ML083640082

Draft - Outlines (Folder 2) (Facility Ltr. Dtd - 10/22/08)

ML083640082
Person / Time
Site:	Beaver Valley
Issue date:	10/22/2008
From:	FirstEnergy Nuclear Operating Co
To:	David Silk Operations Branch I
Hansell S
Shared Package
ML081060562	List: IR 05000412/2008301 ML083370145 ML083400431 ML083640082 ML083640084 ML083640089 ML090120828 ML090120832 ML090120846 ML090120853 ML090230109 ML090260673 ML091760057
References
TAC U01628
Download: ML083640082 (27)

Text

ES-401 PWR Examination Outline Form ES-401-2 1I Facility: Beaver Valley Unit 2 RO I I Date of Exam Weeks of 1218 & 12/15 2008 I

3 Generic Knowledge and Abilities Category

\late:

I. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (!.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).

?. 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 + I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not appl.

at the facility should be deleted and justified: operationally important, site-specific systemsievolutions that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.

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

5. Absent a plant-specific priority, only those WAS 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.

3. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

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

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

9. For Tier 3. select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs. and point totals (#)on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

NUREG-1021, Revision 9 Supplement 1 RO Page 1 of 13 Beaver Valley Facsimile R3:v. 1

ES-401 PWR Examination Outline Form ES-401-2 I Em aenc nd Abnormal Plant Evolutions -Tier IlGroup I ( R 0 )

I1 EiAPE # / Name / Safety Function KIA Topic@)

IR 000007 (BWiEOZ&EIO; CEIE02) Reactor EK2 Knowledge of the interrelations between a 3.5 Trip - Stabilization - Recovery / 1 reactor trip and the following:

[Question I] EK2.03 Reactor trip status panel lCFR 41.7 / 45.71 000008 Pressurizer Vapor Space AK3 Knowledge of the reasons for the following 4.2 Accident / 3 responses as they apply to the Pressurizer Vapor Space Accident:

[Question 21 AK3.04 RCP tripping requirements (CFR41.5.41.10/45.6/45.13) 000009 Small Break LOCA / 3 EA1 Ability to operate and monitor the following as 4.4 they apply to a small break LOCA:

[Question 31 EA1.13 ESFAS (CFR 41.7 / 45.5 / 45.6) 000015117 RCP Malfunctions / 4 AK2 Knowledge of the interrelations between the 2.9

[Question 41 Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:

AK2.07 RCP seals (CFR 41.7 / 45.7) 2.4.11 Knowledge of abnormal condition 4.0

[ Q u e s t i o n 51 procedures.

(CFR:41.10/43.5/45.13) u d 0 2 6 Loss of Component Cooling 2.4.8 Knowledge of how abnormal operating 3.8 Water / 8 procedures are used in conjunction with EOPs.

[ Q u e s t i o n 61 (CFR:41.10/43.5/45.13) 000029 ATWS / 1 EA2 Ability to determine or interpret the following as 4.4

[Question 71 they apply to a ATWS:

EA2.01 Reactor nuclear instrumentation (CFR43.5i45.13)

EK1 r(nonr eogc of tnc operatona imp1 cat ons of 3.1 1

[Question 81 the fo lo@ny concepts as tney apply IO !he SGTR.

EK1 01 &e of steam tabes (CFR41 8 41 10 4 5 3 )

AK1 Knowledge of the operational implications of 3.2 1 Line Rupture - Excessive Heat Transfer / 4 the following concepts as they apply to Steam Line

[Question 91 Rupture:

AK1.04 Nil ductility temperature (CFR41.8 141.10 145.3)

NUREG-1021,Revision 9 Supplement 1 ROPageZaf13 Beaver Valley Facsimile R 'v 1

is-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier IlGroup l ( R 0 ) Continued EiAPE # / Name / Safety Function WA Topic@)

100055 Station Blackout / 6 EA2 Ability to determine or interpret the following as

Question 101 they apply to a Station Blackout:

EA2.02 RCS core cooling through natural zirculation cooling to S/G cooling (CFR 43.5 / 45.13) 100056 Loss of Off-site Power / 6 AA2 Ability to determine and interpret the following

[Question 111 as they apply to the Loss of Offsite Power:

AA2.88 Necessary SIG water level for natural circulation (CFR: 43.5 / 45.13) 100057 Loss of Vital AC lnst. Bus / 6 &A1 Ability to operate and / o r monitor the following

[Question 121 as they apply to the Loss of Vital AC Instrument Bus:

AAl.01 Manual inverter swapping ICFR 41.7 / 45.5 / 45.6) 300058 Loss of DC Power / 6 AK3 Knowledge of the reasons for the following

[Question 131 responses as they apply to the Loss of DC Power:

AK3.02 Actions contained in EOP for loss of DC power (CFR41.5/41.10/45.6/45.1)

'62 Loss of Nuclear Svc Water 1 4 AK3 Knowledae ._ of the reasons for the followinoI responses as they apply to the Loss of Nuclear

[Question 141 Service Water:

AK3.03 Guidance actions contained in EOP for Loss of nuclear service water fCFR41.4i41.8i45.71 000065 Loss of Instrument Air / 8 AA2 Ability to determine and interpret the following as they apply to the Loss of Instrument Air:

[Question 151 AA2.08 Failure modes of air-operated equipment ICFR: 43.5 / 45.13)

WIE04 LOCA Outside Containment / 3 EA2 Ability to determine and interpret the following as they apply to the (LOCA Outside Containment)

[ Q u e s t i o n 161 EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

ICFR: 43.5 / 45.13)

W i E l 1 Loss of Emergency Coolant EK3 Knowledge of the reasons for the following Recirc. / 4 responses as they apply to the (Loss of Emergency Coolant Recirculation)

[Question 171 EK3.3 Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

(CFR: 41.5 / 41.10 145.6 / 45.13)

NUREG-1021,Revision 9 Supplement 1 RO Page 3 of 13 Beaver Valley Facsimile Re v 1

1I ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions .Tier 1IGroup l ( R 0 ) Continued

~~~

EiAPE # / Name / Safety Function K K K A A G KIA Topic(s) IR #

2 3 1 2 x EA2 Ability to determine and interpret the following 3.4 1 Loss of Secondary Heat Sink / 4 as they apply to the (Loss of Secondary Heat Sink)

[Question 181 EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13)

KIA Category Point Totals 2 2 4 2 6 2 Group Point Total 18 NUREG-1021, Revision 9 Supplement 1 RO Page 4 of 13 Beaver Valley Facsimile Re,). 1

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

~~~

EIAPE # / Name I Safety Function KIA Topic(s) 000005 InoperableiStuck Control Rod / 1 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

[ Q u e s t i o n 191 (CFR: 41.10 I 43.5 145.3 / 45.12) 000032 Loss of Source Range NI I 7 2.2.39 Knowledge of less than or equal to one hour 39 1 Technical Specification action statements for

[ Q u e s t i o n 201 systems.

(CFR:41.7/41.10/43.2/45.13) 000037 Steam Generator Tube Leak I 3 AK3 Knowledge of the reasons for the following 25 1 responses as they apply to the Steam Generator

[Question 211 Tube Leak:

AK3.04 Use of "feed and "bleed" process.

(CFR41.5 141.10 145.6 145.131 000069 (WIE14) Loss of CTMT Integrity / 5 AA2 Ability to determine and interpret the following 37 1 as they apply to the Loss of Containment Integrity:

[Question 221 AA2.01 Loss of containment integrity (CFR: 43.5 / 45.13)

WiE02 SI Terminationi3 EK2 Knowledge of the interrelations between the (SI 3.5 Termination) and the following:

[Question 231 EK2.2 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.

(CFR: 41.7 / 45.71

~~

WIE13 Steam Generator Over-pressure I 4 EK2 Knowledge of the interrelations between the 3.0 (Steam Generator Overpressure) and the following:

[Question 241 EK2.1 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7)

WIE15 Containment Flooding 1 5 EKI Knowledge of the operational implications of the 2.7 following concepts as they apply to the (Containmenl

[Question 251 Flooding).

EK1.2 Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

(CFR:41.8/41.10/45.3)

BWIE08: WIE03 LOCA Cooldown EA2 Ability to determine and interpret the following 3.4 Depress. I 4 as they apply to the (LOCA Cooldown and Depressurization)

[Question 261 EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13)

NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 Beaver Valley Facsimile Rsw. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1IGroup Z(R0) Continued EiAPE # 1 Name 1 Safety Function I KI K I K I AI A I 1 2 3 1 2 GI WA Topic(s) I I R #

BWIEO9, CEIA13. W/E09&E10 Natural Circ X EKI Knowledge of the operational implications of the 3.3 14 following concepts as they apply to the (Natural Circulation Operations)

[ Q u e s t i o n 271 EKI .3 Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Operations).

(CFR 41 8 / 4 1 1 0 1 4 5 3 )

=

I I I I I I i WA Category Point Totals 2 2 1 0 2 2 Group PointTotal 9 NUREG-1021, Revision 9 Supplement 1 RO Page 6 of 13 Beaver Valley Facsimile R. v 1

s-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2/Group l ( R 0 )

System # / Name WA Topic(s) 303 Reactor Coolant Pump :3 Knowledge of the effect that a loss or nalfunction of the RCPS will have on the

[Question 281 dlowing:

(3.04 RPS CFR:41.7/45.6) 004 Chemical and Volume (4 Knowledge of CVCS design feature(s)

Control indior interlock(s) which provide for the ollowing:

[Question 291 (4.1 1 Temperatureipressure control in etdown line: prevent boiling, lifting reliefs, iydraulic shock, piping damage, and burst CFR: 41.7) 005 Residual Heat Removal ( 6 Knowledge of the effect of a loss or nalfunction on the following will have on the

[ Q u e s t i o n 301 IHRS:

(6.03 RHR heat exchanger CFR: 41.7 / 45.7) 006 Emergency Core Cooling <6 Knowledge of the effect of a loss or nalfunction on the following will have on the

[Question 311 zccs:

16.03 Safety Injection Pumps

'CFR: 41.7 / 45.71 006 Emergency Core Cooling 44 Ability to manually operate and/or monitor n the control room:

[ Q u e s t i o n 321 44.05 Transfer of ECCS flowpaths prior to

.ecirculation (CFR: 41.7 / 45.5 to 45.8) 007 Pressurizer ReIieflQuench K3 Knowledge of the effect that a loss or Tank malfunction of the PRTS will have on the following:

[Question 331 K3.01 Containment ICFR: 41.7 / 45.6) 008 Component Cooling Water 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the

[Question 341 appropriate control room reference material.

