =l=Fij3 I 4 - - - - - - Removed for CE Plant - - BW,lAQ§ EFReF§IeRsy 9iesel Ast~o~atiaR Ie - - - - - - Removed for CE Plant - - Bl/>UAQ7 FleaEiiR§I ,l 8 - - - - - - Removed for CE Plant - - BVWEQ.3 IRaEie(1llate S~o~l:lseeliR§J MaF§JiR I 4 - - - - - - - - Removed for CE Plant BWIEQ8; W,lEQ.3 bGGA GaeiEiewR 9ej3Fess.l 4 - - - - - - Removed for CE Plant - - BWIE09; CEIA13; WIE09&E10 Natural Circ. I 4 X AK2.1 Knowledge of the 3.0 27 interrelations between the (Natural Circulation Operations) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features E!VVfE~ .3&E~ 4 EGI2 R~o~les aRE! ERGies~o~Fes - - - - - - - - Removed for CE Plant GElA~ ~; li>UEQ8 RGS GveFGaeliR§J 12+S ,1 4 - - - - - - Randomly Deselected - - GEf.A~e EXGess RGS beaiEa§le I 2 - - - - - - Randomly Deselected - - GEIEQ9 Fio~RGtiaRal ResaveFy - - - - - - Randomly Deselected - - KJA Category Point Totals: 2 2 2 I 1 1 Group Point Total: 914

ES-401 4 Form ES-401-2 Fo cc tni ..., ES-401 PWR Examination Outline PlantS stems- Tier 2/Group 1 (RO I SRG) System #I Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump X K2.02 Knowledge of bus power 2.5 28 (RCPS) supplies to the following: CCW pumps 003 Reactor Coolant Pump X A3.05 Ability to monitor 2.7 29 (RCPS) automatic operation of the RePS, including: RCP lube oil and bearing lift pumps A2.22 Ability to (a) predict the 004 Chemical and Volume X 3.2 30 Control (CVCS) impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions: Mismatch of letdown and charging flows. K3.07 Knowledge of the effect 005 Residual Heat Removal X 3.2 31 (RHRS) that a loss or malfunction of the RHRS will have on the following: Refueling operations Al.lS Ability to predict and/or 006 Emergency Core Cooling X 3.3 32 (ECCS) monitor changes in parameters (to prevent exceeding design limits) associated with operating the Eees controls including: RWST level and temperature K5.02 Knowledge of the 007 Pressurizer Relief/Quench X 3.1 33 Tank (PRTS) operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR K3.01 Knowledge of the effect 008 Component Cooling Water X 3.4 34 (CCWS) that a loss or malfunction of the eews will have on the following: Loads cooled by CCWS 010 Pressurizer Pressure Control X K6.03 Knowledge of the effect of 3.2 35 (PZR PCS) a loss or malfunction of the following will have on the PZR PeS: PZR sprays and heaters

A2.07 Ability to (a) predict the 36 012 Reactor Protection (RPS) X 3.2 impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of de control power K4.03 Knowledge of ESF AS 013 Engineered Safety Features X 3.9 37 Actuation (ESFAS) design feature(s) and/or interlock(s) which provide for the following: Main Steam Isolation System 013 Engineered Safety Features X K4.07 Knowledge of ESF AS 3.7 38 Actuation (ESFAS) design feature(s) and/or interlock(s) which provide for the followin_g: Power Supply Loss Kl.Ol Knowledge of the physical 022 Containment Cooling (CCS) X 3.5 39 connections and/or cause effect relationships between the CCS and the following systems: SWS/cooling system Al.02 Ability to predict and/or 022 Containment Cooling (CCS) X 3.6 40 monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Containment pressure Q~a lse GeAEieAseF - - - - - - - - - - - MP2 does not have system - - K4.05 Knowledge of CSS design 026 Containment Spray (CSS) X 2.8 41 feature(s) and/or interlock(s) which provide for the following: Prevention of material from clogging nozzles during recirculation Kl.Ol Knowledge of the physical 039 Main and Reheat Steam X 3.1 42 (MRSS) connections and/or cause-effect relationships between the MRSS and the following systems: S/G 059 Main Feedwater (MFW) X 2.2.44 Ability to interpret control 4.2 43 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 061 Auxiliary/Emergency X A3.03 Ability to monitor 3.9 44 Feedwater (AFW) automatic operation of the AFW, including: AFW S/G level control on automatic start

