ML12111A198

Draft - Outlines (Folder 2)

ML12111A198
Person / Time
Site:	Beaver Valley
Issue date:	01/17/2012
From:	Rudolph W FirstEnergy Nuclear Operating Co
To:	David Silk Operations Branch I
Jackson D
Shared Package
ML113320121	List: IR 05000334/2012301 ML11334A008 ML120900525 ML12111A189 ML12111A195 ML12111A198 ML12111A204 ML12111A212 ML12111A219 ML12111A222 ML12111A234 ML12111A239 ML12180A418 ML12180A443
References
TAC U01846
Download: ML12111A198 (32)

Text

Note:

1. Ensure that at least two topics from every applicable KIA category are s~lmpled within each tier of the RO and SRO only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals* in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site,-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

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

5. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

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

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is samph~d 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 ~~ (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 KlAs that are linked to 10 CFR 55.43.

NUREG-1021. Revision 9 Supplement 1 RO Page 1 of 13 FENoe Facsimile Rev. 1

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

~======================~

E/APE # 1 Name I Safety Function KIA Topic(s) IR #

000007 Reactor Trip - Stabilization EA2 Ability to dl~termine or interpret the following as 4.2 Recovery 11 they apply to a reactor trip:

[Question 1] EA2.03 Reactor trip breaker position.

(CFR 41.7/45.:5/45.6) 000008 Pressurizer Vapor Space Accident 1 AK2 Knowledge! of the interrelations between the 2.7* 1 3 Pressurizer Vapor Space Accident and the

[Question 2] following:

AK2.01 Valves.

(CFR 41.7 I 45.'7) 000009 Small Break LOCA I 3 EK2 Knowledge! of the interrelations between the 3.0 1 small break LOCA and the following:

[Question 3]

EK2.03 S/Gs.

(CFR 41.7 145.'7) 000011 Large Break LOCA / 3 EA2 Ability to dl=termine or interpret the following as 4.5

[Question 4] they apply to a Large Break LOCA:

EA2.10 Verification of adequate core cooling.

(CFR 43.5 145.13) 000022 Loss of Reactor Coolant Makeup I AA2 Ability to determine and interpret the following 2.9 2 as they apply to the Loss of Reactor Coolant

[Question 5] Makeup:

AA2.04 How long PZR level can be maintained within limits.

(CFR: 43.5/45,13) 000025 Loss of RHR System 14 AK1 Knowledge! of the operational implications of 3.9

[Question 6] the following concepts as they apply to Loss of Residual Heat Removal System:

AK1.01 Loss of RHRS during all modes of operation.

(CFR: 41.8/41,10/45.3) 000026 Loss of Component Cooling Water / AA1 Ability to operate andlor monitor the following 3.2 8 as they apply to the Loss of Component Cooling

[Question 7] Water:

AA 1.02 Loads c,n the CCWS in the control room.

(CFR 41.7/45,15 145.6) 000027 Pressurizer Pressure Control AK1 Knowledge* of the operational implications of 2.8 1 System Malfunction 1 3 the following concepts as they apply to Pressurizer

[Question 8] Pressure Control Malfunctions:

AK1.02 Expansion of liquids as temperature rises.

(CFR 41.8/41.'10/45.3) 000029 ATWS 11 EK3 Knowledge of the reasons for the following 4.4 1

[Question 9] responses as they apply to the A TWS:

EK3.12 Actions contained in EOP for ATWS.

(CFR 41.5 /41.'10/45.6/45.13)

NUREG-1021, Revision 9 Supplement 1 RO Page 2 of 13 FENOC Facsimile Rev. 1

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

~===-==================~~~=F=

ElAPE # I Name I Safety Function KKK KiA Topic(s) IR #

123 000038 Steam Generator Tube Rupture I 3 x EK1 KnowledgE~ of the operational implications of 3.2

[Question 10] the following concepts as they apply to the SGTR:

EK1.02 Leak rate vs. pressure drop.

(CFR 41.8/41/10 145.3) 000040 Steam Line Rupture - Excessive AA1 Ability to Ol)erate and I or monitor the following 4.5 1 Heat Transfer I 4 as they apply to the Steam Line Rupture:

[Question 11] AA1.02 Feedwclter isolation.

(CFR 41.7 145.:5 145.6) 000054 Loss of Main Feedwater /4 2.2.44 Ability to interpret control room indications to 4.2 1

[Question 12] verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR 41.5/435145.12) 000055 Station Blackout 16 x EK3 Knowledge! of the reasons for the following 4.3 1

[Question 13] responses as they apply to the Station Blackout:

EK3.02 Actions contained in EOP for loss of offsite and onsite powE~r.

(CFR 41.5/41.10 145.6/45.13) 000056 Loss of Off-site Power 16 x AK3 Knowledge! of the reasons for the following 3.5

[Question 14] responses as they apply to the Loss of Offsite Power:

AK3.01 Order and time to initiation of power for the load sequencer .

(CFR 41.5/41.10145.6/45.13) 000058 Loss of DC Power 16 2.4.47 Ability to diagnose and recognize trends in 4.2 1

[Question 15] an accurate ancl timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 /4:~.5/45.12) 000062 Loss of Nuclear Service Water I 4 2.4.4 Ability to r.ecognize abnormal indications for 4.5 1

[Question 16] system operating parameters that are entry conditions for emergency and abnormal operating procedures.

(CFR: 41.10/4:3.2 145.6) 000077 Generator Voltage and Electric Grid x AK2 Knowledge of the interrelations between 3.9 Disturbances 16 Generator Voltage and Electric Grid Disturbances

[Question 17] and the following:

AK2.06 Reactor Power.

(CFR: 41.4/41.5/41.7/41.10/45.8)

NUREG-1021 , Revision 9 Supplement 1 RO Page 3 of 13 FENoe Facsimile Rev. 1

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

~======================9=9=9=~

E/APE # I Name 1 Safety Function K KIA Topic(s) IR #

1 WIE04 LOCA Outside Containment 13 EA 1 Ability to operate and lor monitor the following 3.6

[Question 18] as they apply to the (LOCA Outside Containment):

EA1.2 Operatin!~ behavior characteristics of the facility.

(CFR: 41.7/45.5/45.6)

KIA Category Point Totals: 3 3 3 3 3 3 Group Point Tolal:

NUREG-1021. Revision 9 Supplement 1 RO Page 4 of 13 FENoe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(RO) 1F=======================9F9F~~

ElAPE # 1 Name 1 Safety Function KIA Topic(s) IR #

000028 Pressurizer Level Malfunction 1 2 AK2 Knowledge of the interrelations between the 2.6 Pressurizer Level Control Malfunctions and the

[Question 19] following:

AK2.02 Sensors and detectors.

(CFR:41.7/45.7) 000051 Loss of Condenser Vacuum 12 2.1.20 Ability to interpret and execute procedure 4.6 1 steps.