(CFR: 41.10 / 43.5 145.12)

~

010 Pressurizer Pressure A I Ability to predict and/or monitor changes in Control parameters (to prevent exceeding design limits) associated with operating the PZR PCS

[ Q u e s t i o n 351 controls including:

A I .06 RCS heatup and cooldown effect on pressure (CFR: 41.5 / 45.5)

NUREG-1021, Revision 9 Supplement 1 ROPage7of13 Beaver Valley Facsimile Rs?v. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant fsterns -Tier 2lGroup I ( R 0 ) Continued

~

System # / Name R 0 WA Topi+) IR 1 2 -

010 Pressurizer Pressure A3 Ability to monitor automatic operation of the 3.6 Control PZR PCS, including:

[Question 361 A3.02 PZR pressure ICFR: 41.7 / 45.51 012 Reactor Protection K4 Knowledge of RPS design feature@) and/or 3.2 interlock(s) which provide for the following:

[Question 371 K4.06 Automatic or manual enableidisable of RPS trips ICFR: 41.71

~ -

012 Reactor Protection x A I Ability to predict and/or monitor Changes in 2.9 parameters (to prevent exceeding design

[Question 38) limits) associated with operating the RPS controls including:

A I .01 Trip setpoint adjustment C F R : 41.5 / 45.51 013 Engineered Safety Features K2 Knowledge of bus power supplies to the 3.6 Actuation following:

[Question 391 K2.01 ESFASisafeguards equipment control ICFR: 41.7)

P-7 Containment Cooling A4 Ability to manually operate and/or monitor 3.6 in the control room:

. .estion 401 A4.01 CCS fans (CFR:41.7/45.5 to45.8) 026 Containment Spray K1 Knowledge of the physical connections 4.2 and/or cause-effect relationships between the

[ Q u e s t i o n 411 CSS and the following systems:

K1.O1 ECCS C F R : 41.2 to 41.9 / 45.7 to 45.81 026 Containment Spray 2.2.40 Ability to apply Technical Specifications 3.4 for a system.

[Question 421 (CFR: 41.10/43.2/43.5/45.3) 039 Main and Reheat Steam A4 Ability to manually operate and/or monitor 2.8 in the control room:

[Question 431 A4.07 Steam dump valves (CFR: 41.7 / 45.5 to 45.8) 059 Main Feedwater K4 Knowledge of MFW design feature@) 2.5 and/or interlock(s) which provide for the

[Question 441 following:

K4.08 Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch)

(CFR: 41.7)

NUREG-1021, Revision 9 Supplement 1 RO Page 8 of 13 Beaver Valley Facsimile Re 1

I ES-401 PWR Examination Outline it Systems Form ES-401-2

-Tier ZlGroup l ( R 0 ) Continued System # / Name < WA Topic(s) 1 059 Main Feedwater A2 Ability to (a) predict the impacts of the following malfunctions or operations on the

[ Q u e s t i o n 451 MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.11 Failure of feedwater control system (CFR: 41.5 / 43.5 / 45.3 / 45.13)

K2 Knowledge of bus power supplies to the Feedwater following:

[Question 461 K2.02 AFW electric drive pumps (CFR: 41.7)

A I Ability to predict andlor monitor changes in Feedwater parameters (to prevent exceeding design limits) associated with operating the AFW

[Question 471 controls including:

A1.O1 SG level (CFR: 41.5 / 45.5)

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ac

[ Q u e s t i o n 481 distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.11 Aligning standby equipment with correct emergency power source (DIG)

C F R : 41.5 / 43.5 / 45.3 / 45.13)

K1 Knowledge of the physical connections and/or cause-effect relationships between the

[Question 491 DC electrical system and the following systems:

K1.02 AC electrical system (CFR:41.2to41.9/45.7to45.8) 064 Emergency Diesel K3 Knowledge of the effect that a loss or Generator malfunction of the EDiG system will have on the following:

[ Q u e s t i o n 501 K3.02 ESFAS controlled or actuated systems (CFR: 41.7 / 45.6)

K5 Knowledge of the operational implications Monitoring as they apply to concepts as they apply to the PRM system:

[ Q u e s t i o n 511 K5.01 Radiation theory, including sources, types, units, and effects (CFR: 41.5 / 45.7)

L NUREG-1021, Revision 9 Supplement 1 RO Page 9 of 13 Beaver Valley Facsimile Rcv 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier ZlGroup l ( R 0 ) Continued System # / Name 1 1 WA Topic@)

1 076 Service Water A2 Ability to (a) predict the impacts of the following malfunctions or operations on the

[Question 521 SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

AZO1 Loss of SWS (CFR:41.5/43.5/45.3/45.13) 076 Service Water A4 Ability to manually operate andlor monitor in the control room:

[Question 531 A4.04 Emergency heat loads (CFR: 41.7 I45.5 to 45.8) 078 Instrument Air A3 Ability to monitor automatic operation of the IAS. including:

[ Q u e s t i o n 541 A3.01 Air pressure (CFR: 41.7 / 45.51

~~

103 Containment A3 Ability to monitor automatic operation of the containment system, including:

[ Q u e s t i o n 551 A3.01 Containment isolation (CFR: 41.7/45.5)

, . , Category Point Totals: Grouo Point Total:

NUREG-1021, Revision 9 Supplement 1 RO Page 10 of 13 Beaver Valley Facsimile Re., 1

ES-401 PWR Examination Outline Form ES-401-2 Plan! vstems -Tier 2lGroup 2(RO)

System # / Name / WA Topic(s) 1 IR 014 Rod Position Indication A2 Ability to (a) predict the impacts of the 3.

following malfunctions or operations on the

[ Q u e s t i o n 561 RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A 2 0 2 Loss of power to the RPIS (CFR: 41.5/43.5/45.3/45.13) 015 Nuclear Instrumentation A4 Ability to manually operate and/or monitor in 3.

the control room:

[Question 571 A4.03 Trip bypasses (CFR: 41.7 / 45.5 to 45.8) 016 Non-nuclear A4 Ability to manually operate and/or monitor in 2.'

Instrumentation the control room:

[ Q u e s t i o n 581 A4.01 NNI channel select controls (CFR: 41.7 / 45.5 to 45.8) 028 Hydrogen Recombiner and K5 Knowledge of the operational implications of 2.'

Purge Control the following concepts as they apply to the HRPS:

[Question 591 K5.03 Sources of hydrogen within containment (CFR: 41.5 / 45.7)

.n-Core Temperature A4 Ability to manually operate and/or monitor in 3,,

tv,,nitor System (ITM) the control room:

A4.02 Temperature values used to determine

[Question 601 RCSiRCP operation during inadequate core cooling (i.e.. if applicable, average of five highest values)

(CFR: 41.7 / 45.5 to 45.8) 034 Fuel Handling Equipment K4 Knowledge of design feature@) and/or 2.'

interlock@) which provide for the following:

[Question 611 K4.01 Fuel protection from binding and dropping ICFR: 41.7) 041 Steam Dumpnurbine K1 Knowledge of the Physical connections 3.:

Bypass Control and/or cause-effect relationships between the SDS and the following systems:

[Question 621 K1.05 RCS (CFR:41.2to41.9/45.7 to45.8) 056 Condensate K1 Knowledge of the physical connections and/or cause-effect relationships between the

[Question 631 Condensate System and the following systems:

K1.03 MFW (CFR: 41.2 to 41.9 / 45.7 to 45.8)

NUREG-1021,Revision 9 Supplement 1 RO Page 11 of 13 Beaver Valley Facsimile REI 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Sy! -Tier 2IGroup Z(R0) Continued il System # / Name WA Topic@)

075 Circulating Water K4 Knowledge of circulating water system design feature(s) and interlock@)which provide

[Question 641 for the following:

K4.01 Heat sink (CFR: 41.7) 086 Fire Protection A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)

[ Q u e s t i o n 651 associated with Fire Protection System operating the controls including:

Al.05 FPS lineups (CFR: 41.5 / 45.5)

KIA Category Point Totals: Group Point Total:

NUREG-1021, Revision 9 Supplement 1 RO Page 12 of 13 Beaver Valley Facsimile Rev. 1

ES 401 Generic Knowledge and Abilities Outline (Tier 3) 1 ,,ihty: Beaver Valley Unit 2 RO Date of Exam Weeks of 1218 & 12/15 2 0 0 8 I

Category KIA# Topic 1R IR 1 2 1 29 Knowledge of how to conduct system lineups, such as valves breakers, Conduct switches etc I

of Operations (CFR: 41.10/45.1 145.12) [Question 661

. ~ ~~~~~~~ ~ ~~~~~~~~

2.1.36 ' Knowledge of procedures and limitations invoived in core alterations. ' 3.0 ' 1 (CFR: 41 .IO / 43.6 / 45.7) [Question 671

~~~~~~~ ~ ~ ~ ~ ~ ~ _ _ _~~~~~ _ _ _ ~ ~

2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

Control (CFR 41 I O / 45 12 / 45 13) [Question 701

3. 2.3.12 Knowledge of radiological safety principles pertaining to licensed 3.2 Radiation operator duties, such as containment entry requirements, fuel handling Control es. access to locked high-radiation areas, aligning filters, etc.

' (CFR: 41 . I 2 / 45.9 / 45.10) [Question 711

, ~

~

~~~~~~~~ ~ ~~~~~~

2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation ~ 2.9 monitors and alarms, portable survey instruments. personnel monitoring ~

equipment. etc.

Emergency parameters that are entry-level conditions for emergency and abnormal Procedures/ operating procedures.