A4.03 Ability to manually operate 062 AC Electrical Distribution X 2.8 45 and/or monitor in the control room: Synchroscope, including an understanding of running and incoming voltages 063 DC Electrical Distribution X K2.01 Knowledge of bus power 2.9 46 supplies to the following: Major DC loads A2.13 Ability to (a) predict the 064 Emergency Diesel Generator X 2.6 47 (ED/G) impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequences of opening auxiliary feeder bus (ED/G sub supply) K3.03 Knowledge of the effect 064 Emergency Diesel Generator X 3.6 48 (ED/G) that a loss or malfunction of the ED/G system will have on the following: ED/G (manual loads) Al.Ol Ability to predict and/or 073 Process Radiation X 3.2 49 Monitoring (PRM) monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels KS.Ol Knowledge of the 073 Process Radiation X 2.5 50 Monitoring (PRM) operational implications as they apply to concepts as they apply to the PRM system: Radiation theory, including sources, types, units, and effects K2.02 Knowledge of bus supplies 026 Containment Spray (CSS) X 2.7 51 to the following: MOVs 076 Service Water (SWS) X 2.2.22 Knowledge of limiting 4.0 52 conditions for operations and safety limits. K3.01 Knowledge of the effect 078 Instrument Air (lAS) X 3.1 53 that a loss or malfunction of the lAS will have on the following: Containment air system K3.02 Knowledge of the effect 078 Instrument Air (lAS) X 3.4 54 that a loss or malfunction of the lAS will have on the following: Systems having pneumatic valves and controls A3.01 Ability to monitor 103 Containment X 3.9 55 automatic operation of the containment system, including: Containment isolation KIA Cate11QryPoint Totals: 2 3 5 3 2 I 3 3 3 I 2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlantS stems -Tier 21Group 2 (RO I~) System #I Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 QQ~ GeAtFal Rea QFive - - - - - - - - - - - Randomly Deselected - - QQ:l ReasteF GeelaAt - - - - - - - - - - - Randomly Deselected - - K6.03 Knowledge of the effect of a 011 Pressurizer Level Control X 2.9 56 (PZR LCS) loss or malfunction on the following will have on the PZR LCS: Relationship between PZR level and PZR heater control circuit. 014 Rod Position Indication - - - X - - - - - - - K4.06 Knowledge ofRPS design 3.4 59 features and/or interlocks which provide for the following: individual and group misalignment. 015 Nuclear Instrumentation (NIS) X K6.04 Knowledge of the effect of a 3.1 57 loss or malfunction on the following will have on the NIS: Bistables and logic circuits. QHl ~leA AlolSieaF IAStF~oJmeAtatieA - - - - - - - - - - - Randomly Deselected - - QH lA seFe +emJ3eFat~oJFe MeAiteF - - - - - - - - - - Randomly Deselected - - KS.Ol Knowledge of the operational 027 Containment Iodine Removal X 3.1 58 (CIRS) implications of the following concepts as they apply to the CIRS: Purpose of charcoal filters Q:l!l FlyaFa§eA ResemsiAeF - - - - - - - - - - - Randomly Deselected - - Rejected 029 Containment Purqe (CPS) K4.01 Knowledge of design 033 Spent Fuel Pool Cooling X 2.9 60 (SFPCS) feature(s) and/or interlock(s) which provide for the following: Maintenance of spent fuel level f"I'>A Co c. . '~ ,~, 

                                     - - -  -   -  -  -   -   -      -   Randomly Deselected                       -

Gda gteam GeAeFateF - - - - - - - - Randomly Deselected - A2.02 Ability to (a) predict the 61 041 Steam Dump System (SDS) X 3.6 and Turbine Bypass Control impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations: Steam valve stuck open K4.11 Knowledge ofMT/G system 045 Main Turbine Generator X 3.6 62 (MTIG) design feature(s) and/or interlock(s) which provide for the following: T/G reactor trip

Kl.06 Knowledge of the physical 055 Condenser Air Removal X 2.6 63 (CARS) connections and/or cause effect relationships between the CARS and the following systems: PRM system 056 Condensate X A2.04 Ability to (a) predict the - 65 impacts of the following malfunctions or operations on the Condensate system; and (b) based on those predications, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps Qe!! biEJlliEl RaEl'A'asle - - - - - - - - - - - Randomly Deselected - - A4.26 Ability to manually operate 071 Waste Gas Disposal (WGDS) X 3.1 64 and/or monitor in the control room: Authorized waste gas release, conducted in compliance with radioactive gas discharge permit n7"l A o. * - - - - - - - - - - - Randomly Deselected - - Q7a GiFGlllaliA§ Wa!eF Rejected ~ M Q7Q :::ltaliaA AiF - - - - - - - - - - - Randomly Deselected - - Q!!e FiFe i=!FalestiaA - - - - - - - - - - Randomly Deselected - - KJA Category Point Totals: I 0 0 3 I 2 0 2 0 I 0 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3} Form ES-401-3 Facility: Millstone Unit 2 Date of Exam: October 2014 Category KIA# Topic RO SRO-Only IR # IR # I 1. Conduct 2.1.13 2.1.37 Knowledge of facility requirements for controlling vitaVcontrolled access. Knowledge of procedures, guidelines, or limitations 2.5 4.3 66 67 

                                                                                                     \                1 of Operations                 associated with reactivity management.

Subtotal 2 \ 2.2.6 Knowledge of the process for making changes to 3.0 68 procedures.

2. 2.2.13 Knowledge of tagging and clearance procedures. 4.1 69 \ I
                                                                                                             \\ 1/I Equipment Control            2.2.22     Knowledge of limiting conditions for operations and       4.0      70 safety limits.

Subtotal 3 Knowledge of radiological safety principles pertaining to 2.3.12 3.2 71 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to

3. locked high-radiation areas, aligning filters, etc. J~

Radiation II \\ Knowledge of radiation or contamination hazards that Control 2.3. 14 3.4 72 may arise during normal, abnormal, or emergency conditions or activities. Subtotal 2 2.4.4 Ability to recognize abnormal indications for system 4.5 73 operating parameters that are entry-level conditions for

4. emergency and abnormal operating procedures.