[Question 20]

(CFR: 41.10 14:3.5/45.12) 000061 ARM System Alarms 17 AK 1 Knowledge of the operational implications of the 2.5*

following concepts as they apply to Area Radiation

[Question 21] Monitoring (ARM) System Alarms:

AK1.01 Detector limitations.

(CFR 41.B141.'1 0 I 45.3) 000067 Plant Fire On-site 19 AK1 Knowledge of the operational implications of the 3.1 1 following concepts as they apply to Plant Fire on

[Question 22] site:

AK1.02 Fire fighting.

(CFR: 41.BI41.10 145.3) 000068 Control Room Evacuation 1 B AK3 Knowledge of the reasons for the following 3.9 1 responses as they apply to the Control Room

[Question 23] Evacuation:

AK3.10 Maintenance of PZR level, using pumps and heaters.

{CFR: 41.5/41.10 145.6/45.13}

WIEOB .RCS Overcooling - PTS 14 EA 1 Ability to operate and 1 or monitor the following 3.8 1 as they apply to the (Pressurized Thermal Shock)

[Question 24]

EA1.1 ComponEmts and functions of control and safety systems, including instrumentation, signals, interlocks, failun~ modes, and automatic and manual features.

(CFR: 41.7 145.5/45.6)

W/E10 Natural Circulation with Steam Void EK2 Knowledge of the interrelations between the 3.3 in Vessel withlwithout RVLlS 14 (Natural Circulation with Steam Void in Vessel with/without RVLlS) and the following:

[Question 25J EK2.1 ComponElnts and functions of control and safety systems, including instrumentation, signals, interlocks, failun~ modes, and automatic and manual features.

(CFR: 41.7/45.7)

W/E14 High Containment Pressure 15 EA2 Ability to dEltermine and interpret the following 3.3 as they apply to the (High Containment Pressure):

[Question 26]

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5145.13)

NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 FENoe Facsimile Rev. 1

ES-401 . PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(RO) Continued IF===~~~~=============F=F=F=F=

E1APE # I Name I Safety Function K K KIA Topic(s) IR #

1 2 W/E15 Containment Flooding I 5 EA1 Ability to operate and I or monitor the following 2.8 as they apply to the (Containment Flooding):

[Question 27]

EA 1.3 Desired operating results during abnormal and emergency situations.

(CFR: 41.7 I 45.5 145.6)

Group Point Total:

NUREG-1021 , Revision 9 Supplement 1 RO Page 6 of 13 FENoe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - TiE~r 2/Group 1 (RO)

System # / Name K K K K

~

K A

~ ~~ A KIA Topic(s) IR #

,I 1 2 3 4 6 1 3

= 1

~

003 Reactor Coolant Pump X K5 Knowledge of the operational implications 3.2 1 of the following concepts as they apply to the

[Question 28] RCPS:

K5.04 Effects of RCP shutdown on secondary

~~ parameters, such as steam pressure, steam J~fi~ flow, and feed flow.

yJ,. (CFR: 41.5/45.7) 004 Chemical and Volume Control X

~t~ K2 Knowledge of bus power supplies to the following: 2.6* 1 [Question 29] ~;!~'i!:' K2.06 C()ntrol instrumentation. I~~ :j~i ':'. (CFR: 41.7) 005 Residual Heat Removal li~t X!: A4 Ability to manually operate and/or monitor 2.S* 1 I~~  ::"i~ in the control room: [Question 30] A4.03 RHR temperature, PZR heaters and 006 Emergency Core Cooling X I:i~, 1~'~! I,,~~ flow, andl nitrogen. (CFR: 41.7/45.5 to 45.S) K6 Knowledge of the effect of a loss or 2.8 1 malfunctilon on the following will have on the [Question 31] I}N!' I:::*~' ECCS: I:";: I~~ K6.13 Pumps. I(;l~ (CFR: 41.7/45.7) J Emergency Core Cooling I~, I~( 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry 4.5 1 I~~ [Question 32]

                                                      ~j level conditions for emergency and abnormal operatin!j procedures.
                                                      .~~~.:    I;\~~      (CFR: 41.10/43.2 /45.6)

I~ 007 Pressurizer Relief/Quench Tank X r~i\ K5 Knowledge of the operational implications of the following concepts as they apply to the 3.1 1 [Question 33] i" I~J'~, PRTS: K5.02 Method of forming a steam bubble in the PZR. j~ "i;;. (CFR: 41.5/45.7) I"~':'" OOS Component Cooling Water X A3 Ability to monitor automatic operation of the 3.6* 1 [Question 34] Ifi CCWS, including: A3.0S Automatic actions associated with the I~t ",'j::i~: CCWS that occur as a result of a safety injection signal. 1/ ." ..

                                                                 ,~,>,      (CFR: 41.7/45.5)

I 010 Pressurizer Pressure X K6 Knowledge of the effect of a loss or 2.7 1 Control malfuncbon of the following will have on the PZR pcs: [Question 35] i:~~~~ K6.01 Pressure detection systems.

                                                       ~:R H.:,                   (CFR: 41.7/45.7)

NUREG-1021, Revision 9 Supplement 1 RO Page 7 of 13 FENoe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - TiE~r 2/Group 1(RO) Continued System # 1 Name K KIA Topic(s) 1 010 Pressurizer Pressure K5 Knowledge of the operational implications 3. Control of the following concepts as they apply to the PZR pcs: [Question 36] K5.01 DE~termining of condition of fluid in PZR. using stEfam tables. (CFR: 41.5/45.7) 012 Reactor Protection K4 Knowledge of RPS design feature(s) and/or 3.7 1 interlock{s) which provide for the following: [Question 37] K4.01 Trip logic when one channel OOC or in test. (CFR: 411.7) 013 Engineered Safety Features X K1 Knowledge of the physical connections 4.1 1 Actuation and/or c.ause-effect relationships between ESFAS and the following systems: [Question 38] K1.07 AFW System. (CFR: 4'1.2 to 41.9/45.7 to 45.8) 022 Containment Cooling K2 Knowledge of bus power supplies to the 3.0* foliowin£l: [Question 391 K2.01 Containment cooling fans. (CFR: 4'1.7)

   , Containment Spray                                  A2 Ability to (a) predict the impacts of the        3.9 foliowin~1  malfunctions or operations on the

[Question 40] CSS; and (b) based on those predictions. use procedures to correct. control. or mitigate the conseql;lences of those malfunctions or operations: A2.04 Failure of spray pump. (CFR: 41.5/43.5/45.3/45.13) 026 Containment Spray 2.2.39 Knowledge of less than or equal to one 3.9 1 hour Technical Specifications for a system. [Question 41] (CFR: 41.7/41.10/43.2/45.13) 039 Main and Reheat Steam K4 Knowledge of MRSS design feature(s) 3.4 and/or interlock(s) which provide for the [Question 42] followinll: K4.07 Reactor building isolation. (CFR: 41.7) 059 Main Feedwater K3 Knowledge of the effect that a loss or 3.6 malfunction of the MFW system will have on [Question 43] the following: K3.02 AFW System. (CFR: 41.7/45.6) 061 Auxiliary/Emergency K4 Knowledge of AFW design feature(s) 2.7 Ceedwater and/or interlock(s) which provide for the followin!~:

~.Juestion  44]

K4.08 AFW Recirculation. (CFR: 41.7) NUREG-1021. Revision 9 Supplement 1 RO Page 8 of 13 FENOe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

• TiE!r 2/Group 1(RO) Continued System # I Name KIA Topic(s) IR #

062 AC Electrical Distribution A 1 AbiliW to predict and/or monitor changes in 3.4 parametors (to prevent exceeding design [Question 45] limits) associated with operating the AC Distribution System controls including: A1.01 Si!~nificance of D/G load limits. (CFR: 41.5/45.5) 063 DC Electrical Distribution A 1 Ability to predict and/or monitor changes in 2.5 1 parametE~rs associated with operating the DC [Question 46] electrical system controls including: A 1.01 Battery capacity as it is affected by discharge rate. (CFR: 41 .5 I 45.5) 063 DC Electrical Distribution 2.4.11 Knowledge of abnormal condition 4.0 1 procedures. [Question 47] (CFR: 41.10/43.5/45.13) 064 Emergency Diesel A2 Ability to (a) predict the impacts of the 2.7 Generator following malfunctions or operations on the EDIG system; and (b) based on those [Question 48] predictions. use procedures to correct. contrOl. or mitigate the consequences of those malfunctions or operations: A2.0S CIJnsequences of opening/closing breaker between buses (VARS. out-ot-phase. voltage). (CFR: 4'1.5 / 43.5 / 45.3/45,13) 073 Process Radiation K3 Knowledge of the effect that a loss or 3.6 Monitoring malfunction of the PRM system will have on the following: [Question 49] K3.01 Radioactive effluent releases. (CFR: 4'1.7/45.6) 076 Service Water A2 Ability to (a) predict the impacts of the 3.5* followinO malfunctions or operations on the [Question 50] SWS sy:stem; and (b) based on those predictions. use procedures to correct. control, or mitig~lte the consequences of those malfunctions or operations: A2.01 Loss of SWS. (CFR: 41.5/43.5/45.3/45.13) 076 Service Water A4 Ability to manually operate and/or monitor 3.5* 1 in the cCintrol room: [Question 51] A4.04 Emergency heat loads. (CFR: 41.7/45.5 to 45.S) NUREG-1021. Revision 9 Supplement 1 RO Page 9 of 13 FENoe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - TiElr 2/Group 1(RO) Continued

                                   ==;==;;==;==

System # 1 Name KiA Topic(s) IR # 078 Instrument Air K1 Knowledge of the physical connections 2.7* andlor c~luse-effect relationships between lAS [Question 52] and the following systems: K1.02 Service Air. (CFR: 41.2 to 41.9/45.7 to 45.8) 078 Instrument Air A4 Ability to manually operate andlor monitor 3.1 1 in the control room: [Question 53] A4.01 Pressure gauges. (CFR: 41.7/45.5 to 45.8) 103 Containment K3 Knowledge of the effect that a loss or 3.8 1 malfunction of the containment system will [Question 54] have on the following: K3.02 LOlss of containment integrity under normal conditions. (CFR: 41.7 1 45.6) 103 Containment A3 Ability to monitor automatic operation of the 3.9 1 containment system, including: [Question 55] A3.01 Containment isolation. (CFR: 41.7/45.5)

   . Category Point Totals:                                    Group Point Total:                                      28 NUREG-1021. Revision 9 Supplement 1          RO Page 10 of 13                                  FENoe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401*2 Plant Systems - TiE~r 2/Group 2(RO) System # 1 Name K K K K KIA Topic(s) IR # 1 2 3 4 015 Nuclear Instrumentation K5 Knowledge of the operational implications of the following concepts as they apply to the NIS: [Question 56] KS.04 Falctors affecting accuracy and reliability of calorimetric calibrations. (CFR: 41.5 1 4S.7) 016 Non-nuclear X K4 Knowledge of NNIS design feature(s) andlor 2.8* 1 Instrumentation interlock(s) which provide for the following: [Question 57] K4.01 RE!ading of NNIS channel values outside control room. (CFR: 41.7) 017 In-Core Temperature K6 Knowledge of the effect of a loss or 2.7 1 Monitor System (lTM) malfunction of the ITM system components: [Question 58] K6.01 Sensors and detectors. (CFR: 41.7/45.7) 2.4.9 Knowledge of low power/shutdown 3.8 [Question 59] implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. (CFR: 41.10 /43.5/4S.13) 045 Main Turbine Generator A 1 Ability to predict and/or monitor changes in 3.8 parameb~rs (to prevent exceeding design limits)

~"lJestion  60]                                                associab~d with MT/G system controls including:

A 1.05 Expected response of primary plant parameters (temperature and pressure) following TlG trip. (CFR: 41.5/45.5) 055 Condenser Air Removal X K1 Knowledge of the physical connections 2.6 and/or cause-effect relationships between the [Question 61] CARS and the following systems: K1.06 PHM system. (CFR: 41.2 to 41.9/45.7 to 45.8) 068 Liquid Radwaste A3 Ability to monitor automatic operation of the 3.6 1 Liquid Radwaste system including: [Question 62] A3.02 Automatic isolation. (CFR: 41.7/45.5) 071 Waste Gas Disposal A2 Abilitll to (a) predict the impacts of the 2.S 1 following malfunctions or operations on the [Question 63] Waste Gas Disposal System; and (b) based on those on those predictions, use procedures to correct, Gontrol, or mitigate the consequences of those malfunctions or operations: A2.08 MI:!teorological changes. (CFR: 41.5/43.5/45.3/45.13) NUREG-1021 , Revision 9 Supplement 1 RO Page 11 of 13 FENoe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - TiE!r 21Group 2(RO) Continued 1F===================~~r=r=T=~~= System # / Name KiA Topic(s) IR # 075 Circulating Water K2 Knowledge of bus power supplies to the 2.6* following: [Question 64] K2.03 Emergency/essential SWS pumps. (CFR: 41.7) 086 Fire Protection A4 Ability to manually operate and/or monitor 3.3 1 in the control room: [Question 65] A4.01 Fire water pumps. (CFR: 41.7/45.5 to 45.8) lte!Jorv Poi'nt Totals: Group Point Total: NUREG-1021, Revision 9 Supplement 1 RO Page 12 of 13 FENoe Facsimile Rev. 1

1 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

    .:ility: BVPS UNIT 1 RO                                        Date of Exam 4/09 thru 4/20/2012 Category                                                     Topic

1. Ability to evaluate plant performance and make operational judgments Conduct based on operating characteristics, reactor behavior, and instrument of Operations interpretation.

(CFR: 41.5/43.5/45.12/45.13) [Question 66] use plant computers to evaluate system or component status .

