ML12299A110
| ML12299A110 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/02/2012 |
| From: | Rudolph W FirstEnergy Nuclear Operating Co |
| To: | David Silk Operations Branch I |
| Jackson D | |
| Shared Package | |
| ML12136A033 | List: |
| References | |
| TAC U01850 | |
| Download: ML12299A110 (33) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
BVPS Unit 2 Date of Examination:. 9/24 thru 10/42012 (amination Level RO [R]
Operating Test Number 2LOT8 NRC Administrative Topic (See Note)
Conduct of Operations (RO A.1.1)
Conduct of Operations (RO A.1.2) equipment Control (RO A.2)
Radiation Control (RO A.3)
Emergency Procedures/Plan Type Code*
Describe activit~' to be performed N,R 2.1.25 (3.9)
Ability to interpret reference materials, such as graphs, curves, tables, etc.
(2AD-036) Perform SID Margin Calculation (At Power with One Inoperable rod).
D,R 2.1.7 (4.4)
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(2AD-30) Calculate The RCS Initial Void Volume and Final Void Volume.
N,R 2.2.13 (4.1)
Knowledge of tagging and clearance procedures.
(2AD-031) Prepare a Clearance Tagout [2QSS-P21 B] Quench Spray Pump 21B D,R 2.3.11 (3.8)
Ability to control radiation releases.
(2AD-10) Determine GW Storage tank Discharge Bleed Flow Rate NOT EVALUATED NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (::5. 3 for ROs; ::5. 4 for SROs & RO retakes)
(N)ew or (M)odified from bank <.:: 1)
(P)revious 2 exams (::! 1; randomly selected)
NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
ES-301 Facility:
BVPS Unit 2
~.xamination Level SRO [:&1 Administrative Topic (See Note)
Conduct of Operations (SRO A.1.i)
Conduct of Operations (SRO A.1.2)
Equipment Control
'SRO A.2)
Radiation Control (SRO A.3)
Emergency Procedures/Plan (SRO A.4)
Type Code*
N,R N,R N,R N,R N,R Administrative Topics Outline Form ES-301-1 Date of Examination: 9/24 thru 10/4 2012 Operating Test Number 2LOT8 NRC Describe activity to be performed 2.1.25 (4.2)
Ability to interpret reference materials, such as graphs, curves, tables, etc.
(2AD-039) Review Completed SID Margin Calculation (At Power with One Inoperable rod).
2.1.7 (4.7)
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(2AD-040) Review completed RCS Initial Void Volume and Final Void Volume Calculation.
2.2.18 (3.9)
Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments. work prioritization. etc.
(2AD-041) Perform a Risk Assessment (2FWE*P23A maintenance) 2.3.11 (4.3)
Ability to control radiation releases.
(2AD-042) Determine Compensatory actions for 2GWS-RQ104 and 2GWS-OA 100A being ODS.
2.4.40 (4.5)
Knowledge of SRO responsibilities in emergency plan implementation.
(2AD-043) Complete Initial Notification that includes a PAR.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unl topics, when all 5 are required.
- Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oorn (D)irect from bank ~ 3 for ROs;.:::: 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (:: 1)
(P)revious 2 exams (.:::: 1; randomly selected)
NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
ES-301 Control Room/In-Plant S stems Outline Form ES-301-2 Date of Examination: 9/24 thru 10/4 2012 Operating Test No..:
2LOT8 NRC
); (7 for SRO-I); (2 or 3 for SRO-U, including 1 E:SF)
System / JPM Title S1 - Shift from Main FIVV Reg. Vlvs to Bypasses (2CR-072)
S2 - Respond to Rad Monitor Alarm (leak Coli Vent) (2CR-622)
S3 - Raise Rx PWR to lO-e AMPS (2CR-644)
S4 - Isolate SI Accumulators During a LOCA (2CR-654)
S5 - Perform Manual Makeup to the Charging Suction (2CR-581)
S6 - X-fer 4Kv AE Emerg Bus from Emerg to Norm (2CR-597)
S7 - Containment Spray Manual Actuation (2CR-573)
S8 - Swap RHS Trains (2CR-636)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
Pi - Align Service Water Supply to AFW Pump Suction (2PL-167)
P2 - Startup a Rod Drive MG Set (2PL-003)
P3 - Place a RPS Channel in the Tripped Condition (2PL-009)