Emergency Ability to verify that the alarms are consistent with the Procedures I 2.4.46 4.2 74 Plan plant conditions. 2.4.18 Knowledge of the specific bases for EOPs. 3.3 75 1/ Subtotal 3 ~ \ Tier 3 Point Total 10 7

ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 2 Date of Exam: October 2014 

                                       ~                   RO KJA Category Points                  /                    SRO-Only Points v

Tier Group K 1 

                                              " I}N K

2 K K 5 K 6 A 1 A 2 A A ~ 3 %__

  • Total A2 G* Total v
                                                           ~v
1. 1 18 3 3 6 Emergency & v Abnormal 2 N/A 9 2 2 4 Plant
                                                              /

Evolutions 2. Tier Totals 1 v v "" ' "' ['.. 27 28 5 3 5 2 10 5 Plant Systems 2 Tier Totals v 

                                              /
                                                                                            ""     ~

10 K41 II 5 2 0 2 8 3 r--::I I I I I I

3. Generic Knowledge and Abilities ~~

3 ~ 1 2 3 4 7 Categories ~ 1---- 2 2 I 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those 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 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#)

on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergencv and Abnormal Plant Evolutions - Tier 11Group 1. (RG I SRO) EIAPE #I Name I Safety Function KKKAA G KIA Topic(s) IR # 1 2 3 1 2 000007 (BWIE02&E10; CE/E02) Reastor Randomly Deselected To' D. 'nn. 1 000008 Pressurizer Vapor £pase Randomly Deselected 1\ssident I 3 EA2.02 Ability to determine or interpret 000009 Small Break LOCA I 3 X 3.8 76 the following as they apply to a small break LOCA: Possible leak paths 000011 Large Break LOCA I 3 X 2.4.6 Knowledge of EOP Mitigation 4.7 78 Strategies AA2.10 Ability to determine and interpret 000015117 RCP Malfunctions I 4 X 3.7 77 the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on loss of cooling or seal injection Randomly Deselected 000022 boss of Rx Coolant Makeup I 2 000025 boss of RI=IR Systern f 4 Randomly Deselected 2.4.49 Ability to perform without reference 4.4 000026 Loss of Component Cooling X 79 Water 18 to procedures those actions that require immediate operation of system components and controls. 000027 Pressurizer Pressure Control Randomly Deselected 000029 AnA.'£ I 1 Randomly Deselected 000038 Stearn Gen. Tube Rupture I 3 Randomly Deselected 000040 (BVV!E05; CEIE05; WIE12) Randomly Deselected Stearn line Rupture Exsessive l=leat Transfer I 4 000054 (CEIE06) boss of Main Randomly Deselected Feed*.vater I 4 EA2.06 Ability to determine or interpret 000055 Station Blackout I 6 X 4.1 80 the following as they apply to a Station Blackout: Faults and lockouts that must be cleared prior to re-energizing buses 000056 boss of Off site PO'over I 6 Randomly Deselected 000057 boss of Vital AC lnst. Bus I 6 Randomly Deselected 2.4.30 Knowledge of events related to 000058 Loss of DC Power I 6 X 4.1 81 system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission ~stem oi>_erator. Randomly Deselected 000065 boss of Instrument Air I 8 Randomly Deselected

WII:OQ4 bGGA Glol!siae GeRtaiRrneRt I~ - - - - - - Removed for CE Plant - - lJI/,11:0~ ~ bess ef l:erneF§eRsy GeelaAt - - - - - - Removed for CE Plant - - ResiFG. I 4 BWII:OQ4; VW!:OQa IAa8eEjlolate Flea! T. ,, . CO: 

                                            - - - - - - Removed for CE Plant -   -

QQQQ77 GeAeFateF Velta§e aA8 l:elestFiG - - - - - - Randomly Deselected - - GFia gjstlolFSaAGes ,l e KJA Category Totals: 0 0 0 0 3 3 Group Point Total: 18/6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 11Group 2 (RG I SRO) EIAPE #I Name I Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 ggggg~ GeRtiRllells ReEl WitRElrawal /. ~ - - - - - - Randomly Deselected - - QQQQQJ gF8J3J3eEl GeRtFel ReEl /. ~ - - - - - - Randomly Deselected - - QQQQQa IReJ3eral:lle/.atllsl~ GeRtFel ReEl /. ~ - - - - - - Randomly Deselected - - QQQQ24 E:meF§eRsy BeFatieR /. ~ - - - - - - Randomly Deselected - - QQQQ2!l FlFesslJFii!eF be>1el MalfllRstieR f. 2 - - - - - - Randomly Deselected - - QQQQJ2 bess ef Se~oJFse RaR§e Nl /. 7 - - - - - - Randomly Deselected - - ggggaa bess ef IRteFmeEliate RaR§e Nil- 7 - - - - - - Randomly Deselected - - QQQQJe \BVl.W\.Q!l) Fllel F1aRElliR§ AssiEleAt f. g - - - - - - Randomly Deselected - - 000037 Steam Generator Tube Leak I 3 X AA2.12 Ability to determine and 4.1 82 interpret the following as they apply to the Steam Generator Tube Leak: Flow rate of leak QQQQa~ bess ef GeREleRseF VaSllllm /. 4 - - - - - - Randomly Deselected - - 000059 Accidental Liquid RadWaste Rei. I 9 X 2.2.38 Knowledge of conditions and 3.6 83 limitations in the facility license. gggg(Jg AssiEleRtal Gasee~oJs RaEJy,raste Rei. 1- 9 - - - - - - Randomly Deselected - - QQQQe~ ARM System AlaFms /. 7 - - - - - - Randomly Deselected - - 000067 Plant Fire On-site I 8 X 2.2.37 Ability to determine 4.6 84 operability and/or availability of safety related equipment. QQQQe!l (BVV/AQe) GeRtFel Reem E:vas. f. g - - - - - - Randomly Deselected - - QQQQe9 \W/E: ~ 4) bess ef GTMT IRte§Fity /. a  !-n~..r2.02 ,~..rbility to deteFmiRe aRd 44

  • iRteFpFet the fellowiRg as they aJJJJiy S4 to the boss of GoRtaiRmeRt IRtegFity: Vefi:fieati:sR sf aHtematie asd maRHal meaas of festefiag integfity Kl A rejected due to overlap with RO exam.

