ML083640082
| ML083640082 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/22/2008 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Silk D M Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML081060562 | List: |
| References | |
| TAC U01628 | |
| Download: ML083640082 (27) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 I 11 Facility: Beaver Valley Unit 2 RO Date of Exam Weeks of 1218 & 12/15 2008 I I I 3 Generic Knowledge and Abilities Category
\late: I. ?. 3. 1. 5. 3. 7.' 5. 9. 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. 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.
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. 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
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. 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. 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. RO Page 1 of 13 Beaver Valley Facsimile R3:v. 1 NUREG-1021, Revision 9 Supplement 1
- ES-401 PWR Examination Outline Form ES-401-2 II Em EiAPE # / Name / Safety Function I1 000007 (BWiEOZ&EIO; CEIE02) Reactor Trip - Stabilization - Recovery / 1 [Question I] 000008 Pressurizer Vapor Space Accident / 3 [Question 21 000009 Small Break LOCA / 3 [Question 31 000015117 RCP Malfunctions
/ 4 [Question 41 [Question 51 ud026 Loss of Component Cooling Water / 8 [Question 61 000029 ATWS / 1 [Question 71 [Question 81 Line Rupture - Excessive Heat Transfer
/ 4 [Question 91 aenc nd Abnormal Plant Evolutions -Tier IlGroup I(R0) KIA Topic@)
EK2 Knowledge of the interrelations between a reactor trip and the following:
EK2.03 Reactor trip status panel lCFR 41.7 / 45.71 AK3 Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: AK3.04 RCP tripping requirements (CFR41.5.41.10/45.6/45.13) EA1 Ability to operate and monitor the following as they apply to a small break LOCA:
EA1.13 ESFAS (CFR 41.7 / 45.5 / 45.6) AK2 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:
AK2.07 RCP seals (CFR 41.7 / 45.7) 2.4.1 1 Knowledge of abnormal condition procedures. (CFR:41.10/43.5/45.13)
2.4.8 Knowledge
of how abnormal operating procedures are used in conjunction with EOPs. (CFR:41.10/43.5/45.13) EA2 Ability to determine or interpret the following as they apply to a ATWS: EA2.01 Reactor nuclear instrumentation (CFR43.5i45.13)
EK1 r(nonr eogc of tnc operatona imp1 cat ons of the fo lo@ ny concepts as tney apply IO !he SGTR. EK1 01 &e of steam tabes (CFR41 8 41 10 453) AK1 Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture: AK1.04 Nil ductility temperature (CFR41.8 141.10 145.3) - - IR - - 3.5 - 4.2 - 4.4 - 2.9 - 4.0 - 3.8 - 4.4 3.1 1 _- 3.2 1 NUREG-1021, Revision 9 Supplement 1 ROPageZaf13 Beaver Valley Facsimile R 'v 1 is-401 EiAPE # / Name / Safety Function 100055 Station Blackout
/ 6 :Question 101 100056 Loss of Off-site Power
/ 6 [Question 111 100057 Loss of Vital AC lnst. Bus
/ 6 [Question 121 300058 Loss of DC Power / 6 [Question 131 '62 Loss of Nuclear Svc Water 1 4 [Question 141 000065 Loss of Instrument Air
/ 8 [Question 151 WIE04 LOCA Outside Containment
/ 3 [Question 161 WiEl1 Loss of Emergency Coolant Recirc. / 4 [Question 171 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier IlGroup l(R0) Continued WA Topic@) EA2 Ability to determine or interpret the following as they apply to a Station Blackout:
EA2.02 RCS core cooling through natural zirculation cooling to S/G cooling (CFR 43.5 / 45.13) AA2 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:
AA2.88 Necessary SIG water level for natural circulation (CFR: 43.5
/ 45.13) &A1 Ability to operate and
/or monitor the following as they apply to the Loss of Vital AC Instrument Bus: AAl.01 Manual inverter swapping ICFR 41.7 / 45.5 / 45.6) AK3 Knowledge of the reasons for the following 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)
AK3 Knowledae of the reasons for the followino
._ I responses as they apply to the Loss of Nuclear Service Water:
AK3.03 Guidance actions contained in EOP for Loss of nuclear service water fCFR41.4i41.8i45.71 AA2 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: AA2.08 Failure modes of air-operated equipment ICFR: 43.5 / 45.13) EA2 Ability to determine and interpret the following as they apply to the (LOCA Outside Containment)
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
ICFR: 43.5 / 45.13) EK3 Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation)
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 I1 ES-401 KIA Category Point Totals PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions .Tier 1IGroup l(R0) Continued 2 2 4 2 6 2 Group Point Total 18 EiAPE # / Name / Safety Function K Loss of Secondary Heat Sink / 4 [Question 181 ~~~ KKAAG KIA Topic(s) IR # 2312 x EA2 Ability to determine and interpret the following 3.4 1 as they apply to the (Loss of Secondary Heat Sink)
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 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 000005 InoperableiStuck Control Rod / 1 [Question 191 000032 Loss of Source Range NI I 7 [Question 201 000037 Steam Generator Tube Leak I 3 [Question 211 000069 (WIE14) Loss of CTMT Integrity
/ 5 [Question 221 WiE02 SI Terminationi3
[Question 231 ~~ WIE13 Steam Generator Over-pressure I 4 [Question 241 WIE15 Containment Flooding 1 5 [Question 251 BWIE08: WIE03 LOCA Cooldown Depress. I 4 [Question 261 NUREG-1021, Revision 9 Supplement 1 KIA Topic(s) 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 I 43.5 145.3 / 45.12) 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR:41.7/41.10/43.2/45.13)
AK3 Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: AK3.04 Use of "feed and "bleed" process. (CFR41.5 141.10 145.6 145.131 AA2 Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: AA2.01 Loss of containment integrity (CFR: 43.5
/ 45.13) EK2 Knowledge of the interrelations between the (SI Termination) and the following:
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 EK2 Knowledge of the interrelations between the (Steam Generator Overpressure) and the following: 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) EKI Knowledge of the operational implications of the following concepts as they apply to the (Containmenl Flooding). EK1.2 Normal, abnormal and emergency operating procedures associated with (Containment Flooding). (CFR:41.8/41.10/45.3) EA2 Ability to determine and interpret the following as they apply to the (LOCA Cooldown and Depressurization)
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR: 43.5 / 45.13) 39 1 __ 25 1 __ 37 1 3.5 - 3.0 - 2.7 - 3.4 - - RO Page 5 of 13 Beaver Valley Facsimile Rsw. 1 ES-401 BWIEO9, CEIA13. W/E09&E10 Natural Circ 14 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1IGroup Z(R0) Continued 12312 X EiAPE # 1 Name 1 Safety Function I KI KI KI AI AI GI WA Topic(s) IIR # EKI Knowledge of the operational implications of the following concepts as they apply to the (Natural Circulation Operations)
EKI .3 Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Operations).
3.3 [Question 271 WA Category Point Totals 2 2 1 0 2 2 Group PointTotal 9 = (CFR 41 8/41 101453) IIIIIIi 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 System # / Name 303 Reactor Coolant Pump
[Question 281 004 Chemical and Volume Control [Question 291 005 Residual Heat Removal
[Question 301 006 Emergency Core Cooling
[Question 311 006 Emergency Core Cooling
[Question 321 007 Pressurizer ReIieflQuench Tank [Question 331 008 Component Cooling Water
[Question 341 ~ 01 0 Pressurizer Pressure Control [Question 351 Plant Systems -Tier 2/Group l(R0) WA Topic(s) :3 Knowledge of the effect that a loss or nalfunction of the RCPS will have on the dlowing: (3.04 RPS CFR:41.7/45.6)
(4 Knowledge of CVCS design feature(s) indior interlock(s) which provide for the ollowing:
(4.1 1 Temperatureipressure control in etdown line: prevent boiling, lifting reliefs, iydraulic shock, piping damage, and burst CFR: 41.7) (6 Knowledge of the effect of a loss or nalfunction on the following will have on the IHRS: (6.03 RHR heat exchanger CFR: 41.7
/ 45.7) <6 Knowledge of the effect of a loss or nalfunction on the following will have on the zccs: 16.03 Safety Injection Pumps 'CFR: 41.7 / 45.71 44 Ability to manually operate and/or monitor n the control room: 44.05 Transfer of ECCS flowpaths prior to .ecirculation (CFR: 41.7
/ 45.5 to 45.8) K3 Knowledge of the effect that a loss or malfunction of the PRTS will have on the following:
K3.01 Containment ICFR: 41.7
/ 45.6) 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. (CFR: 41.10
/ 43.5 145.12) AI Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including:
AI .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 fsterns Plant R 1 x -Tier 2lGroup I(R0) Continued
~ WA Topi+)
0 2 - - IR - - 3.6 - 3.2 - 2.9 - 3.6 - 3.6 - 4.2 - 3.4 - 2.8 - 2.5 - - System # / Name 010 Pressurizer Pressure Control [Question 361 A3 Ability to monitor automatic operation of the PZR PCS, including:
A3.02 PZR pressure ICFR: 41.7 / 45.51 012 Reactor Protection
[Question 371 K4 Knowledge of RPS design feature@)
and/or interlock(s) which provide for the following: K4.06 Automatic or manual enableidisable of RPS trips ICFR: 41.71 012 Reactor Protection
[Question
- 38) ~ AI Ability to predict and/or monitor Changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including:
AI .01 Trip setpoint adjustment CFR: 41.5 / 45.51 013 Engineered Safety Features Actuation
[Question 391 K2 Knowledge of bus power supplies to the following: K2.01 ESFASisafeguards equipment control ICFR: 41.7) P-7 Containment Cooling . .estion 401 A4 Ability to manually operate and/or monitor in the control room:
A4.01 CCS fans (CFR:41.7/45.5 to45.8) 026 Containment Spray
[Question 411 K1 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems:
K1.O1 ECCS CFR: 41.2 to 41.9
/ 45.7 to 45.81 026 Containment Spray
[Question 421 039 Main and Reheat Steam
[Question 431 2.2.40 Ability to apply Technical Specifications for a system. (CFR: 41.10/43.2/43.5/45.3)
A4 Ability to manually operate and/or monitor in the control room:
A4.07 Steam dump valves (CFR: 41.7
/ 45.5 to 45.8) K4 Knowledge of MFW design feature@)
and/or interlock(s) which provide for the following:
K4.08 Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch) (CFR: 41.7) 059 Main Feedwater
[Question 441 NUREG-1021, Revision 9 Supplement 1 RO Page 8 of 13 Beaver Valley Facsimile Re 1 PWR Examination Outline Form ES-401-2 II ES-401 System # / Name 059 Main Feedwater
[Question 451 Feedwater
[Question 461 Feedwater
[Question 471 [Question 481 [Question 491 064 Emergency Diesel Generator
[Question 501 Monitoring
[Question 511 L < 1 it Systems -Tier ZlGroup l(R0) Continued WA Topic(s) A2 Ability to (a) predict the impacts of the following malfunctions or operations on the 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 following:
K2.02 AFW electric drive pumps (CFR: 41.7)
AI Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW 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 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) CFR: 41.5 / 43.5 / 45.3 / 45.13) K1 Knowledge of the physical connections and/or cause-effect relationships between the DC electrical system and the following systems: K1.02 AC electrical system (CFR:41.2to41.9/45.7to45.8)
K3 Knowledge of the effect that a loss or malfunction of the EDiG system will have on the following: K3.02 ESFAS controlled or actuated systems (CFR: 41.7
/ 45.6) K5 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system:
K5.01 Radiation theory, including sources, types, units, and effects (CFR: 41.5 / 45.7) NUREG-1021, Revision 9 Supplement 1 RO Page 9 of 13 Beaver Valley Facsimile Rcv 1 ES-401 System # / Name 076 Service Water
[Question 521 076 Service Water
[Question 531 078 Instrument Air [Question 541 103 Containment