                                       .10 1 45.12) [Question 67]

2.1.38 Knowledge of the stations requirements for verbal communilcations when implementing procedures. (CFR: 41.10/45.13) [Question 68] I Subtotal

2. 2.2.44 Ability to interpret control room indications to verify the status and Equipment operation of a system and understand how operator actions and Control directives affect plant and system conditions.

(CFR: 41.5 143.5 /45.12) [Question 69] 2.2.43 Knowledge of the process to track inoperable alarms. (CFR: 41.10/43.5/45.13) [Question 70] Subtotal

3. I 2.3.4 Knowledge of radiation exposure limits under normal or emergency Radiation conditions.

Control . (CFR: 41.12/43.4/45.10) [Question 71]

• 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

(CFR: 41.11 /41.12 143.4 145.9) [Question 72] Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR: 41.12/45.10) [Question 73]

4. Knowledge of RO tasks performed outside the main control room during Emergency an emergency and the resultant operational effects.

Procedures/ Plan I (CFR: 41.10/43.5/45.13) [Question 74] Ability to perform without references to procedures those aGtions that require immediate operation of system components and controls. (CFR: 41.10/43.2 145.6) [Question 75] Subtotal

  .er 3 Point Total NUREG-1021 , Revision 9 Supplement 1                      RO Page 13 of 13                           FENoe FaCSimile Rev. 1

Note:

1. Ensure that at least two topics from every applicable KiA category are s~lmpled 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 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 cHtegories.

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 I::S-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is samplE~d 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 ~~ (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 KlAs that are linked to 10 CFR 55.43.

NUREG-1021 , Revision 9 Supplement 1 SRO Page 1 of 6 FENoe Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(SRO) ~====================r9~= E/APE # I Name I Safety Function K K KIA Topic(s) IR # 1 2 000015117 RCP Malfunctions 14 AA2 Ability to determine and interpret the following 2.9 [Question 76] as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): AA2.07 Calculation of expected values of flow in the loop with RCP secured. (CFR: 43.5 ! 45.13) 000057 Loss of Vital AC Inst. Bus 16 2.2.36 Ability to analyze the effect of maintenance 4.2 [Question 77] activities, such ciS degraded power sources, on the status of limiting conditions for operations. (CFR 41.10/43.2 145.13) 000065 Loss of Instrument Air I 8 AA2 Ability to dE~termine and interpret the following 2.9 [Question 78] as they apply to the Loss of Instrument Air: AA2.03 Location and isolation of leaks. (CFR: 43.51 45.13) W/E05 Inadequate Heat Transfer - Loss of EA2 Ability to determine and interpret the following 4.3 Secondary Heat Sink 14 as they apply to the (Loss of Secondary Heat Sink) [Question 79] EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendmenls. (CFR: 43.51 45.13)

\JII/E11 Loss of Emergency Coolant Recirc I                     2.1.20 Ability to interpret and execute procedure          4.6  1 steps.

[Question 80] (CFR: 41.10 14~1.5/45.12) WlE12 Steam Line Rupture - Excessive 2.1.7 Ability to evaluate plant performance and make 4.7 Heat Transfer 14 operational judgments based on operating [Question 81] characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5/43.5/45.12/45.13) KIA Category Point Totals: Group Point Total: 6 NUREG-1021 , Revision 9 Supplement 1 SRO Page 2 of 6 FENoe Facsimile Rev.1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions* Tier 1/Group 2(SRO) I~==================--======T=~~=F= E/APE # I Name 1 Safety Function KIA Topic{s) IR 000001 Continuous Rod Withdrawal 1 1 2.2.44 Ability to interpret control room indications to 4.4 verify the status and operation of a system, and [Question 82] understand how operator actions and directives affect plant and system conditions. (CFR: 41.5/43.5 145.12) 000005 Inoperable I Stuck Control Rod 11 AA2 Ability to dE!termine and interpret the following 4.4 as they apply to the Inoperable 1 Stuck Control Rod: [Question 83] AA2.03 Required actions if more than one rod is stuck or inoperable. (CFR: 43.5/45.13) 000036 Fuel Handling Accident 1 8 AA2 Ability to dotermine and interpret the following 4.1 as they apply to the Fuel Handling Incidents: [Question 84] AA2.02 Occurrence of a fuel handling incident. (CFR: 43.5/45.13) W/E06 Inadequate Core Cooling 14 2.4.18 Knowled!~e of the specific bases for EOPs. 4.0 1 [Question 85] (CFR: 41.10 14::U 145.13) KIA Category Point Totals: Group Point Total: 4 NUREG-1021 , Revision 9 Supplement 1 SRO Page 3 of 6 FENoe Facsimile Rev.1

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

                                   ===r===;====r===r==

System # 1 Name KlA Topic(s) IR # 005 Residual Heat Removal A2 Ability to (a) predict the impacts of the 2.9 followin!;1 malfunctions or operations on the [Question 86] RHRS; ,md (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operatiol1s: A2.04 RHR valve malfunction. (CFR: 4'1.5/43.5/45.3/45.13) 006 Emergency Core Cooling 2.2.22 Knowledge of limiting conditions for 4.7 operatiol1s and safety limits. [Question 87] (CFR: 4'1.5/43.2/45.2) 008 Component Cooling Water A2 Ability to (a) predict the impacts of the 3.6 followin£1 malfunctions or operations on the [Question 88] CCWS; ;and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: A2.01 Loss of CCW pump. (CFR: 4'1.5/43.5/45.3/45.13) 059 Main Feedwater 2.4.8 Knowledge of how abnormal operating 4.5 procedures are used in conjunction with EOPs. [Question 89] (CFR: 4'1.10 1 43.5 145.13)

\J i J Process Radiation                                               A2 Ability to (a) predict the impacts of the        2.9*

Monitoring followin~1 malfunctions or operations on the PRM system; and (b) based on those [Question 90] predictions, use procedures to correct, control, or mitigElte the consequences of those malfunctions or operations: A2.01 Erratic or failed power supply. (CFR: 4'1.5/43.5/45.3/45.13) int Total: 5 NUREG-1021, Revision 9 Supplement 1 SRO Page 4 of 6 FENoe Facsimile Rev.1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2(SRO) System # I Name KKK K KIA Topic(s) 3 4 5 6 IR # 011 Pressurizer Level Control A2 Ability' to (a) predict the impacts of the 3.7 1 following malfunctions or operations on the PZR [Question 91] LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the conseqUEmces of those malfunctions or operations: A2.05 Loss of PZR heaters. (CFR: 41.5/43.5/45.3/45.13) 014 Rod Position Indication A2 Ability to (a) predict the impacts of the 4.1 1 following malfunctions or operations on the [Question 92] RPIS and (b) based on those predictions, use procedures to correct, control, or mitigate the conseqUl:mces of those malfunctions or operations: 034 Fuel Handling Equipment 2.4.9 Knowledge of low power/shutdown 4.2 implications in accident (e.g., loss of coolant [Question 93] accident or loss of residual heat removal) mitigation strategies. (CFR: 41.10/43.5/45.13) KIA Category Point Totals: Group Point Total: 3 o NUREG-1021, Revision 9 Supplement 1 SRO Page 5 of 6 FENoe Facsimile Rev.1

II t:;::; 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401*3 Facility: BVPS UNIT 1 SRO Date of Exam 4/09 thru 4/20/2012 Category KJA# Topic

1. Ability to evaluate plant performance and make operational Conduct 2.1.7 judgments based on operating characteristics, reactt)r behavior, of Operations and instrument interpretation.