Type Code*
Safety Function S,D 4S S, D 7
S, D,A, L 1
3 S,D,A 2
S,N,A 6
S,M,A 5
S,M,A,EN,L 4P 4S D
1 D
7 Ail 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.
+-------------*---------------------------~I (A)lternate Path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-power / Shutdown
{N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator 4-6 14-6 12-3 s9/:;;8/:;;4
<!:1/<!:1/<!:1
- I - I > 1 (Control room system)
- 1/;;
- 1/<!:1
<!: 2/<!: 2/;:: 1
- 31
- ;; 31
- ;; 2 (randomly selected)
- 1/;
- :1/;::1 NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
ES-301 ControI R oomIIn-PIant SiyStems o tr me Form ES-301 -2 u
Facility:
BVPS UNIT 2 Date of Examination: 9/24 thru 10/42012 Exam Level: SRO(l) I2SJ Operating Test No.:
2LOT8 NRC I Control Room Systemsi!!l (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function S1 - Shift from Main FIW Reg. Vlvs to Bypasses (2CR-072)
S,D 4S S2 - Respond to Rad Monitor Alarm (leak Coli Vent) (2CR-622)
S,D 7
S3 - Raise Rx PWR to 10-8 AMPS (2CR-644)
S,D,A,L 1
S4 - Isolate SI Accumulators During a LOCA (2CR-654)
S,D,A,EN 3
S5 - Perform Manual Makeup to the Charging Suction (2CR-581)
S, D,A 2
S6 - X-fer 4Kv AE Emerg Bus from Emerg to Norm (2CR-597)
S, N,A 6
S7 - Containment Spray Manual Actuation (2CR-573)
S,M,A 5
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1 - Align Service Water Supply to AFW Pump Suction (2PL-167)
N,R,E 4S P2 - Startup a Rod Drive MG Set (2PL-003)
D 1
P3 - Place a RPS Channel in the Tripped Condition (2PL-009)
D 7
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 Crit,eria for RO 1SRO-I 1SRO-U (A)lternate Path 4-6 14-6 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~ 1 (Control room system)
(L)ow-power 1Shutdown
~1/~1/~1 (N)ew or (M)odified from bank including 1 (A)
~2/~2/~1 (P)revious 2 exams
- 31
- ::; 31:::; 2 (randomly selected)
(R)CA
~1/~1/~1 (S)imulator NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
A d' 0 Ippen IX S
. 0 tr cenano u me Form ES 0 1 II Facility:
BVPS Unit 2 Scenario No.: 1 Op Test No.:
2LOT8 NRC Examiners:
Candidates:
SRO ATC BOP Initial IC 211(7): 25% power, BOL, Xe increasing, CB "D" @ 121 steps, RCS boron - 1935 ppm.
Conditions:
Main feed regulating valves in service Turnover:
Increase power to 100%. 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks:
- 1. E-O.E Actuate 1 train of CNMT Spray
- 2. E-O.P Manually actuate SLI
- 3. E-2.A Isolate Faulted S/G Event Malf. No.
Event Type No.
(R) ATC 1
.)
(TS), SRO (M) ALL 6
Event Description Raise power in accordance with reactivity plan.
2CCS-P21A sheared shaft, auto start failure of2CCS-P21B, requires manually starting standby pump.
2FWE*P22 (turbine driven Aux Feedwater pump) trips 2CHS-PT145, fails high, ATC required to manually control letdown pressure via 2CHS-PCV145.
Loss of 2AE 4kv Emergency bus / 2-1 Emergency Diesel fails to auto start. BOP required to manually start EDG 2-1.
Feedline break inside Cl\\JMT.
CIB actuation failure MSLI actuation failure with 2SDS* AOVIIl 's failing to auto close, requires BOP to manually actuate MSLI and close all 6 2SDS*AOVl11 's "B" train CREV's fails to actuate, requires BOP to manually actuate.
rJ\\J)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev, 0
Appendix D Scenario Outline Form ES-D-1 2L8N1 The crew will assume the shift at 25% power with instructions to raise power to 100% IA W 20M-52.4.A and the reactivity plan.
When reactor power has increased to > P8 (30%), Secondary Component Cooling Water Pump, 2CCS P21 A, will experience a sheared shaft, requiring the crew to enter AOP 2.28.1, Loss of Secondary Component Cooling Water, and the BOP to manually start the standby pump, 2CCS-P21B, which failed to auto start.
The linkage for the trip-throttle valve for the Turbine Driven Auxiliary Feedwater Pump, 2FWE*P22, will fail requiring the US to determine appropriate Tech Spec action.
When Tech Specs have been addressed, Letdown Pressure Transmitter, 2CHS-PT145, will fail high, requiring the A TC to control letdown pressure by manually controlling the Letdown Pressure Control Valve,2CHS-PCVI45.