Plan  ! (CFR: 41.10 / 43.2 / 45.6) [Question 731

~ ~~~

~~~~~~~~ ______~ ~ ~ ~ _ _ _ _ _ _

2.4.11 Knowledge of abnormal condition procedures.

(CFR: 41 .IO / 43.5 / 45.13) [Question 741

. ~~ ~ ~~~~ ~~~~ ~~ ~~~~ ~~ ~~~ ~~~~ ~~~~~ ~

I (CFR 41 10 / 45 12) [Question 751 I

Subtotal I .i 3 Point Total NUREG-1021, Revision 9 Supplement 1 RO Page 13of 13 Beaver Valley Facsimile F ?v. 1

ES-401 PWR Examination Outline Form ES-401-2 I

1 Facility: Beaver Valley Unit 2 SRO I I Date of Exam Weeks of 12/8 & 12/15 2008 I

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. Systemslevolutions 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 systemslevolutions 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 befor, selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those WAS 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 ) WAS in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable KlAs.

8. On the following pages, enter the WA 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.

'1 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 WAS that are linked to 10 CFR 55.43.

NUREG-1021, Revision 9 Supplement 1 SRO Page 1 of 6 Beaver Valley Facsimile K'?v.l

is401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1IGroup l ( S R 0 )

EiAPE # / Name / Safety Function WA Topic@)

)00011 Large Break LOCA / 3 2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational

Question 761 effects.

(CFR: 41.10 / 43.5 /45.13)

)00015/17 RCP Malfunctions / 4 AA2 Ability to determine and interpret the following

[ Q u e s t i o n 771 as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

AA2.10 When to secure RCPs on loss of cooling or seal injection (CFR 43.5 / 45.13) 300027 Pressurizer Pressure Control AA2 Ability to determine and interpret the following System Malfunction / 3 as they apply to the Pressurizer Pressure Control

[ Q u e s t i o n 781 Malfunctions:

AA2.14 RCP injection flow (CFR: 43.5 / 45.13) 000038 Steam Generator Tube Rupture 2.4.18 Knowledge of the specific bases for (SGTR) EOPs.

[Question 791 (CFR: 41.10 /43.1/45.13) 000056 Loss of Off-site Power / 6 AA2 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:

- mestion 801 AA2.19 T-cold and T-hot indicators (wide range)

(CFR: 43.5 / 45.13)

~~

WIE04 LOCA Outside Containment / 3 EA2 Ability to determine and interpret the following as they apply to the (LOCA Outside Containment)

[ Q u e s t i o n 811 EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13)

KIA Category Point Totals: Group Point Total:

NUREG-1021, Revision 9 Supplement 1 SRO Page 2 of 6 Beaver Valley Facsimile Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Abnormal Plant Evolutions -Tier I/Group Z(SR0)

EiAPE # / Name / Safety Function G WA Topic@)

000003 Dropped Control Rod / 1 as they apply to the Dropped Control Rod:

[ Q u e s t i o n 821 AA2.01 Rod position indication to actual rod position (CFR: 43.5 / 45.13) 000059 Accidental Liquid RadWaste Rel. / X 2.4.47 Ability to diagnose and recognize trends in an 4.2 1 9 accurate and timely manner utilizing the appropriate control room reference material.

[Question 831 I (CFR: 41.10/43.5/45.12) 000067 Plant Fire on-site X 2.4.27 Knowledge of "fire in the plant" procedures

[Question 841 ICFR: 41.10/ 43.5 / 45.131 000061 ARM System Alarms / 7 AA2 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring

[Question 8-51 (ARM) System Alarms:

AA2.06 Required actions if alarm channel is out of service (CFR: 43.5 145.13)

WA Category Point Totals: G r o w Point Total:

[Qu.

NUREG-1021, Revision 9 Supplement 1 SRO Page 3 of 6 Beaver Valley Facsimile R 'v 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier ZlGroup 2(SRO)

System # / Name K K K K I G WA Topic(s)

Il 31 1 Pressurizer Level Control X 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of

[Question 911 plant operation.

(CFR:41.10/43.5/45.2/45.6) 071 Waste Gas Disposal x 2.1.20 Ability to interpret and execute procedure steps.

[Question 921 (CFR:41.10/43.5/45.12) 086 Fire Protection make operational judgments based on

[Question 931 operating characteristics, reactor behavior, and instrument interpretation.

WA Category Point Totals: Group Point Total:

NUREG-1021, Revision 9 Supplement 1 SRO Page 5 of 6 Beaver Valley Facsimile Hev.1

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

..-Ility: Beaver Vallev Unit 2 SRO Date of Exam Weeks of 12/8 & 12/15 20( I&

RO Category KIA# Tnpic I. Knowledge of individual licensed operator responsibilities 3.8 1 Conduct 2.1.4 related to shift staffing, such as medical requirements, "no-solo

)f Ooerations operation, maintenance of active license status, 10CFR55. etc. I (CFR: 41.10 / 43.2)

[ Q u e s t i o n 941

~~ ~~~~~~~~~~ ~ ~~ ~ ~~~~ ~ ~ ~ . . .

2.1.34 Knowledge of primary and secondary plant chemistry limits. 3.5 ~ 1 (CFR: 4 1 . 1 0 / 4 3 . 5 / 4 5 . 1 2 )

[ Q u e s t i o n 951 21 Knowledge of pre- and post-maintenance operability 4.1 1 Equipment requirements Control (CFR 41 1 0 1 4 3 2)

[ Q u e s t i o n 961

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2,2,37 Ability to determine operability and/or availability of safety 4.6 1 related equipment.

~ (CFR: 41.7 / 43.5 / 45.12)

[ Q u e s t i o n 971

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Subtotal 2

1

3. 2,3,15 Knowledge of radiation monitoring systems, such as fixed 31 Radiation radiation monitors and alarms, portable survey instruments, Control personnel monitoring equipment, etc.

(CFR 41 1 2 1 4 3 4 1 4 5 9 )

[ Q u e s t i o n 981 1.

Subtotal Knowledge of the operational implications of EOP warnings, 43 ,

1 1

2.4.20 Emergency cautions, and notes.

Procedures/

Plan (CFR: 41.10 / 43.5 145.13)

[ Q u e s t i o n 991

~ ~ ~~ ~~~~~~~~~~~~~~~ ~~~~~~~

2.4.35 Knowledge of local auxiliary operator tasks during an 4.0 1 emergency and the resultant operational effects.