(CFR: 41.5/43.5145.12/45.13) [Question 94] 2.1.36 Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10/43.6/45.7) [Question 95] I SLlbtotal

2. Ability to determine the expected plant configuration using design Equipment 2.2.15 and configuration control documentation, such as drawings, line Control ups, tagouts, etc.

(CFR: 41.10/43.3/45.13) [Question 96] 2.2.40 Ability to apply technical specifications for a system. (CFR: 41.10/43.2 143.5/45.3) [Question 97) SUbtotal

3. Knowledge of radiological safety procedures pertaining to licensed Radiation 2.3.13 operator duties, such as response to radiation monitor alarms, Control containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12/43.4/45.9145.10) [Question 981 Subtotal

4. Knowledge of how abnormal operating procedures are used in Emergency 2.4.8 conjunction with EOP's.

Proceduresl Plan (CFR: 41.10/43.5/45.13) [Question 99] 2.4.44 Knowledge of emergency plan protective action recc,mmendations. (CFR: 41.10/41.12/43.5/45.11) [Question 1001 Subtotal Tier 3 Point Total NUREG*1021 , Revision 9 Supplement 1 SRO Page 6 of 6 FENoe Facsimile Rev.1

ES-401 Record 0 f R* eJec te d KIAs Form ES-4014 I Facility: BVPS UNIT 1 Date of Exam 4/9 thru 4/20 2012 Opl~rating Test No.: 1LOT8 NRC II er I Randomly Reason fc)r Rejection l:jroup Selected KIA RO OUTLINE 1/1 026 AA1.03 SWS backup to CCWS is not applicable at BVPS. 026AA1.02 reselected for Question #7. 1/1 027 AK1.01 Definition of saturation temperature is fUindamental knowledge. Unable to construct a discriminatory question. Res,elected based on 12/19 discussion with Lead Examiner. 027 AK1.02 reselected for Question # 8. 1/1 029 EK3.02 Starting specific charging pumps is not applicable to an A TWS at BVPS. 029 EK3.12 reselected for Question # 9. 1/1 040AA1.22 Load sequencer status lights are not applicable to BVPS. 040 AA1.02 reselected for Question # 11. 1/1 0542.2.1 *ES-40'1 D.1.b requires exclusion of generic KlAs for Tier 1 & 2. These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator (manually reselected from same generic group). 054 2.2.44 reselected for Question # 12. 1/1 0622.4.37

• Same as above. 2.4.1 was initially resE~lected. Since BVPS Loss of Nuclear Service Water AOP contains no immediate action steps another section 2.4 Generic KIA was manually reselected.

062 2.4.4 reselected for Question # 16. 1/2 051 2.1.43

• Same as above.

051 2.1.20 reselected for Question # 20. 2/1 004 K2.02 Make-up pumps are not applicable to the BVPS design. Author/Exam Lead believed this KIA was referencing po~sitive displacement makeup pumps. Follow-up discussion with Lead Examiner revealed this KIA is referring to Primary Make-up (PG) pumps. Unit 1 currently uses Unit 2 PG pumps. 004 K2.06 reselected for Question # 29. 2/1 0252.4.39 Ice Condensers are not applicable to the BVPS design. 006 2.4.4 reselected for Question # 32. 2/1 025 K5.02 Ice Condensers are not applicable to the BVPS design. 007 K5.02 reselected for Question # 33. 2/1 0262.2.41

• Same as above.

026 2.2.39 reselected for Question # 41. 2/1 0632.4.12

• Same as above.

063 2.4.11 reselected for Question # 47. 2/2 0292.4.26

• Same as above.

0292.4.9 reselected for Question # 59. 2/2 068 A3.01 Evaporators are no longer used for Liquid Radwaste at BVPS. 068 A3.02 reselected for Question # 62. NUREG-1021, Revision 9 Supplement 1 Page 1 of 2 FENOC Facsimile Rev. 1

3 2.1.5 KIA not an RO function at BVPS. ReselElcted based on 12/19 discussion with Lead Examiner. 2.1.7 reselected for Question # 66. 3 2.2.25 TS Bases is SRO level knowledge lAW Region II white paper on SRO ONLY questions. 2.2.44 reselected for Question # 69. 3 2.2.4 BVPS is not a multi-unit license plant. 2.2.43 reselected for Question # 70 SROOUTLINE 1/1 W/E112.1.6 *ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2. These generic KlAs were not suppressed and thereforE~ were not automatically omitted using PWROG Random Generator (manually reselected from same generic group). 2.1.20 reselected for Question # 80. 111 W/E122.1.35

• Same as above.

2.1.7 reselected for Question # 81. 1/2 01 2.2.15

• Same as above.

2.2.44 reselected for Question # 82. 1/2 05AA2.02 Jog and run rod speeds are not applicable to BVPS. AA2.03 reselected for Question # 83. 1/2 W/E162.4.50 High Containment Radiation (FR-Z.3) was deleted at BVPS Unit 1. Not SRO KIA. W/E06 2.4.18 reselected for Question # 85. 2/1 0062.2.43

• Same as above.

2.2.22 reselected for Question # 87. 2/1 008 A2.07 CCW Pump low flow auto start is not applicable to BVPS Design. A2.01 reselected for Question # 88. 2/1 0592.3.15

• Same as above.

2.4.8 reselected for Question # 89. (manually reselected from Group 4 versus 3 since radiation control not applicable to main feedwater) 3 2.1.14 KIA not an SRO function at BVPS. ResE~lected based on 12/19 discussion with Lead Examiner. 2.1.36 reselected for Question # 95. NUREG-1021. Revision 9 Supplement 1 Page 2 of2 FENOC Facsimile Rev. 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: BVPS Unit 1 Date of Examination: 4,/9 thru 4/20/2012

  -'<amination Level      RO [8]                                  Operating Test Number 1LOTS NRC Administrative                Type                                   Describe activity to be performed Topic                  Code*

(See Note) Conduct of N,R 2.1.7 (4.4) Operations Ability to evaluate plant performance and make operational judgments (ROA.1.1) based on operating characteristics, reactor behavior, and instrument interpretation. (1AD-30) Calculate The RCS Initial Void Volume and Final Void Volume. Conduct of D,R 2.1.25 (3.9) Operations Ability to interpret reference malterials, such as graphs, curves, tables, (RO A.1.2) etc. (1AD-OOS) Perform Shutdown Margin Calculation. _quipment Control N,R 2.2.37 (3.6) (RO A.2) Ability to determine operability clOd/or availability of safety related equipment. (1AD-027) Complete Surveillance of RHR Pump Radiation Control D,R 2.3.11 (3.S) (RO A.3) Ability to control radiation releases. (1AD-10) Determine GW Stora~le tank Discharge Bleed Flow Rate Emergency NOT EVALUATED Procedures/Plan It=;;=TE: All items (5 total) are required for SROs. RO applicants require only 4 itemEi unless they are retaking only the II .- topics, when all 5 are required. II "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) II (P)revious 2 exams <::. 1; randomly selected) NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: BVPS Unit 1 Date of Examination:4/9 thru 4/20/2012