[Question 551 , . , Category Point Totals:
1 1 1 PWR Examination Outline Form ES-401-2 Plant Systems -Tier ZlGroup l(R0) Continued WA Topic@) A2 Ability to (a) predict the impacts of the following malfunctions or operations on the 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) A4 Ability to manually operate andlor monitor in the control room: A4.04 Emergency heat loads (CFR: 41.7 I45.5 to 45.8) A3 Ability to monitor automatic operation of the IAS. including:
A3.01 Air pressure (CFR: 41.7 / 45.51 ~~ A3 Ability to monitor automatic operation of the containment system, including:
A3.01 Containment isolation (CFR: 41.7/45.5) Grouo Point Total: NUREG-1021, Revision 9 Supplement 1 RO Page 10 of 13 Beaver Valley Facsimile Re., 1 ES-401 System # / Name 014 Rod Position Indication
[Question 561 015 Nuclear Instrumentation
[Question 571 016 Non-nuclear Instrumentation
[Question 581 028 Hydrogen Recombiner and Purge Control
[Question 591 .n-Core Temperature tv,,nitor System (ITM)
[Question 601 034 Fuel Handling Equipment
[Question 611 041 Steam Dumpnurbine Bypass Control [Question 621 056 Condensate
[Question 631 NUREG-1021, Revision 9 Supplement 1 PWR Examination Outline Form ES-401-2 Plan! / 1 vstems RO Page 11 of 13 -Tier 2lGroup 2(RO) WA Topic(s) IR A2 Ability to (a) predict the impacts of the 3. following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A202 Loss of power to the RPIS (CFR: 41.5/43.5/45.3/45.13)
A4 Ability to manually operate and/or monitor in the control room:
A4.03 Trip bypasses (CFR: 41.7 / 45.5 to 45.8)
A4 Ability to manually operate and/or monitor in the control room: A4.01 NNI channel select controls (CFR: 41.7
/ 45.5 to 45.8) K5 Knowledge of the operational implications of the following concepts as they apply to the HRPS: K5.03 Sources of hydrogen within containment (CFR: 41.5
/ 45.7) A4 Ability to manually operate and/or monitor in the control room: A4.02 Temperature values used to determine RCSiRCP operation during inadequate core cooling (i.e.. if applicable, average of five highest values) (CFR: 41.7
/ 45.5 to 45.8) 3. 2.' 2.' 3,, K4 Knowledge of design feature@) and/or 2.' interlock@) which provide for the following:
K4.01 Fuel protection from binding and dropping ICFR: 41.7) K1 Knowledge of the Physical connections 3.: and/or cause-effect relationships between the SDS and the following systems:
K1.05 RCS (CFR:41.2to41.9/45.7 to45.8) K1 Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: K1.03 MFW (CFR: 41.2 to 41.9
/ 45.7 to 45.8) Beaver Valley Facsimile REI 1 ES-401 PWR Examination Outline Form ES-401-2 System # / Name 075 Circulating Water
[Question 641 086 Fire Protection
[Question 651 KIA Category Point Totals: NUREG-1021, Revision 9 Supplement 1 Plant Sy! il RO Page 12 of 13 -Tier 2IGroup Z(R0) Continued WA Topic@) K4 Knowledge of circulating water system design feature(s) and interlock@) which provide for the following:
K4.01 Heat sink (CFR: 41.7) A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including:
Al.05 FPS lineups (CFR: 41.5
/ 45.5) Group Point Total: 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 2008 I 1R IR Category KIA# Topic 1 2 1 29 Conduct switches etc Knowledge of how to conduct system lineups, such as valves breakers, (CFR: 41.10/45.1 145.12) [Question 661 of Operations ~ ~~~~~~~~ ~ ~~~~~~~ . 2.1.36 ' Knowledge of procedures and limitations invoived in core alterations.
' 3.0 ' 1 (CFR: 41 .IO / 43.6 / 45.7) [Question 671 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. ~ ~~~~______~ ~~~~~ ~ ~~~~~~~ ~ 2.1.43 I Control (CFR 41 IO / 45 12 / 45 13) [Question 701 3. 2.3.12 Knowledge of radiological safety principles pertaining to licensed 3.2 Radiation Control operator duties, such as containment entry requirements, fuel handling etc. es. access to locked high-radiation areas, aligning filters, ' (CFR: 41 .I2 / 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 Procedures/
operating procedures.