(CFR: 4 1 . 1 0 / 4 3 . 5 / 4 5 . 1 3 )

[ Q u e s t i o n 1001 Subtotal I I

1 I

2 Tier 3 Point Total 7 NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 Beaver Valley Facsimile Rrw 1

ES-401 Record of Rejected WAS Form ES-401-4 Reason for Rejection Selected WA Beaver Valley does NOT have Ice Condensers.

1 211 I 059 K4.05 Beaver Valley does NOT have variable speed main feedwater pumps.

APE 003 AA2.04 Beaver Valley does NOT have any automatic outward rod motion. All automatic outward rod motion has b en defeated 2.1.27 WA is NOT linked to 10CFR 55.43 and IS therefore NOT suitable for SRO exam.

2.4.3 KIA is NOT linked to IOCFR 55.43 and is therefore NOT suitable for SRO exam.

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022 A2.05 Unable to construct a SRO discriminatory question for this KIA.

1 212 1 072 A2.01 Balance of exam. This would be the sixth radiation monitor question.

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BVPS Post DBA Hydrogen control equipment and associated procedures have been retired in place. If thr need arises, Post DBA Hydrogen control equipment and procedures will be directed by the Technical support 0 nter with engineering support.

At BVPS the response to containment high radiation procedure (FR-Z.3) has no actions for the operations crew other than contact the TSC. Any response to high containment radiation will be guided by ERO. This WA 1 1: 1 therefore has no discriminatory value for a written exam question.

BVPS Unit 2 Does NOT have any automatic controls on spent fuel pool cooling associated with a leaking mr ruptured fuel assembly.

061 A1 04 BVPS Unit 2 Does Not have any AFW controls on the AFW source tank (FWE'TK210) except a level c o n 01 valve that will provide makeup to the tank as level drops, Unable to construct a discriminatory written que! tion to match this KIA.

000029 2.4.1 Unable to construct a SRO discriminatory question for this WA. Knowledge of ATWS EOP entry

/I 1/2 I 000060 2.4.21 conditions and immediate actions are also RO knowledge's. (Q 79)

Unable to construct a SRO discriminatory question for this WA. Generic WA is a difficult match to accidental gas release. Too much time( 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) spent trying to construct a valid SRO discriminatwy question. (084)

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NUREG-1021 Revision 9 Supplement 1 Beaver Valley Facsimile R v I

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Beaver Valley Unit 2 Date of Examination: Weeks of 12/8 & 12/15 2008

)I famination Level RO El Operating Test Number 2LOT6 NRC Exam (1

~

Administrative Topic Describe activity to be performed I (See Note)

Type Code*

I Conduct of Operations 'lot and Evaluate 1/M Data 2.1.43 4.1

+

I Conduct of Operations Perform Daily Heat Balance 2.1.7 4.4 Equipment Control N.R Prepare Tagout of 21 B Service Water Pump 2.2.13 3.6 i 7 Radiation Control N. S

~~ ~

Respond to Radiation Monitor Alarm and complete the Radioactive Waste Discharge permit.

2.3.1 1 3.3 Emergency ProcedureslPlan NIA NIA NOTE: All items (5 total) are rc red for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required. .-

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'Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)

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

(P)revious 2 exams (5 1; randomly selected) .__

NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Beaver Vallev Unit 2 Date of Examination Weeks of 1218 8 12/15 2008 hamination Level SRO Operating Test Number 2LOT6 NRC Exam I-

~ ~ ~

Describe activity to be performed Code*

(See Note)

Conduct of Operations M, R Plot and Evaluate l / M Data and make recommendations fc, continued Rod Withdrawal 2.1.43 4.3 Conduct of Operations N, R Prepare Partial OST for Performance (2OST-6.6, PORV Isolation Valve Test and Position Check) 2.1.20 4.6 Equipment Control N, R ReviewlApprove Completed RHS Pump Surveillance 2.2.37 4.6 Radiation Control N, R Review/Approve LW Discharge Permit 2.3.1 1 4.3 Emergency N, S Evaluate EPP and complete the Initial Notification Form.

ProcedureslPlan 2.4.41 4.1 NOTE: All items (5 total) are required for SROs. RC plicants require only 4 items unless they are retaking only the administrative topics when all 5 are required

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, =

'Type Codes & Criteria (C)ontrol Room, (S)imula!or, or Class(R)oom (D)irect from bank (5 3 for ROs; 2 4 for SROs & RO retakes)

NUREG-1021. Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1

<O(U)0 Operating Test No.: -

System I JPM Title Type Code* Safe?:

I Functic m 3;:,!PI\\: >?!.'.I? (,L!2 Piitr3rv: IHo; Ei.is irmr!sfcr , 130 Y~, Po..yei-)

C. 006 A4.02 4.013.8 (Stand-alone) S , M, A 3 S3 JPM 2CR-529 Transfer To Cold Leg Recirculation (Post LOCA)

d. E05 EA1.l 4.114.0 (Stand-alone) D, S, A 4P S4 JPM 2CR-624 Establish RCS Bleed and Feed per FR-H.l (Post LOCA)

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L .

I .x ",,

1

' , 8 g 015 A3.03 3.913.9 (Paired with S8) N, S , L 7 S7 JPM 2CR-646 Perform Nuclear IR Channel Functional Test (Mode 2 - 3% RX Power) h 004 A4.04 3.213.6 (Paired with S?) S, M, A, L 2 S8 JPM 2CR-537 Batch To RWST (Mode 2 - 3% RXPower) .--

I. 013 A3.01 3.713.9 D, EN 2 P I JPM 2PL-048 Safeguards test of FWI -

1. 06 1 A2.04 3.413.8 N, R 4s P2 JPM 2PL-069 Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A) .-

k. 064 A4.01 4.014.3 E, D, A, EN 6 P3 JPM 2PL-606 Locally Start the No. l(2) Emergency Diesel Generator NUREG-1021. Revision 9 Supplement 1 Beaver Valley Facsimile Rev 1

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Beaver Vallev Unit 2 Exam Level: RO 0 SRO(1) [ . ,

SRO(U)O Ooeratina u Test No.:

Date of Examination:Weeks of 1218 & 12/15 2 0 O . r 2L

--OT6 NRC Exam