After the crew has stabilized the plant, 4KV emergency bus 2AE will de-energize and EDG 2-1 will fail to automatically start. The crew will enter AOP 2.36.2, Loss of 4KV Emergency Bus, which requires a manual start to restore power to the bus. The SRO will determine appropriate Tech Spec actions.
A Feedwater header rupture will occur inside containment. The reactor will trip. Upon the reactor trip, the crew will enter E-O.
MSLI will fail to automatically actuate, requiring the BOP to manually actuate a Steam Line Isolation.
When MSLI is actuated, the main steam line drains (2SDS* AOVl11 's) will fail to close requiring the BOP to manually close at least 1 train.
CIB will fail to automatically actuate, The A TC will identify the failure to actuate and manually actuate both trains of CIB.
The crew will identify the "C" S/G as faulted and transition to E-2 to isolate.
Train "B" CREV's, Control Room Emergency Ventilation System, will fail to actuate requiring the BOP to manually initiate.
The crew will progress through E-2 and transition to E-l.
The scenario will be terminated after the crew transitions to ES-1.1.
Expected procedure f10w path is E-O -+ E-2 -+ E-1 -+ ES-1.1.
NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
A d'
ppen IX D s
cenano 0 r ut me Form ES-D-1 II Facility:
BVPS Unit 2 Scenario No.:2 Op Test No.:
2LOT8 NRC Examiners:
Candidates:
SRO ATC BOP Initial IC 212(17): 72% power, MOL, Eq Xe. CB "D"@180 steps, RCS boron - 1140 ppm.
Conditions:
Turnover:
Maintain steady state power at 72%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks:
- 1. E-O.A Manually trip the Reactor
- 2. E-O.Q Manually trip the turbine
- 3. FR-H.1.A Establish feedwater flow before F,eed and Bleed criteria Event Malf. No.
No.
1 2
3 4
5 6
7 8
9 Event Type (C) ATC, SRO (TS) SRO (R) ATe (C) BOP, SRO (TS) SRO (M) ALL (C) ATC, SRO (C) BOP, SRO (M) ALL (C) BOP, SRO (C) BOP, SRO Event Description N44 fails high, rods automatically step in.
2FWS-P21 B trips/ reduce power to 52%
Misaligned Rod 2RCS*P21 B locked rotor trip Automatic Reactor trip failure Automatic turbine trip failure Loss of all auxiliary feed water, entry into FR-H.l Failure of2FWS-P24, 2FWS-P21A and P21B (requires secondary depressurization and use of condensate pump.
2HVS-FN204A and B trip, requires manual starting of at least 1 fan.
O\\J)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
Appendix 0 Scenario Outline Form ES-O-1 2L8N2 The crew will assume the shift at 72% power with instructions to maintain steady state conditions.
N-44 will fail high causing the control rods to automatically insert. The crew will enter AOP 2.1.3, RCCA Control Bank Inappropriate Continuous Movement, verify no load rejection is occurring and then the ATC will place the control rods in Manual to stop rod insertion. The US will then enter AOP 2.2.1 C, Power Range Channel Malfunction, to remove the channel from service and determine appropriate Tech Spec action.
Main Feedwater pump, 2FWS-P21 B will then trip, the crew will enter AOP 2.24.1, Loss of Main Feedwater AOP, and begin an immediate power reduction to 52%. While the rods are inserting, 1 rod will experience a moveable gripper failure causing the rod to ratchet inward on each step demand. The crew will identify the misaligned rod and initiate boration for the remainder of the power reduction. After the plant has stabilized, the SRO will enter AOP 2.1.8, Rod Inoperability, and address Tech Spec's for the misaligned rod.
The "B" reactor coolant pump will then experience a locked rotor trip, the reactor will fail to automatically trip, the ATC will manually trip the reactor. The crew will enter E-O.
The turbine will fail to automatically trip in the reactor trip requiring the BOP to manually trip the turbine.
A loss of all aux feed water will then occur, the crew will recognize the loss and enter FR-H.l, Response to Loss of Secondary Heat Sink, to re-establish feedwater.
The crew will attempt to restore normal feedwater via the startup feedwater pump and the main feedwater pumps, Various failures will prevent each pump from starting. The crew will then depressurize the S/G's to establish feedwater flow from a condensate pump. When feedwater flow has been re-established, the SRO will return to E-O.
The Ventilation fans, 2HVS-FN204A & B will trip on the reactor trip, the BOP will start at least 1 fan.
The scenario will be terminated after the crew transitions to ES-l.l.
Expected procedure flow path is E-O ----> FR-H.l ----> E-O ----> ES-l.l.