Plan parameters that are entry-level conditions for emergency and abnormal
! (CFR: 41.10 / 43.2 / 45.6) [Question 731 ~~~~~~~~ ______~ ~~~______ ~ ~~~ 2.4.1 1 Knowledge of abnormal condition procedures. (CFR: 41 .IO / 43.5 / 45.13) [Question 741 ~~~~~ ~ ~~~ ~~~~ ~~ ~~~~ ~~ ~ ~~~~ ~~~~ . ~~ (CFR 41 10 / 45 12) [Question 751 I Subtotal I I .i 3 Point Total RO Page 13of 13 Beaver Valley Facsimile F ?v. 1 NUREG-1021, Revision 9 Supplement 1
ES-401 PWR Examination Outline Form ES-401-2 I 11 Facility:
Beaver Valley Unit 2 SRO Date of Exam Weeks of 12/8 & 12/15 2008 I I 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). 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. 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.
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. 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories 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. 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.
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. 2. 3. 4. 5. 6. 7.' 8. '1 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 EiAPE # / Name / Safety Function
)00011 Large Break LOCA / 3 :Question 761 )00015/17 RCP Malfunctions
/ 4 [Question 771 300027 Pressurizer Pressure Control System Malfunction
/ 3 [Question 781 000038 Steam Generator Tube Rupture (SGTR) [Question 791 000056 Loss of Off-site Power
/ 6 - mestion 801 WIE04 LOCA Outside Containment
/ 3 [Question 811 KIA Category Point Totals:
NUREG-1021, Revision 9 Supplement 1 Emergency and Abnormal Plant Evolutions -Tier 1IGroup l(SR0) WA Topic@) 2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5 /45.13) AA2 Ability to determine and interpret the following 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) AA2 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: AA2.14 RCP injection flow (CFR: 43.5
/ 45.13) 2.4.18 Knowledge of the specific bases for EOPs. (CFR: 41.10 /43.1/45.13)
AA2 Ability to determine and interpret the following as they apply to the Loss of Offsite Power: AA2.19 T-cold and T-hot indicators (wide range) (CFR: 43.5
/ 45.13) ~~ EA2 Ability to determine and interpret the following as they apply to the (LOCA Outside Containment) EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR: 43.5
/ 45.13) Group Point Total: SRO Page 2 of 6 Beaver Valley Facsimile Rev 1 ES-401 EiAPE # / Name / Safety Function 000003 Dropped Control Rod
/ 1 [Question 821 000059 Accidental Liquid RadWaste Rel. / 9 [Question 831 000067 Plant Fire on-site [Question 841 000061 ARM System Alarms
/ 7 [Question 8-51 WA Category Point Totals:
[Qu. NUREG-1021, Revision 9 Supplement 1 PWR Examination Outline Form ES-401-2 Abnormal Plant Evolutions -Tier I/Group Z(SR0) G WA Topic@) as they apply to the Dropped Control Rod: AA2.01 Rod position indication to actual rod position (CFR: 43.5
/ 45.13) X 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
I (CFR: 41.10/43.5/45.12)
X 2.4.27 Knowledge of "fire in the plant" procedures ICFR: 41.10 / 43.5 / 45.131 AA2 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: AA2.06 Required actions if alarm channel is out of service (CFR: 43.5 145.13) Grow Point Total:
4.2 1 SRO Page 3 of 6 Beaver Valley Facsimile R 'v 1 ES-401 System # / Name 31 1 Pressurizer Level Control
[Question 911 071 Waste Gas Disposal [Question 921 086 Fire Protection
[Question 931 WA Category Point Totals: NUREG-1021, Revision 9 Supplement 1 KKKKI Ill PWR Examination Outline Form ES-401-2 Plant Systems -Tier ZlGroup 2(SRO) G WA Topic(s) X 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR:41.10/43.5/45.2/45.6) x 2.1.20 Ability to interpret and execute procedure steps. (CFR:41.10/43.5/45.12) make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. Group Point Total:
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& Category KIA# Tnpic , RO I. Conduct )f Ooerations 2.1.4 2.1.34 21 Knowledge of pre- and post-maintenance operability (CFR 41 10143 2) Equipment requirements Control Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo
operation, maintenance of active license status, 1 OCFR55. etc. (CFR: 41.10 / 43.2) [Question 941 Knowledge of primary and secondary plant chemistry limits. (CFR: 41.10/43.5/45.12)
[Question 951 . .. ~~ ~~~~~~~~~~ ~ ~~ ~ ~~~~ ~ ~ ~ ~ ~~ ~~~~~~ ~ ~ ~~~~~ ~~ ~
[Question 961 Ability to determine operability and/or availability of safety related equipment.