QQQQ74 (VV/.E:9e&E:Q7) IRaEl. GeFe GeeliR§ f. 4 - - - - - - Randomly Deselected - - gggg7e Fli§R ReasteF GeelaRt Astivity /. 9 - - - - - - Randomly Deselected - - VWE:G~ & E:Q2 ReElia§Resis & Sl TeFmiRatieR /. a - - - - - - Removed for CE Plant - - Vl/1-E:~ a Steam GeAeFateF G>ieF J3FeSSllFe /. 4 - - - - - - Removed for CE Plant - - WIE:~ a GeRtaiRmeRt Flee8iR§ I a - - - - - - - 

                                                                           -          Removed for CE Plant
'.ilJI.E:~e F1i§i=l GeRtaiRmeRt RaeiatieR ,1 9                 -   -   -   -  -   -                                                 -         -

Removed for CE Plant BW/.1\Q~ PlaRt RllAI:lask / ~ - - - - - - Removed for CE Plant - - BlJI//,li,Q2&AQJ bess ef ~J~JI XJ.¥ ,1 7 - - - - - - Removed for CE Plant - -

Bl.*W,A,Q4 =i=llFBiAe =!=FifJ 1- 4 - - - - - - - - Removed for CE Plant BIJl.l,IAQa E:FfleF§eAG'f Diesel ,ll,stlJatieA 1- e - - - - - - Removed for CE Plant - - BW,~li,Q7 FleeEliA§ 1- g - - - - - - - - Removed for CE Plant BW,lE:Qd IAaEle(1llate Sl!sseeliA§ MaF§iA 1- 4 - - - - - - Removed for CE Plant - - BW,lE:Q8; W/-E:Qd bGGA GeeiElewA Qef)Fess./- 4 - - - - - - - - Removed for CE Plant BW,lE:Q9; GE:.~A.~ d; WI-E:Q9&E:Hl ~latl!Fal GiFG. ,l 4 - - - - - - Randomly Deselected - - BW/-E:~ d&E:~ 4 E:GI2 Rllles aAEl E:Aslesl!Fes - - - - - - - - Removed for CE Plant GE:I-A~ ~; W,lE;Qg RGS G*ieFseeliA§ P+S ,l4 - - - - - - Randomly Deselected - - GE:.tAH~ E:*sess RGS beakage 1- 2 - - - - - - Randomly_Deselected - - CE/E09 Functional Recovery X EA2.1 Ability to determine and 4.4 85 interpret the following as they apply to the (Functional Recovery): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. lA I". 

                  "'* 'nt Totals:                           0 0 0 0 2 2 Group Point Total:                          9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlantS stems -Tier 21Grou ~ 1 (RG I SRO) System #I Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 A2.01 Ability to (a) predict the 003 Reactor Coolant Pump X 3.9 86 (RCPS) impacts of the following malfunctions or operations on the RePS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Problems with RCP seals, especially rates of seal leak-off A2.15 Ability to (a) predict the 004 Chemical and Volume X 3.7 87 Control (CVCS) impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level QQ§ ResiEiio~al l=leai Remeval - - - - - - - - - - - Randomly Deselected - - 

~

GQl effiGF§leAGy Gere GeeliA§ - - - - - - - - - - - Randomly Deselected - - 

~

GO+-P-ress~-Rel+efiQtfeflBf1 - - - - - - - - - - - Randomly Deselected - - l=<lffk-1-P-R+S) QQg Gemf)eAeA! GeeliA§JlNa!er - - - - - - - - - - - Randomly Deselected - - fGGWS-) 2.2.25 Knowledge of the bases in 010 Pressurizer Pressure Control - - - - - - - - - - - 4.2 89 (PZR PCS) Technical Specifications for limiting conditions for operations and safety limits. A2.02 t 4..bility te (a) pFediet the 012 Reaetor ProteetioA (RPS) - - - - - - - .X: - - -  ;;-,9 && impaets ef the fullewing malfunetiens eF epentions on the R¥S; and (b) based en those pFedietions, use pFoeedaFes te eeFFeet, eontFel, eF mitigate the eonse(fHenees ef those malfunetiens eF epeFatiens: bess sf instrument pewer Kl A rejected due to overlap with ROexam. G1 g eA§iAeereEl Safely 

,1\ettJaiieA (ES~.C*,S)
                             ~eattJres - - -  -   -  -  -   -   -  -     -   Randomly Deselected                      -       -

Questioned rejected due to 022 Containment Cooling (CCS) oversampling ees.