NUREG-1 021. Revision 9 Supplement 1 FENoe Facsimile Rev. 0
A d'
.ppen IX D S
cenano 0 tr u me Form ES-D 1 Facility:
BVPS Unit 2 Scenario No.:4 Op Test No.:
2LOT8 NRC Examiners:
Candidates:
SRO ATC BOP Initial IC 214(18): 100% power. MOL. Eq Xe, CB "D" @ 225 steps, RCS boron - 1044 ppm.
Conditions:
Turnover.
Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21 BOOS Critical Tasks:
- 1. E-O.O Close CNMT isolation valves
- 2. E-l.C Stop RCP's
- 3. FR-S.l.C Insert RCCA's Event Malf. No.
Event Type No.
(1) ArC, SRO 1
(R) ATC 3
crS) SRO (M) ALL 6
(M) ALL 7
9 Event Description 2RCS*LT459 fails low.
Restore letdown to service Valve position limiter failure causes load rejection with Auto rod malfunction, ATC required to insert negative reactivity.
During load rejection, "A" Main Feed Regulating Valve controller holds valve in position, BOP required to manually control "A" S/G level.
2RCS*PT445 fails high, 2 PORV's open, 2RCS*PCV455C fails to 18% open with Block valve failed open, requiring crew to manually trip the reactor.
A TWS, crew enters FR-S.l.
2000 gpm SBLOCA on return to E-O.
Train B CIA failure with 2CHS*MOV378 failing to auto close O\\T)ormaL (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
Appendix 0 Scenario Outline Form ES-O-1 2L8N4 The crew will assume the shift at ] 00% power with instructions to maintain steady state conditions.
The controlling PZR level channel, 2RCS*LT459 will fail low causing letdown to automatically isolate.
The crew will enter the Instrument failure procedure to address the failed channel and place the alternate channel in service. The US will determine appropriate Tech Spec action.
After the alternate channel is placed in service, the crew will restore normal letdown to service.
When letdown has been restored. the valve position limiter will fail causing a load rejection with an Auto Rod malfunction requiring the A TC to manually insert control rods.
During the load rejection, the "A" Main feed regulating valve will fail to control in auto (the valve will remain in its 100% power position), The BOP will be required to recognize the malfunction and manually control the "A" S/G level.
Once the plant has stabilized, a ReS control pressure transmitter, 2RCS*PT445 will fail high, causing 2 PORV's to open, 2RCS*PCV455C will stick at 18% open, with the block valve failing to close. The SRO will address PORV Tech Spec. RCS pressure will continue to slowly decrease requiring the SRO to direct the crew to manually trip the reactor and enter E-O.
The reactor will fail to trip from the control room, the SRO will transition to FR-S.l and the crew will dispatch an operator to locally trip the Rx. After the reactor is locally tripped, the crew will return to E-O.
3 minutes after the reactor is locally tripped, a 2000 gpm LOCA will occur on the "A" loop, the crew will transition to E-1. The crew will be required to recognize that RCS I Secondary pressure DP requirements are met to require that the Rep's be manually tripped.
Train "B" CIA will fail to actuate along with 2CHS*MOV378 failing to auto close on the Train "A" CIA signal.
The scenario will be terminated after the crew transitions to ES-l.2.
Expected procedure now path is E-O FR-S.1-4E-0-4E-I-4ES-1.2.
NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 0
A d" 0 Ippen IX S
" 0 tr cenano u me Form ES 0 1
\\I Facility:
BVPS Unit 2 Scenario No.:5 Op Test No.:
2LOT8 NRC Examiners:
Candidates:
SRO ATC BOP Initial IC 217( 1 0): 100% power, BOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1458 ppm.
Conditions:
Turhcvel Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks:
- 1. E-O.D Crew manually actuates at least one train of SIS
- 2. E-O.F Crew establishes the minimum required AFW flow
- 4. E-O.I Establish flow from at least 1 High head ECCS pump Event Malf. No.
Event Type Event Description No.
1 (I) ATC, SRO 2RCS*PT444 drifts low, requires ATC to manually control RCS pressure.
(TS) SRO 2FWS-LT485 fails high 2
(C) BOP, SRO Voltage regulator failure causes main generator over 3
excitation, requires BOP to turn voltage regulator off and manually lower excitation.
(1) ATC, SRO 2CHS-L T 115 fails high, requires A TC to restore letdown flow 4
to the VCT and perform manual makeups as necessary.
(C) ATC, SRO 25 gpm RCS leak on "A" Loop 5
(TS) SRO (M) ALL 500 gpm RCS leak on "A" Loop.