2,2,37 ~ (CFR: 41.7
/ 43.5 / 45.12) ~ [Question 971 Subtotal 3. 2,3,15 Knowledge of radiation monitoring systems, such as fixed Radiation radiation monitors and alarms, portable survey instruments, Control personnel monitoring equipment, etc. (CFR 41 1214341459)
[Question 981 Subtotal 1. Emergency Procedures/
Plan 2.4.20 2.4.35 Knowledge of the operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 145.13)
[Question 991 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13)
[Question 1001 ~ ~ ~~ ~~~~~~~~~~~~~~~ ~~~~~~~ Subtotal I1 I I Tier 3 Point Total 3.8 1 I 3.5 ~ 1 4.1 1 4.6 1 - 2 31 1 - - 1 43 , 1 - 4.0 1 - 2 7 _. NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 Beaver Valley Facsimile Rrw 1 ES-401 Selected WA 11 211 I 059 K4.05 APE 003 AA2.04 2.1.27 2.4.3 022 A2.05 11 212 1 072 A2.01 1 1: 1 061 A1 04 000029 2.4.1 /I 1/2 I 000060 2.4.21 Record of Rejected WAS Form ES-401-4 Reason for Rejection Beaver Valley does NOT have Ice Condensers.
Beaver Valley does NOT have variable speed main feedwater pumps. Beaver Valley does NOT have any automatic outward rod motion.
All automatic outward rod motion has b en defeated WA is NOT linked to lOCFR 55.43 and IS therefore NOT suitable for SRO exam. KIA is NOT linked to IOCFR 55.43 and is therefore NOT suitable for SRO exam.
Unable to construct a SRO discriminatory question for this KIA. Balance of exam. This would be the sixth radiation monitor question.
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 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.
BVPS Unit 2 Does Not have any AFW controls on the AFW source tank (FWE'TK210) except a level con 01 valve that will provide makeup to the tank as level drops, Unable to construct a discriminatory written que! tion to match this KIA. Unable to construct a SRO discriminatory question for this WA. Knowledge of ATWS EOP entry 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.
(0 84) .~ ~- ~- 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 famination Level RO El )I Operating Test Number 2LOT6 NRC Exam (1 Administrative Topic I (See Note)
Conduct of Operations I Conduct of Operations I + Equipment Control i7 Radiation Control Emergency ProcedureslPlan
~ Type Code* N. R N. S NIA Describe activity to be performed
'lot and Evaluate 1/M Data 2.1.43 4.1 Perform Daily Heat Balance 2.1.7 4.4 - Prepare Tagout of 21 B Service Water Pump 2.2.13 3.6 ~~ ~ Respond to Radiation Monitor Alarm and complete the Radioactive Waste Discharge permit.
2.3.1 1 3.3 NIA NOTE: All items (5 total) are rc 'Type Codes & Criteria red for SROs.
RO applicants require only 4 items unless they are retaking only the administrative
.- .~ topics, when all 5 are required. (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odified from bank (> 1) .__ .__ (P)revious 2 exams (5 1; randomly selected)
Beaver Valley Facsimile Rev 1 NUREG-1021, Revision 9 Supplement 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 II - (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency ProcedureslPlan NOTE: All items (5 total) are required Operating Test Number 2LOT6 NRC Exam Code* M, R N, R N, R N, R N, S for SROs. RC ~ ~ ~ Describe activity to be performed are required ~ , = '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) Plot and Evaluate l/M Data and make recommendations fc, continued Rod Withdrawal 2.1.43 4.3 Prepare Partial OST for Performance (2OST-6.6, PORV Isolation Valve Test and Position Check) 2.1.20 4.6 ReviewlApprove Completed RHS Pump Surveillance 2.2.37 4.6 Review/Approve LW Discharge Permit 2.3.1 1 4.3 - Evaluate EPP and complete the Initial Notification Form. 2.4.41 4.1 plicants require only 4 items unless they are retaking only the administrative topics when all 5 NUREG-1021. Revision 9 Supplement 1 Beaver Valley Facsimile Rev.