~~~ ~

Control Room Systemsa (8 for RO); (7 for SRO-I); (2 or 3 for SRO-IJ. including 1 ESF)

(Paired with S8)

S7 JPM 2CR-646 Perform Nuclear IR Channel Functional Test 11 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 013 A3.01 P I JPM 2PL-048 Safeguards test of FWI 3.713.9 1 D,EN 1 2 1 06 1 A2.04 3.413.8 k 2 JPM 2PL-069 Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A)

k. 064 A4.01 4.014.3 I N,R E, D, A, EN I 4s 6

P3 JPM 2PL-606 Locally Start the No. l ( 2 ) Emergency Diesel Generator -

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'Type Codes Criteria ior RO / sRO-I / SRO-U-

~~~ ~~~ ~ ~~~~~ ~~ ~~ ~ ~ ~- ~~~ ~~ , ~~~ ~

(A)lternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S9 / 5 8 i <4 (E)mergency or abnormal in-plant 21 / 21 / 21 (EN)gineered safety feature - / - / 2 1 (Control room system (L)ow-power / Shutdown 21 / 2 1 i 21

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I (N)ew or (M)odified from bank including 1(A) 2 2 1 s i 21 (P)revious 2 exams F)CA i s 3 / s 3 i 4 (randomly selectzd 21 / 2 1 / 21 (S)imulator NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev.1

ippendix D Scenario Outline Form ES-D-

acility: BVPS 2 Scenario No.: 1 Op Test No.: NRC

xaminers: Candidates: SRO ATC BOP nitial BOL, -5% power following Xe free S/U, CB D = 104,2003 PPM IC-165

'onditions:

rumover: Continue plant startup IAW 20M-52.4.A. [2SAS-C21B] Station Air Compressor OOS, will not be returned this shift

'ritical Tasks: 1 . E-0.1 Crew establishes flow from at least one high head ECCS pump before transition out of E-0.

2. E-0.P Crew manuallv actuates main steam line isolation before a Severe (orange path) challenie develops to either the Sub-criticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first.

3. E-2.A Crew isolates the faulted SG and directs operator to close isolation valve(s) operated from outside of the control room before transition out of E-2.

Event I Malf. No. Event Type Event Description No. 1 Crew raises power IAW procedure (Must raise power above 10% before N-36 fai 1ure) 2 NIS07B S R 0 T.S. IRNI N-36 Intermediate Range Nuclear Instrument Inst Pwr fuse blows

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3 XMT-RCSO 19A I(RO/SRO) [2RCS*LT459] Controlling P U R Level Channel fails low, L/D isolates SR 0 T.S.

4 N(RO/SRO) Alternate channel selected and U D restored 5 CNH-CFW 15B C(BOP/SRO) 'C' BPFRV fails open in auto, manual control required t) MSSOIC M(ALL) Steam leak inside CNMT slowly progresses to Steam line RUPTURE inside CNMT, SI, CIA, CIB 7 PMP-CHS002 C(RO/SRO) [2CHS*P21B] HHSI Pump trips on SI

[2CHS*P21A] HHSI pump Fails to AUTO, PPL07A requires manual start on S1 8 PPLl OA C(BOPISR0) AUTO MSLl failure BOTH Trains, requires manual actuation PPLl OB (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1

ippendix D Scenario Outline Form ES-D-1

acility: BVPS 2 Scenario No.: 2 Op Test No.: NRC Cxaminers: Candidates: SRO ATC BOP nitial MOL, 75 YOpower Equ ?(e, CB = 188, 11 16 PPM IC-166

onditions:

umover: Maintain current plant conditions Mica1 Tasks: 1. E.I .c Crew trips all RCPs when RCS to highest SG DIP criteria is exceeded and SI flow verified prior to exiting procedure E-I

2. FR-S.1 .C Crew inserts negative reactivity into the core by inserting RCCAs before completing the immediate action steps of FR-S.1 3

3vent Malf. No. Event Type Event Description No.

2 II XMT-MSS022A XMT-LDS003A 1I I(BOP/SRO)

SROTS.

I(RO/SRO)

[2MSS*FT485] B SG Selected Steam Flow Channel drifts HIGH VCT Level control channel failure LOW 3 l XMT-RCS032A SRO T S . [2RCS*PT455] PRZR Pressure Protection Channel fails HIGH 4 Power reduction due to TS 3.0.3 requirement (No TS Action addressing two channels of OTAT being inoperable) 5 1 RCPOIA I C(ROISR0) RCP #I seal leakoff excessive (requires Rx trip)