G:la lse GeneenseF - - - - - - - - - - - MP2 does not have system - - A2.04 Ability to (a) predict the 026 Containment Spray (CSS) X 4.2 88 impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic recirculation transfer W-9-Main and Reheat-Steam - - - - - - - - - - - Randomly Deselected - - ~ G&9-Maifl-F-eedwatf--{-MfWj - - - - - - - - - - - Randomly Deselected - - Ge+At!*iliafyf.emef§BBGY - - - - - - - - - - - Randomly Deselected - - f: 'AFW-j 2.2.40 Ability to apply Technical 062 AC Electrical Distribution X 4,7 90 Specifications for a System. QJJ QG e;lee\Fieal Dislril:llo~tien - - - - - - - - - - Randomly Deselected - - 004-E-ffifgf+Gy Diesel Generettlf - - - - - - - - - - - Randomly Deselected - - ~ 073-P+eees&-Radlal+eR IP-RM) 

                                     - - - - - - - - - - - Randomly Deselected                -     -

G1-&-Setvite-WareF-fSWS) - - - - - - - - - - - Randomly Deselected - - 0+&-IBStrtlfR&nt-A~ - - - - - - - - - - - Randomly Deselected - - q03 Gen!ainrnerrt - - - - - - - - - - Randomly Deselected - - K!A Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlantS stems -Tier 21Group 2 (RG I SRO) System #I Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 gg~ GaA!Fel Rea gFive - - - - - - - - - - - Randomly Deselected - - QQ2 ReastaF GaalaAt - - - - - - - - - - - Randomly Deselected - - Q~ ~ PFeSSt,JFi;;:eF be~*el GaA!Fal - - - - - - - - - - - Randomly Deselected - - ro7o rc: Q~ 4 Rea PasitiaA IAaisatiaA - - - - - - - - - - - Randomly Deselected - - A2.05 Ability to (a) predict the 015 Nuclear Instrumentation (NIS) X 3.8 91 impacts of the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core void formation QHi ~JaR At,JGieaF IAS!Ft,Jffi9A!a!i9A - - - - - - - - - - - Randomly Deselected - - Q~ 7 lA saFe +emJ3eFalt,JFe MaAitaF - - - - - - - - - - - Randomly Deselected - - Q27 GaAtaiAmeAt laaiAe Remaval - - - - - - - - - - - Randomly Deselected - - 

~

Q28 ~yaFa!iJeA ResamsiAeF - - - - - - - - - - - Randomly Deselected - - orl Doorn r, ,n Q29 GaAtaiAmeAI Pl,IF!iJe (GPg) - - - - - - - - - - - Randomly Deselected - - A2.03 Ability to (a) predict the 033 Spent Fuel Pool Cooling X 3.5 92 (SFPCS) impacts of the following malfunctions or operations on the SFPCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level 

                                                                                     ~.01 Knawledge af the effeet that 9d4    ft,Jel   ~aAaliA!iJ  Eqt,JiJ3meAt      -  -  ~   -  -   -  -   -  -   -  -                                              ;&.-9  ~

a lass 91' malfunetian af the Fuel Handling System willha>,*e 9B the fullawing: Coe:taiflffieBt veHtilatioH Kl A rejected due to overlap with RO exam. K4.02 Knowledge of design 034 Fuel Handling Equipment X 3.3 93 feature(s) and/or interlock(s) which provide for the following: Fuel movement Gda gteam GeAeFataF - - - - - - - - - - - Randomly Deselected - - Q4~ gteam gl,lffiJ'l gystem (SgS) - - - - - - - - - - - Randomly Deselected - - T, " D* r-,

Q4§ MaiA +llFeiAe GeAeFateF - - - - - - - - - - - Randomly Deselected - - {M+IG} Q§§ GeA8eAseF AiF ReFAe\*al - - - - - - - - - - - Randomly Deselected - - .~ Q§e GeAaeAsate - - - - - - - - - - - Randomly Deselected - - Ql8 biEJlli8 Ra8\Naste - - - - - - - - - - - Randomly Deselected - - Q7~ \1\laste Gas Qis~esal (WGQS) - - - - - - - - - - - Randomly Deselected - - Q72 AFea RaaiatieA MeAiteFiA§ - - - - - - - - - - - Randomly Deselected - - Q7a GiFslllatiA§ WateF - - - - - - - - - - - Randomly Deselected - - Q79 StatieA AiF - - - - - - - - - - - Randomly Deselected - - Q!!e FiFe PmtestieA - - - - - - - - - - - Randomly Deselected - - KIA Category Point Totals: 0 0 0 I 0 0 0 2 0 0 0 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3} Form ES-401-3 Facility: Millstone Unit 2 Date of Exam: October 2014 Category K/A# Topic RO SRO-Only IR # IR # Ability to use procedures related to shift staffing, such as 1. Conduct 2.1.5 minimum crew complement, overtime limitations, etc. 1\ I 3.9 94 

                                                                                           \\ II Ability to perform specific system and of Operations       2.1.23                                                                                 4.4     95 integrated plant procedures during all modes of plant operation.

Subtotal 2 

                                                                                              \I Ability to perform pre-startup procedures for the facility,
2. 2.2.1 4.4 96 including operating those controls associated with plant Equipment equipment that could affect reactivity.