1
- <O(U) 0 Operating Test No.: - 3;: ,!PI\\: >?!.'.I? (,L!2 Piitr3rv:
IHo; Ei.is irmr!sfcr , 130 Y~, Po..yei-)
C. 006 A4.02 4.013.8 (Stand-alone)
- d. E05 EA1.l 4.114.0 (Stand-alone)
S3 JPM 2CR-529 Transfer To Cold Leg Recirculation (Post LOCA) S4 JPM 2CR-624 Establish RCS Bleed and Feed per FR-H.l (Post LOCA) II S, M, A 3 D, S, A 4P - System I JPM Title ~ L. ',8 g 015 A3.03 3.913.9 (Paired with S8) S7 JPM 2CR-646 Perform Nuclear IR Channel Functional Test (Mode 2 - 3% RX Power) S8 JPM 2CR-537 Batch To RWST (Mode 2 - 3% RXPower) h 004 A4.04 3.213.6 (Paired with S?) Type Code*
Safe?: Functic m x ", ., .- N, S, L 7 - S, M, A, L 2 .- - I. 01 3 A3.01 3.713.9 PI JPM 2PL-048 Safeguards test of FWI P2 JPM 2PL-069 Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A)
- k. 064 A4.01 4.014.3 P3 JPM 2PL-606 Locally Start the No. l(2) Emergency Diesel Generator
- 1. 06 1 A2.04 3.413.8 I 1 D, EN 2 N, R 4s E, D, A, EN 6 - .- - - 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) [ Date of Examination:Weeks of 1218 & 12/15 20O.r ., u ~~~ ~ --OT6 NRC Exam .- - Control Room Systemsa (8 for RO); (7 for SRO-I); (2 or 3 for SRO-IJ. including 1 ESF) k. 064 A4.01 4.014.3 P3 JPM 2PL-606 Locally Start the No. l(2) Emergency Diesel Generator - SRO(U)O Ooeratina Test No.: 2L E, D, A, EN 6 - (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 3.713.9 PI JPM 2PL-048 Safeguards test of FWI 2 1 D,EN 1 4s I N,R I 06 1 A2.04 3.413.8 11 k2 JPM 2PL-069 Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A)
~~ 'Type Codes Criteria ior RO / sRO-I / SRO-U- ~ ~ ~- ~~~ ~~ , ~~~ ~ 4-6 14-6 12-3 S9 / 58 i <4 21 / 21 / 21 21 / 21 i 21 221 si 21 21 / 21 / 21 ~~~~~ ~~ ~~ ~~~ ~~~ ~ (A)lternate Path (C)ontrol room (D)irect from bank (EN)gineered safety feature (E)mergency or abnormal in-plant (L)ow-power
/ Shutdown I (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams F)CA (S)imulator - / - / 2 1 (Control room system ~ i s3/ s3 i 4 (randomly selectzd .- .- 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 2 3 4 5 - t) - 7 8 nitial 'onditions:
rumover: 'ritical Tasks: NIS07B ~ XMT-RCSO 19A CNH-CFW 15B MSSOIC PMP-CHS002 PPL07A PPLl OA PPLl OB BOL, -5% power following Xe free S/U, CB D = 104,2003 PPM IC-165 Continue plant startup IAW 20M-52.4.A.