  -'{amination Level         SRO IX!                                 Operating Test Number 1LOT8 NRC Administrative Topic                  Type                                Describe a(:tivity to be performed (See Note)                  Code*

Conduct of Operations N, R 2.1.43 (4.3) (SRO A.1.1) Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (1AD-019) Evaluate 1/M Plot and Determine Required Actions Conduct of Operations N,R 2.1.25 (4.2) (SRO A.1.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. (1AD-031) Review Shutdown Margin Calculation Equipment Control N,R 2.2.37 (4.6) (SRO A.2) Ability to determine operability and/or availability of safety related equipment. (1AD-026) Review/Approve Completed Surveillance of RHR Pump Radiation Control N,R 2.3.11 (4.3) (SRO A.3) Ability to control radiation releclses. (1AD-023) Review/Approve LW Discharge. Emergency N,R 2.4.40 (4.5) Procedures/Plan Knowledge of SRO responsibilities in emergency plan implementation. (SRO A.4) (1AD-015) Classify an Event (and determine PAR) II NV I t:: 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(H)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 selElcted) NUREG-1021 , Revision 9 Supplement 1 FENOC Facsimile Rev. 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 BVPS UNIT 1 ~ Date of Examination: 4/9 thru 4120/2012 I: RO ug Operating Test No.: 1LOT8 NRC Control Room Systems@'. (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function S1 - Emergency Borate RCS (1 CR-511) S,D,A,E 1 52 - Synchronize and Load #1 Emergency Diesel Generator (1CR-!524) S,N,A,EN S S3 -Isolate SI Accumulators During a LOCA (1CR-642) S,D,A,P,EN 3 S4 - Align SI Pumps for Hot/Cold Leg Recirculation (1 CR-570) I S. D.A, E 2 55 - Establish a Containment Purge to Ventilation Duct (1 CR-02S) N,S,L 8 S6 - Respond to RCP #1 Seal Failure (1 CR-040) S, M, E, L 4P 57 - Control Room Evacuation (1 CR-S09) S,D,A,E 4S S8 - Respond to an Intermediate Range Malfunction (1CR-10S) S,D,L 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for 5RO-U) Pi - Vent Charging Pump Suction Header (1 PL-057) D,R,EN 2 P2 - AMSAC System Trouble - PT Failure (PL-147) D,E 7 P3 - Transfer 120VAC Vital Power (1PL-S24) N,A,E S @ All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

                        *Type Codes                                               Criteria for RO I SRO-II SRO-U (A)lternate Path                                                                               4-6 /4-6 /2-3 (C)ontrol room (D)irect from bank                                                                            s9/s8/s4 (E)mergency or abnormal in-plant                                                              <1:1/<1:1/<1:1 (EN)gineered safety feature                                                                            - f - f::: 1 (Control room system)

(L)ow-power I Shutdown  ;::1/;::1/<1:1 (N)ew or (M)odified from bank including 1(A) <1:2/<1:2/<1:1 (P)revious 2 exams s 31 s 3 1 s 2 (randomly selected) (R)CA  ;::1/;::1/;::1 (S)imulator NUREG-1021 , Revision 9 Supplement 1 FENoe Facsimile Rev. 1

ES -301 Con t roI Room II n-PIan t S_ys tems o utrme - Form ES 301 2 Facility: BVPS UNIT 1 Date of Examination: 4/9 thru 4/20/2012 Exam Level: SRO(I) 1:&:1 Operating Test No.: 1LOT8 NRC I Control Room Systems tm (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, includin!;J 1 ESF) System I JPM Title Type Code* Safety Function S1 - Emergency Borate RCS (1CR-511) S,D,A,E 1 S2 - Synchronize and Load #1 Emergency Diesel Generator (1 CR-624) S,N,A,EN 6 S3-lso/ate SI Accumulators During a LOCA (1CR-642) S,D,A,P,EN 3 S4 - Align SI Pumps for HoUCoid Leg Recirculation (1CR-570) S,D,A,E 2 S5 - Establish a Containment Purge to Ventilation Duct (1 CR-026) N,S,L 8 S6 - Respond to RCP #1 Seal Failure (1 CR-040) S, M, E, L 4P S7 - Control Room Evacuation (1 CR-609) S,D,A,E 4S In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) P1 - Vent Charging Pump Suction Header (1 PL-057) D,R,EN 2 P2 - AMSAC System Trouble - PT Failure (PL-147) D,E 7 ~ -rig, ~ D,A,E 6

 @         All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                          *Type Codes                                              Criteria for RO 1 SRO-I 1 SRO-U (A)lternate Path                                                                             4-6 14-6 12-3 (C)ontrol room (D)irect from bank                                                                           S9/S8/S4 (E)mergency or abnormal in-plant                                                             ;::1/;::1/;::1 (EN)gineered safety feature                                                                          -I -I > 1 (Control room system)

(L)ow-power 1 Shutdown  ;::1/;::1/;::1 (N)ew or (M)odified from bank including 1(A)  ;::2/;::2/;::1 (P)revious 2 exams S3/s3/s2 (randomly selected) (R)CA  ;::1/;::1/;::1 (S)imulator NUREG-1021. Revision 9 Supplement 1 FENOC Facsimile Rev. 1

ES 301 Con t roI RoomII n-PIant Siys t ems ou trme Form ES 301 2 - ~VPSUNIT1 Date of Examination: 4/9 thru 4/20/2012 _ev'e!: SRO(U) [&l Operating Test No.: 1LOT8 NRC II Control Room Systems~ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System 1 J PM Title Type Code* Safety Function S1 - Emergency Borate RCS (1CR-511) S,D,A,E 1 S3 -Isolate SI Accumulators During a LoeA (1CR-642) S,D,A,P,EN 3 S5 - Establish a Containment Purge to Ventilation Duct (1 CR-026) N,S,L 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) Pi - Vent Charging Pump Suction Header (1 PL-057) D,R,EN 2 P3 - Transfer 120VAC Vital Power (1PL-523) D,A,E 6

   @          All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                            *Type Codes                                                Criteria for RO / SRO-I/ SRO-U (A)lternate Path                                                                                4-6/4-6 12-3 (C)ontrol room (D)irect from bank                                                                             ::;;9/::;;8/::;;4 (E)mergency or abnormal in-plant                                                               ~1/~1/~1 (EN)gineered safety feature                                                                             / .::: 1 (Control room system)

(L)ow-power / Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams s, 3/::;; 3/::;;2 (randomly selected) (R)CA ~1/~1/~1 II (S)imulator I NUREG-1021 , Revision 9 Supplement 1 FENOC Facsimile Rev, 1

A~ppen d*IX D s cenarlo r

                                                    . 0 utlne II Facility:          BVPS Unit 1                   Scenario No.:2          Op Test No.:     1LOT8 NRC F.xaminers:                                             Candidates:                                  SRO ATC BOP Initial                  IC 235: 5% power, EOL, Xe increasing, CB "D" @ 115 steps, RCS boron - 664 ppm.