Control 2.2.37 Ability to determine operability and/or availability of safety related equipment. \1/ 4.6 97 Subtotal 2 3. Radiation 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. I1\ 3.7 98 Control 2.3.- Randomly Deselected I \ - - Subtotal I \ 1 4. Emergency 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. I \ 4.4 99 Procedures I Plan 2.4.37 Knowledge of the lines of authority during implementation of the emergency plan. I \ 4.1 100 Subtotal I \ 2 Tier 3 Point Total 10 7

ES-40~1~----------------~R~e~c~o~r~d~o~f~R=e~je~c~te~d~~=A~s~----------~F=o=r=m=E=S=-=4=0=1-=4~ Tier I Randomly Reason for Rejection Group Selected KlA SROl/2 069 AA2.02 Kl A was also randomly selected on the RO exam. Reselected E/APE 000059 AA 2.03Accidental Liquid Radwaste Release. (Q#83) SRO 211 012 A2.02 A similar KIA was randomly selected on the RO exam: RPS A2.07, Ability to (a) predict the impacts of the following malfunctions or (Q#88) operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of de control power (RO Q#36) Kl A would test similar concepts. Reselected Plant System 026 Containment Spray, A2.04 SRO 2/2 034 K3.01 Kl A tests similar concept, automatic purge isolation that appears on RO written exam in question #59 for the Fuel Handling Equipment (Q#93) System. Re-selected K4.02. R03 G2.4.6 Could not write a good RO question to 2.4.6 EOP mitigation strategies. Randomly selected 2.4.4 entry level conditions for EOP (Q#73) and abnormal procedures. R03 G2.4.13 Could not write a good RO question to 2.4.13 Knowledge of crew responsibilities. Randomly selected 2.4.46 Ability to verify that the (Q#74) alarms are consistent with the plant conditions. SRO 1/2 2.2.37 Could not write a discriminating SRO question for entry conditions for KA 2.4.4 AOPs, EOPs for Plant Fire system. Randomly (Q#84) selected 2.2.37. RO 2/1 013 K4.16 Could not find write a discriminating question for ESF AS "to avoid PTS." Randomly selected K4.07, Power Supply Loss. (Q#38) R02/2 015 A4.01 Could not find write a discriminating question for NIS "Selection of controlling channel." Randomly selected K6.04, Bistables and (Q#57) logic circuit. R03 G2.1.13 +hi,; K/.'\ i~; J3erferHleEI f:Jy See~::~:rity 13emeHHel at: Mills~eHe aHE:! net relevant for Reactor Operators. Randomly selected G 2.1.23. (Q#66) Located an acceptable bank Q that tests the original G2.1.13 at an appropriate license level. Returned to the originally selected Kl A G2.1.13. RO 111 029 G2.1.25 Could not write an ATWS question that was discriminating using the ability to interpret reference material. Randomly selected 2.1.23. (Q#8) RO 1/1 038 G2.1.31 Could not write a SGTR question that was discriminating using the ability to locate control room switches. Randomly selected 2.1.7. (Q#9) R02/1 006 A1.14 Could not write a discriminating question for monitoring controls for reactor level. Randomly selected Al.l5. (Q#32)

ES-401 Record of Rejected Kl As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA SROl/1 011 G2.2.39 Knowledge of less than one hour TS is RO knowledge. Could not write a SRO only question. Re-selected 2.4.6. (Q#78) SRO 211 062 G2.2.42 Knowledge of entry level TS conditions is RO knowledge. Could not write a SRO only question. Re-selected 2.2.40. (Q#90) R02/1 004 Al.ll Could not write question to 004 Al.ll. Re-selected 004 A2.22 Predict impact of mismatch of charging I letdown and mitigate. (Q#30) RO 2/2 045K5.18 Could not find write a discriminating question for MT/G K5 .18. Reselected 045 K4.11. (Q#62) R03 G2.2.35 Could not find write a discriminating question for G2.2.35. Reselected G2.2.22. (Q#70) SRO G2.1.23 Could not find write a discriminating SRO question for G2.1.29. (Q#95) Reselected G2.1.23. SRO System 022 Rejected question based on oversampling system. Reselected System 010 Pressurizer Pressure control. (Q#89) RO System 022 Rejected question based on oversampling system. Reselected System 014 Rod Position Indications. (Q#59) SRO AA2.03 KA changed due to could not write sro level question to ka. Selected generic.2.2.38 which was more appropriate for ODCM (Q#83) question. RO 2/1 System 076 System rejected because of oversampling of service water system. Randomly selected Containment Spray System as a replacement. (Q#51) RO 2/2 System 075 System and KA rejected because of oversampling of service water system. Randomly selected Condensate System KA A2.04 as a (Q#65) replacement.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: October 2014 Examination Level: SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code* KIA: 001, A4.1 0: Determination of an ECP (3.9) Conduct of Operations R,N ADMIN SR0-1 JPM: Review and Approve an ECP Manual Calculation KIA: 2.1.36 Knowledge of procedures and limitations Conduct of Operations R,D involved in core a Iterations ( 4. 1) ADMIN SR0-2 JPM: Loss of Containment Closure KIA: 2.2.40 Ability to apply Tech Specs (4.7) Equipment Control R,N ADMIN SR0-3 JPM: Technical Specification Evaluation KIA: 2.3.6 Ability to approve release permits (3.8) Radiation Control R,P,D ADMIN SR0-4 JPM: Review and Approve Liquid Waste Release Permit KIA: 2.4.41 Knowledge of the emergency action level Emergency Procedures/Plan R,M thresholds and classifications. (4.6) ADMIN SR0-5 JPM: Classify the Event and Determine the PAR NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • 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 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: October 2014 Examination Level: RO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code* R,M KIA: Conduct of Operations 2.1.20 Ability to execute procedure steps. (4.6) (ADMIN R0-1) JPM: Shutdown Safety Assessment Time to Core Boil Conduct of Operations R,D KIA: (ADMIN R0-2) 001, A4.1 0: Determination of an ECP (3.5) JPM: Perform ECP Manual Calculation R,N KIA: Equipment Control 2.2.12 Knowledge of surveillance procedures (3. 7) (ADMIN R0-3) JPM: Perform Borated Water Sources Surveillance R,D KIA: Radiation Control 2.3.7 Ability to comply with RWP requirements (ADMIN R0-4) during normal or abnormal conditions (3.5) JPM: Review RWP and Survey Map NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • 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: Millstone Unit 2 Date of Examination: October 2014 Exam Level: RO SR0-1 SRO-U Operating Test No.: NRC Control Room Systems© (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF) JPM# System I JPM Title Type Code* Safety Function S-1 CRDS I Dropped CEA Recovery M,S,A 1 S-2 ESFAS I Reset Inadvertent SIAS N,S,EN,A 2 S-3 PCS I PORV Switch Failure On OTCC D,S,A 3 S-4 RCS I Start RCP on Heatup D, S, L,A 4(P) S-5 CCS I Shift CAR Units D,S,A 5 S-6 AC Distribution I Tie 480 Volt Busses D,S 6 S-7 NISI RPS Calibration One Channel lnop M,S 7 S-8 CPS I Initiate Containment Purge M, A, S, L 8 In-Plant Systems© (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U) P-1 Elect Dist I Appendix R Actions in Fire Area R-1 N,E 6 P-2 MRSS I Local Operation of ADV D,E,RCA 4(S) P-3 CVCS I Local Boration lAW AOP 2551 N, E,RCA 1 