[2SAS-C21B]
Station Air Compressor OOS, will not be returned this shift 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. No. 1 Event Type SR0 T.S. I(RO/SRO)
SR 0 T. S. N(RO/SRO)
C(BOP/SRO)
M(ALL) C(RO/SRO)
C(BOPISR0) Event Description Crew raises power IAW procedure (Must raise power above 10% before N-36 fai 1 ure) IRNI N-36 Intermediate Range Nuclear Instrument Inst Pwr fuse blows [2RCS*LT459] Controlling PUR Level Channel fails low, L/D isolates Alternate channel selected and UD restored 'C' BPFRV fails open in auto, manual control required Steam leak inside CNMT slowly progresses to Steam line RUPTURE inside CNMT, SI, CIA, CIB [2CHS*P21B]
HHSI Pump trips on SI [2CHS*P21A]
HHSI pump Fails to AUTO, requires manual start on S1 AUTO MSLl failure BOTH Trains, requires manual actuation (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 3vent No. Cxaminers:
Candidates:
SRO ATC BOP nitial :onditions: umover: Maintain current plant conditions Mica1 Tasks: 1. E.I .c MOL, 75 YO power Equ
?(e, CB = 188, 11 16 PPM IC-166 Crew trips all RCPs when RCS to highest SG DIP criteria is exceeded and SI flow verified prior to exiting procedure E-I Crew inserts negative reactivity into the core by inserting RCCAs before completing the immediate action steps of FR-S.1 2. FR-S.1 .C 3 Malf. No. Event Type XMT-MSS022A I(BOP/SRO)
'I 1 SROTS. 2 I XMT-LDS003A I I(RO/SRO)
XMT-RCS032A SRO TS. 3l 4 5 1 RCPOIA I C(ROISR0)
PPL07B Event Description
[2MSS*FT485]
"B" SG Selected Steam Flow Channel drifts HIGH VCT Level control channel failure LOW [2RCS*PT455] PRZR Pressure Protection Channel fails HIGH Power reduction due to TS 3.0.3 requirement (No TS Action addressing two channels of OTAT being inoperable)
RCP #I seal leakoff excessive (requires Rx trip) ATWS ~ Failure of auto/manual Rx trip
[2FWE*P22], Turbine driven AFW pump trips 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 1 'acility:
BVPS 2 Scenario No.: 3 Op Test No.: NRC 3xaminers:
Candidates:
SRO ATC BOP initial conditions:
rumover: MOL, 75 % power Equ Xe, CH = 188, 11 16 PPM IC-167 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 NIS03D 2 CRF03-H14
-* 4 7 5 1 PMP-CFW04 LOA-AFW022 PMP-AFW002 6 I EHC08A and bleed i Event Type* I (RO/SRO) SRO T.S. SRO TS. R (RO) N (BOPISRO)
C (BOPISRO)
M (ALL) C (BOP/SRO)
M (ALL) equired. Event Description PRNl N-44 fails HIGH causing automatic control rod insertion 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 Normal power reduction [2FWS-P21B], Main Feedwater Pump trips
[2FWS-P21A], 2"d Main Feedwater Pump trips Main Turbine fails to auto trip, manual trip successful [2FWE*P22] Turbine driven AFW Pump trips during startup [2FWE*P23B]
Motor driven AFW 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 Critical Tasks: I. E-O.A 2. E-0.D 3. ECA-3.1 .B 2CHS*P21C HHSI Pump 00s. Will be returned in approximately 1 week Crew manually trips the reactor from the control room before performing the mitigation strategy of FR-S.1. Crew manually actuates at least one train of SIS-actuated safeguards before transition to any OM. Crew initiates cool down of the RCS to cold shutdown conditions at the I- RCS C( Event Type* I(ALL) SRO T.S. :hest rate achievable but less than 100°F per hour in all i legs. Event Description
~ ~ Event No. 1 ____ Malf. No. XMT-MSS042A 2MSS*PT446 Selected First Stage Pressure Transmitter fails LOW 7 '. PMP-CHS002 C(ROISR0)
SRO T.S. 2CHS*P21B HHSI Pump trips 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]
PER PORV sticks open after lifting. block valve closure required Automatic reactor trip failure Manual RX trip from BB 'B' UNSUCCESSFUL, Manual RX trip from BB 'A' SUCCESSFUL IMF PPLOlA IMFPPLO 1 B IOR XBlI021T RCS04C VL V-MSSOO3 VL V-MSSOO4 VL V-MSSOOS - I(RO/SRO)
M(ALL) 350 GPM SGTR on "C" SG with aN MSIVs stuck open PPLOSA PPLOSB C(RO/SRO)
Auto SI failure, both trains, manual actuation required (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1