ATWS ~ Failure of auto/manual Rx trip

[2FWE*P22], Turbine driven AFW pump trips PPL07B during SKJ, [2FWE-P23B] Motor Driven AFW Pump requires manual start PORV [2RCS*PCV455C] sticks open after auto open and its block valve [2RCS*MOV535] cannot be closed from CR (PRZR Vapor space leak)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021. Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 acility: BVPS 2 Scenario No.: 3 Op Test No.: NRC 3xaminers: Candidates: SRO ATC BOP initial MOL, 75 % power Equ Xe, CH = 188, 11 16 PPM IC-167 conditions:

rumover: Plant has been at 75% for three days at system request. Crew is to return the unit to full power at 12%/Hr IAW 2OM-52.4.B, Load Follow, and the reactivity plan provided by Reactor Engineering. [2FWE*P23A] Motor Driven AFW Pump is on clearance for motor replacement and is due to be returned tomorrow. [2SAS-C2 IB] Station Air Compressor is on clearance for bearing replacement and due to be returned 2 days from now.

Critical Tasks: 1. E-0.Q Crew manually trips the main turbine before a Severe (orange path) challenge develops to either the Sub-criticality or the Integrit). CSF or before transition to ECA-2.1, whichever occurs first.

2. FR-H.l . A Crew establishes feedwater flow into at least one SG before RCS feed and bleed i equired.

Event Type* Event Description 1 NIS03D I (RO/SRO) PRNl N-44 fails HIGH causing automatic control rod insertion SRO T.S.

2 CRF03-H14 SRO T S . Misaligned rod. During control rod motion, Control Rod H-14 will drop to some position below the group and then remain stuck at that position R (RO) Normal power reduction N (BOPISRO) 4 C (BOPISRO) [2FWS-P21B], Main Feedwater Pump trips 5 1 PMP-CFW04 M (ALL) [2FWS-P21A], 2dMain Feedwater Pump trips 6

7 I EHC08A LOA-AFW022 C (BOP/SRO)

M (ALL)

Main Turbine fails to auto trip, manual trip successful

[2FWE*P22] Turbine driven AFW Pump trips during startup [2FWE*P23B] Motor driven AFW PMP-AFW002 Pump Trips resulting in Entry into FR-H. 1 Loss of Secondary Heat Sink.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021. Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1

Appendix D Scenario Outline Form ES-D-1 Facility: BVPS 2 Scenario No.: 4 Op Test No.: NRC Examiners: Candidates: SRO ATC BOP BOL, 100% power Equ Xe, CB 229, 1459 PPM IC-168 Conditions:

Turnover: Maintain current plant conditions 2CHS*P21C HHSI Pump 00s. Will be returned in approximately 1 week Critical Tasks: I . E-O.A Crew manually trips the reactor from the control room before performing the mitigation strategy of FR-S.1.

2. E-0.D Crew manually actuates at least one train of SIS-actuated safeguards before transition to any O M .

3. ECA-3.1 .B Crew initiates cool down of the RCS to cold shutdown conditions at the I- :hest rate achievable but less than 100°F per hour in all

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RCS C( i legs.

Event Malf. No. Event Event Description No.

____ Type*

1 XMT-MSS042A I(ALL) 2MSS*PT446 Selected First Stage Pressure Transmitter fails LOW SRO T.S.

7. PMP-CHS002 C(ROISR0) 2CHS*P21B HHSI Pump trips SRO T.S.

3 NIA Crew begins power reduction A XMT-RCS030A I(ROISR0) 2RCS-PT444 PRZR Pressure Control Channel fails HIGH 5 VLV-RCS032 C(ROISR0) [2RCS*PCV455C] P E R PORV sticks open after lifting. block valve closure required IMF PPLOlA I(RO/SRO) Automatic reactor trip failure Manual RX trip from BB B UNSUCCESSFUL, Manual RX trip from IMFPPLO 1B BB A SUCCESSFUL IOR XBlI021T RCS04C M(ALL) 350 GPM SGTR on C SG with aN MSIVs stuck open VL V-MSSOO3 VL V-MSSOO4 VL V-MSSOOS PPLOSA C(RO/SRO) Auto SI failure, both trains, manual actuation required PPLOSB (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1