@          All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                 *Type Codes                         Actual                           Criteria for RO I SR0-11 SRO-U (A}Iternate path                                         6                                          4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank                                       5                                         :;:;91:;:;81:;:;4 (E)mergency or abnormal in-plant                         3                                          ~11~11~1 (EN)gineered safety feature                               1                       - I - I       ~1 (control room      system)

(L)ow-Power I Shutdown 2 ~11~11~1 (N)ew or (M}odified from bank include 1(A) 6 ~21~21~1 (P)revious 2 exams 0  :;:; 31:;:; 31:;:; 2 (randomly selected) (R)CA 2 ~11~11~1 (S)imulator 8

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: October 2014 Exam Level: RO SR0-1 SRO-U Operating Test No.: NRC Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF) JPM# System I JPM Title Type Code* Safety Function S-1 CRDS I Dropped CEA Recovery M,S,A 1 S-2 ESFAS I Reset Inadvertent SIAS N,S,EN,A 2 S-3 PCS I PORV Switch Failure On OTCC D,S,A 3 S-4 RCS I Start RCP on Heatup D, S, L,A 4(P) S-5 CCS I Shift CAR Units D,S,A 5 S-7 NISI RPS Calibration One Channellnop M,S 7 S-8 CPS I Initiate Containment Purge M, A, S, L 8 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U) P-1 Elect Dist I Appendix R Actions in Fire Area R-1 N,E 6 P-2 MRSS I Local Operation of ADV D, E,RCA 4(S) P-3 CVCS I Local Boration lAW AOP 2551 N, E,RCA 1 

@          All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                *Type Codes                          Actual                          Criteria for RO I SR0-1 I SRO-U (A)Iternate path                                         6                                          4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank                                       4                                          :s;91:s;81:s;4 (E)mergency or abnormal in-plant                         6                                          ~11~11~1 (EN)gineered safety feature                              1                        - I - I        ~1   (control room system)

(L)ow-Power I Shutdown 2 ~11~11~1 (N)ew or (M)odified from bank include 1(A) 6 ~21~21~1 (P)revious 2 exams 0 :s; 3 I :s; 3 I :s; 2 (randomly selected) (R)CA 2 ~11~11~1 (S)imulator 7

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: October 2014 Exam Level: RO SR0-1 SRO-U Operating Test No.: NRC Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF) JPM# System I JPM Title Type Code* Safety Function S-1 CRDS I Dropped CEA Recovery M,S,A 1 S-2 ESFAS I Reset Inadvertent SIAS N,S,EN,A 2 S-8 CPS I Initiate Containment Purge M, A, S, L 8 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U) P-1 Elect Dist I Appendix R Actions in Fire Area R-1 N,E 6 P-2 MRSS I Local Operation of ADV D,E,RCA 4(S) 

@          All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                *Type Codes                          Actual                          Criteria for RO I SR0-11 SRO-U (A)Iternate path                                          3                                       4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank                                        1                                      ::;91::;81::;4 (E)mergency or abnormal in-plant                         5                                       :2:11:2:11:2:1 (EN)gineered safety feature                               1                       - I - I :2:1 (control room system)

(L)ow-Power I Shutdown 1 :2:11:2:11:2:1 (N)ew or (M)odified from bank include 1(A) 4 :2:21:2:21:2:1 (P)revious 2 exams 0  ::; 3 I::; 31::; 2 (randomly selected} (R}CA 1 :2:11:2:11:2:1 (S}imulator 3

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 3 Op-Test No.: NRC 2014 Examiners: Operators: SRO ATC BOP Initial Conditions: 100% Power IC, BOL, Equilibrium Xenon, 1105 ppm Boron, SGBD @40gpm per Steam Generator, 24E aligned to 24C, Channel "C" Wide Range Containment Pressure safety instrument is OOS. Winds are NE 54 o at 40 mph. Turnover: 100% power, BOL, equilibrium Xenon, 1105 ppm Boron, blend ratio: 4. 32:1.0, SGBD @ 40gpm per Steam Generator, 24E is aligned to 24C. High winds reported on Long Island Sound. Channel "C" Wide Range Containment Pressure (PI-8115) instrument is OOS. Entered TS 3.3.1.1 Action 2 for RPS Instrumentation and 3.3.2.1 Action 2 for ESAS Instrumentation 2 hours ago. Prerequisites met for SP2606D 2-CS-4.1 B Stroke and Timing_ IST. Perform 1ST at the start of this shift. Critical Tasks:

1. Manually Shutdown the reactor. The reactor must be manually tripped using the CEDM output breakers immediately (within 1 minute) when an automatic reactor trip fails and/or the manual push buttons do NOT work. (CT-1/SPTA-5)
2. The operator is required to trip all RCPS within 5 minutes of the loss of NPSH, following a Small Break LOCA (SBLOCA).