Conditions: Turnover: Continue power increase IA W reactivity plan and commence turbine roll. PCV-IRC-456 isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks: 1. E-3.A Isolate Ruptured S/G

2. E-3.B Establish/maintain RCS temperatllre

3. ECA-3.3.A Terminate Safety Injection Event Event Type Event Description No.

1 NIA (R) ATC Raise power (N) SRO 2 IMF PRS08E (0 0) (I) ATC, SRO PT-1RC-445 fails high, PORV's 455D & 456 open, ATC 250015 (TS) SRO required to manual{v close PORV, PCV-IRC-455D IMF PRS04B 3 IMF BST-CCW006 (C) BOP, SRO "A" CCR pump trips, Auto start failure of "B" CCR pump IMFCCW3A (TS) SRO 4 IMF MSS\ 1(00) (C) BOP, SRO Steam Dump pressure setpoint drifts low, steam dumps open in 1400 1200 response, BOP required to manually control steam dumps 5 IMF RCSIOB (0 0) (C) ATC, SRO "B" RCP high vibration will require RCP/Rx trip 10.6 TRG 6 'IMF RCS I OB (0 120) 16.460010.6' IMF RCS03A (1 120) (M) - ALL "A" SG - 450 gpm tube rupture 6 450 7 IMF MSS08A (S 0) 50 (C) BOP, SRO Steam dump, PCV -1 MS-! 06A fails at 50% following cooldown during . Crew required to isolate steam lines and control RCS temperature via atmospheric steam dumps IMF PRS09A (l 0) 0 (C) ATC, SRO pzr spray valves and remaining PORV fail to open during 8 IMF PRS09B (10) 0 depressurization in , will require transition to ECA-3.3 lOR X07I0970 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG*1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1

Appendix 0 Scenario Outline 1L8N2

 'le crew will assume the shift at 5% power with instructions to raise power in accordance with the reactivity plan and IOM-52.4.A.

After the power increase is commenced, PT-IRC-445 will fail high causing PORV 455D and 456 to open, (per turnover, 456 previously isolated with block valve closed.) the ATC will be required to manually close PORV, PCV-IRC-455D. The US will respond and give direction lAW lOM-6.4.IF, Attachment 2 and determine applicable Tech Spec actions. The "A" CCR pump will then trip due to a faulty breaker with a failure ofthe "B" to auto start. The BOP will manually start the "B"; the US will dispatch an operator to place the "c" pump in service on the "AE" 4kv bus. The US will then address Technical Specifications. When Tech Specs have been addressed, the steam dump pressure setpoint will drift low, causing the steam dumps to open and an RCS cooldown. The crew will take action to control steam dumps manually. When steam dumps are in manual control, an RCP will show signs of high vibration, the crew will respond using AOP 1.6.8, "Abnormal RCP Operation". The vibration will increase in severity to the point where the Rx and RCP must be tripped. As a result of the reactor trip a 450 gpm SGTR occurs on the "A" S/G. The crew will progress through E-O and diagnose the "A" S/G as ruptured and transition to E-3. The crew will isolate the "A" S/G and cooldown to a target temperature. Following the Cooldown to target temperature, Condenser Steam Dump valve, PCV-IMS 16A will fail at 50% open, the crew will identify the failure and isolate the mainsteam lines and stabilize Lcmperature using the "B" and "C" S/G atmospheric steam dump valves. When the crew attempts to depressurize the RCS, the spray valves will not function, nor will the PZR PORV's, 456 was previously isolated on turnover block valve will open but PORV will not, 455D was isolated per event 2, block valve will not open. 455C will fail to open via control switch, crew will then transition to ECA 3.3. The scenario is terminated when the crew establishes a normal charging flow path in ECA-3.3. Expected procedure flow path is E-O -- E-3 -- ECA-3.3. NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1

A~ppen d'IX 0 s cenano

                                                     . 0 u tl"me II Facility:           BVPS Unit 1                   Scenario No.:3            Op Test No.:      lLOT8NRC Examiners:                                               Candidates:                                    SRO ATC BOP Initial                 IC 238 (18): 100% power, MOL, Equ. XE Condiltions, CB "D" @ 225 steps, RCS boron-Conditions:             1019 ppm.

Turnover: Maintain 100% power. PCV-1 RC-456 isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A FW-P-2 Out ofservice, TS 3. 7.5, Condition B Control Rods in Manual due to sclleduled MSP .on N-44 Critical Tasks: 1. E-O.C Energize 1 AC Emergency Bus

2. E-O.D Manually actuate 1 train of Safety Injection

3. FR-H.1.A Establish feed flow to SG before Feed and Bleed is required

4. E-2.A Isolate faulted SG Event Malf. No. Event Type Event Description No.

IMF PRS08D (0 0) (I) ATC, SRO PT-IRC-444 fails high, requires ATC to close PORV and 1 2500 IS (TS) SRO manually control ReS pressure. lOR Xl21027L (12 0) (TS) SRO OCB-92 trips open, de-energizes SSST-IA 2 ON 3 IMF AUX02A (C) BOP, SRO "A" Station air compressor trips, "B" fails to auto start BOP manually starts "B" air compressor, Diesel Air compressor fails to auto start but will start locally. IMF MSS18C (0 0) (R) ATC "C" SG Fault in MSVR, causes Rx overpower, requires 4 2.5E5 3000 (N) SRO, BOP emergency power reduction. IMF CRF04BV (2 2) (C) ATC, SRO 2 Rods drop during power reduction requires manual Rx trip. 5 I Loss of 4kv busses, "A", "B" and AE occurs on Rx trip IMF CRF04BT (2 4) I 6 TRG 3 'IMF (M)ALL "C" SG Steam Break occurs on Rx trip causes Safety lnj. MSS 18C (0 0) 6E5' IMF SISIOA (C) ATC, SRO Automatic SI fails to actuate - requires manual actuation. 7 IMFSISIOB IMF EPSI1B (I 30) (C) BOP, SRO "B" train 4kv emergency bus de-energizes, #2 EDG trips while 8 IMF INH53 (0 0) loading, #1 EDG auto start inhibited, will start manually. IMF EPS04F (1 10) i 9 IMF FWMIIC (4 30) (M) ALL Loss of all Aux Feedwater flow, requires entry into FR-H.l IMF FWMIIA (0 0) (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG*1 021, Revision 9 Supplement 1 FENoe Facsimile Rev, 1