Event Malf. No. Event Event Description No. Type* N (ATC, 1 RHHS- BOP) Stroke time out of specification during Surveillance Procedure SP-(0 min) 3022 1 26060 for stroke test of Containment Spray Valve CS-4.1 B. TS (SRO) RX03B RXHS- Pressurizer Pressure Transmitter Y fails high, BOTH spray valves I (ATC, 100-2_1' open. 2 SRO) RXHS-(10 min) 100-2_3, During transient, Pressurizer Proportional Heater Group 2 breaker 02A2A5S5 TS (SRO) trips open. (EN-49779) 3 C (BOP, SW09A Service Water Pump "A" strainer high D/P (4psid and rising) (30 min) SRO) 4 (40 min) FW39A High vibration on "A" SGFP (both HP/LP bearings >3mils, <5mils) N (All) Scenario 3 1 of34

Appendix D Scenario Outline Form ES-D-1 R (SRO, 5 Rapid power reduction in preparation for "A" SGFP offline at -65% (43 min) ATC, power BOP) TU02A Turbine High Vibration results in manual scram (greater than 12 RP04A-D 6 mils sustained). Reactor Trip manual push buttons do not work and RD0202 M (All) (60 min) Automatic Reactor trip disabled (ATWS). 8 CEAs fail to insert on thru 0209 RP27B reactor trip (ATWS). Emergency Boration required. 7 RC04, (61 min) C (ATC) RX Head Vent Leak and RCS cold leg break Loop 1A (LOCA) RC03A 

  *       (N)ormal,  (R)eactivity,  (l)nstrument,  (C)omponent,  (M)ajor Target Quantitative Attributes {Per Scenario; See                                           Actual Section D.S.d)
1. Total malfunctions (5-8) 6
2. Malfunctions after EOP entry (1-2) 1
3. Abnormal events (_2-4) 3
4. Major transients (1-2) 1
5. EOPs entered/requiring_ substantive actions11-2) 1
6. EOP contingencies re_guiring substantive actions(0-21 0
7. Critical tasks {2-3) 2 Scenario 3 2 of 34

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 4 Op-Test No.: NRC 2014 Examiners: Operators: SRO ATC BOP Initial Conditions: (IC 55) 100% Power, SOL, Equilibrium Xenon, 1065 ppm Boron, SGBD @40gpm per Steam Generator, 24E aligned to 24C. Turbine Driven Auxiliary Feedwater pump is OOS. Turnover: 100% Power, SOL, Equilibrium Xenon, 1065 ppm Boron, blend ratio: 4.32:1.0, SGBD@ 40gpm per Steam Generator, 24E aligned to 24C, Turbine Driven Auxiliary Feedwater pump is OOS due to an oil issue. Critical Tasks:

1. Manually trip the turbine or close MSIVs within 1 minute following a reactor trip and failure of automatic turbine trip.
2. Isolate AFW to the affected SG #2 within 30 minutes following the generation of MSIS during an ESDE.
3. Manually start "A" HPSI pump prior to reaching pressurizer low level alarm following a failure of "A" HPSI pump to actuate and a degradation of the "C" HPSI pump.

Event No. Malf. Event Event Description No. Type* 1 I (ATC, Channel Y PZR Level transmitter, LT11 OY (selected), fails low RX04B (+10 min) SRO) (55%, 2 minute ramp). C (BOP, 2 No. 1 Turbine control valve failure. (- 20MWe drop, 20% open TC06A SRO) (+20 min) total, 1 min ramp) N (ATC) I (ATC, 3 RP09D SRO) Spurious RPS low flow trip Channel "D" (+35 min) TS (SRO) C (BOP, 4 SG01A SRO), No. 1 Steam Generator tube leak (75 gpd and rising more than 15 (+40 min) gpd/min - 0.12 gpm ) TS (SRO) Scenario 4 1 of 30

Appendix D Scenario Outline Form ES-D-1 5 R (All) Rapid power reduction for Steam Generator Tube Leak (+40 min) 6 M (ATC, No.1 SGTR exceeds charging pump capacity. Reactor trip SG02A (+55 min) SRO) required. (200 gpm) 7 TC10H C (BOP) Turbine fails to trip on reactor trip (+55 min) 8 C (BOP, Excessive Steam Demand Event inside containment on #2 Steam MS01B (+57 min) SRO) Generator 9 ES031 C (ATC, "A" HPSI pump fails to start on SIAS. "C" HPSI pump is degraded (+60 min) SI05C SRO) (50%) 

  *       (N)ormal,  (R)eactivity,  (I )nstrum ent,  (C)omponent,  (M)ajor Target Quantitative Attributes (Per Scenario; See                                            Actual Section D.S.d)
1. Total malfunctions {_5-8) 8
2. Malfunctions after EOP entry (1-2j 2
3. Abnormal events (2-4) 3
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks _{_2-3)_ 3 Scenario 4 2 of 30}}
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