Appendix 0 Scenario Outline 1L8N3 fter taking the shift at 100% power, PT-1RC-444 will fail high causing the pzr spray valves and PORV PCV lRC-455C to open. The ATC will close the PORV and spray valves to stabilize RCS pressure. The ATC will manually control pzr pressure for the remainder of the scenario. The SRO will utilize 10M-6.4IF, Attachment 2 to address the Pressure transmitter failure. The SRO will address T,echnical Specifications for DNB and Shutdown panel instrumentation. OCB-92 will then trip open, de-energizing SSST-IA, the SRO will address Technical Specifications and direct the BOP to perform OST-1.36.7, "Offsite to Onsite Power Distribution System Breaker Alignment Verification" . The "A" station air compressor will trip with auto start failures of the "B" station air compressor and the Diesel driven air compressor. The SRO will direct activities in accordance with AOP 1.34.1, "Loss of Station Instrument Air", the BOP will manually start the "B" station air compressor. A fault will occur on the "COl S/G outside of containment upstream of the MSIV, the fault will ramp in over a 5 minute time period, RCS temperature will decrease and reactor power will increase. High temperature alarms will actuate in the main steam valve room and aux feed pump room. The crew will recognize the over power and begin an immediate power reduction in accord,mce with AOP 1.51.2, "Reactor Overpower". The A TC will insert the control rods in response to the turbine load reduction, 2 rods will drop during the rod insertion, the immediate actions of AOP 1.1.8, "Rod Inoperability", will be taken and the reactor will be

 'anually tripped due to more than 1 rod being dropped. When the reactor is tripped, the "A", "B" and "AE"
,J{V buses will become de-energized on the transfer to otIsite power.

Upon the Rx trip, the steam leak becomes a break resulting in an SI signal being initiated due to the faulted S/G. Safety Injection will not automatically actuate, requiring manual actuation to initiate SI flow. EDG - 1 will fail to auto start and is required to be started manually. The "DF" bus will be -de-energized after the transfer to offsite power following the reactor trip. EDG-2 will auto start but trip while loading, and will not be recoverable Aux Feedwater malfunctions will occur such that FW-P-3A fails completely, FW-P-3B will not have power and the turbine driven pump, FW-P-2 was OOS on turnover, and cannot be recovered due to high temperatures in the Aux feed pump room. The crew will enter E-O on the reactor trip, and then enter FR-H-l due to no auxiliary feed water being available. When the crew dispatches an operator to start up FW-P-4, the dedicated Feedwater pump will start and supply Feedwater. After Feedwater has been established, the crew will return to E-O and progress to diagnose the "e" S/G as being faulted and enter E-2 to isolate the "C" S/G. The scenario will be terminated when the crew determines transition to ES-l.l is appropriate. Expected procedure flow path is E-O ~ FR-H.l ~ E-O ~ E-2. NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1

Appendix D Scenario Outline II Facility: BVPS Unit 1 Scenario No.:4 Op Test No.: lLOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 255(10): 100% power, BOL, Equ. XE Conditions, CB "D" @ 225 steps, RCS boron Conditions: 1434 ppm. Turnover: Maintain 100% power. PCV-1 RC-456 isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks: 1. FR-S.1.C Initiate negative reactivity

2. FR-S.1.B Start Auxiliary Feedwater pumps

3. E-O.O Close cnmt isolation valves Event Malf. No. Event Type Event Description No.

IMF PRS06A (0 0) 0 (I) ATC, SRO LT -1 RC-459 fails low, letdown isolates, crew removes 1 5 (TS) SRO channel from service. N/A (N) ATC, SRO Restores letdown 2 IMF TUR15 (0 0) 78 (C)ATC,SRO Turbine valve position limiter fails low, causes - 100 mw 3 10 (TS)SRO load reduction, 1 Rod stuck at ARO position. IMF eRFl1 BR 0 IMF FWM09C (1 0) (C) BOP, SRO "C" SO Feedwater valve, FCV-1FW-498, begins oscillating, 4 250 requiring BOP to manually control level. IMF TUR03E (0 0) (C) BOP, SRO Turbine high bearing vibration requires crew to manually trip 5 15 8 the unit. IMF CRF02A (5 0) (M) ALL Reactor fails to trip from the control room, requires entry into 6 IMF CRF12A FR-S.l, ATC manually inserts control rods. IMF CRF12B IMF INH20 (C) BOP, SRO All Aux Feedwater pumps fail to automatically start, requires 7 IMF INH21 BOP to start AFW pumps. IMF INH35 IMF INH36 IMF MSS02C (4 0) (M) ALL Main steam line break downstream ofMSIV's, causes safety 8 3.5E6 20 0 injection actuation. 9 IMF INH49 (C) ATC, SRO Train "A" CIA fails to actuate along with train "B" valve IMF VLV-SEAIO (0 MOV-ICH-381 failing to automatically close, ATC must

0) 1000100 manually actuate CIA or close MOV-1CH-381.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1

Appendix 0 Scenario Outline 1L8N4 fter taking the shift at 100% power, LT -1 RC-459 will fail low, letdown will automatically isolate. The SRO will direct the ATC to remove the 459 channel from service in accordance with 10M-6.4.IF. The ATC will restore letdown using IOM-7.4.AF, "Restoring Charging and Letdown," while the SRO reviews applicable Technical Specifications for the level transmitter failure. A malfunction will then occur with the turbine valve position limiter causing a load rejection, rods will auto insert in response. Rod P-8 will be stuck at 225 steps and not insert with the rest of control bank D. At the same time, a malfunction will occur with the "C" main feed regulating valve, (FCV -1 FW-498) causing oscillations in the "C" S/G level requiring the BOP to manually stabilize and control level. The SRO will enter AOP 1.35.2, "Load Rejection," initially and then after the plant has stabilized enter AOP 1.1.8, "Rod Inoperability," and address the rod misalignment with applicable technical specifications. A main turbine bearing #5 will exhibit high vibrations, at 15 mils the ARP for A7-I04, probable cause 5 will require a unit trip. The ATC will unsuccessfully attempt to trip the reactor from BB-B and BB-A. The SRO will enter FR-S.1 with the ATC and BOP performing the lOA's. The reactor will be locally tripped 2 minutes after the crew dispatche~, an operator to locally trip the reactor. The ATC will verify reactor power is <5% after which the SRO ~will return to E-O. Additional malfunctions that occur during the ATWS condition are that all the Aux feed water pumps fail to automatically start, all can be manually started.

\ main steam line break will also occur downstream of the MSIV's, this will be isolated via automatic MSLI.

the safety injection that occurred as a result of the MSLB will fail to actuate the train "A" CIA signal, and MOV-ICH-381 (a train "B" CIA valve) will fail to automatically close. The crew will be required to isolate the containment penetration via either manually actuating Train "A" CIA or manually closing MOV-ICH-381. After returning to E-O, the SRO will determine that SI is not required. The scenario will be terminated after the crew determines that transition to ES-I.1 is appropriate. Expected procedure flow path is E-O -+ FR-S.l -+ E-O. NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1}}