6 (C) ATC, SRO 2RCS-PCV455D fails open on Rx trip, requires ATC to close 7
block valve.
(C) BOP, SRO AFW malfunctions, 2FWE*P23A OOS on turnover, 8
2FWE*P23B auto start failure, requires BOP to manually start.
2FWE*P22 running with reduced flow << 340 gpm)
(C) ATC, SRO Auto SIS inhibited, requires ATC to manually actuate SIS.
'I 9
(C) ATC, SRO 2SIS*MOV867's fail to open on SIS actuation signal, ATC 10 required to manually open valves to initiate Safety Injection flow.
~N)ormaL (R)eactivity, (l)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev, 0
Appendix D Scenario Outline Form ES-D-1 2L8N5 The crew will assume the shift at 100% power with instructions to maintain steady state conditions.
The controlling PZR pressure channeL 2RCS*PT444 will drift low causing RCS pressure to rise due to the pressurizer spray valves closing and the heaters energizing. The crew will respond lAW 20M-6.4.IF, attachment 2. The A TC controls Pzr pressure by manually operating the Pzr heaters and spray valves or manual control of the Pzr pressure master controller.
When the plant has stabilized. 2FWS-LT485, S/G 21B Channel II Narrow Range level transmitter will fail high requiring use of 20M-24.4.IF attachment 1, SRO will review TS.
After the SRO completes FWS L T Tech Spec determination, the voltage regulator will fail causing overexcitation of the MUG. lAW the alarm response procedure, the BOP will turn the voltage regulator off and manually restore power factor and excitation by lowering the base adjust.
VCT level transmitter, 2CHS-LTl15 will fail high causing the letdown flowpath to fully divert, using the instrument failure procedure guidance, the ATC will restore letdown flow to the VCT. The ATC will also be required to manually initiate VCT makeups.
A 25 gpm RCS leak will then occur on the "A" loop, the crew will recognize degrading parameters and enter AOP 2.6.7, Excessive Primary Plant Leakage, to address the primary plant leakage. The SRO will address RCS leakage Tech Spec.
The leak will then become a 500 gpm SBLOCA, RCS pressure and pressurizer level will decrease requiring the SRO to direct the crew to manually trip the reactor and enter E-O.
Upon the reactor trip. PORV 4550 will fail partially open, the ATC will recognize PORV failure and close the block valve.
Auxiliary feedwater malfunctions also occur on the reactor trip, the turbine driven pump will start but provide insufficient flow and the remaining available Motor driven AFW pump will fail to auto start, the BOP will manually start 2FWE*P23B.
SIS will fail to automatically actuate on low RCS pressure, the A TC will manually actuate SIS.
Upon SIS actuation, 2SIS*MOV867's will fail to automatically open, the ATC will manually open valves to initiate SIS injection tlow.
The crew will transition from E-O to £-1 when checking if RCS is intact based on containment parameters.
E-l will then be performed until transition to ES-l.2.
The scenario will be terminated after the crew transitions to 1.2 Expected procedure flow path is E-O......... E-1.........
1.2.
NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Facir 2RO Date of Exam 9/24 thru 10/5 2012 Points Tier Group K
K K
A A
A G
TOTAL 1
2 3
2 3
4
- 1.
1 3
3 3
3 18 Emergency 2
1 2
1 1
9 Abnormal Plant Evolutions Tier Totals 4 5 4 4
27
- 2.
1 2
2 3
3 2
2 3
3 3
2 3
28 Plant Systems 2
2 1
1 1
1 1
1 0
0 1
1 10 Tier 4 3 4 4 3 3 3 4 38 Totals 3
4
- 3. Generic Knowledge and 10 Abilities Category 3
2 2
3 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, thl~ "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 Ibased 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 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 KiA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KiA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
NUREG-1021, Revision 9 Supplement 1 RO Page 1 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
~======================~~~=F=
E/APE # 1Name 1Safety Function 000008 Pressurizer Vapor Space Accident 1 3
[Question 1]
K 1
000009 Small Break LOCA 13
[Question 2]
000015/000017 Reactor Coolant Pump (RCP) Malfunctions 14
[Question 3]
000022 Loss of Reactor Coolant Makeup 1 2
[Question 4]
000025 Loss of RHR System 14 rQuestion 5]
000027 Pressurizer Pressure Control System Malfunction 13
[Question 6]
000029 A TVVS 11
[Question 7]
000038 Steam Generator Tube Rupture I 3
[Question 8]
000040 Steam Une Rupture Heat Transfer 1 4
[Question 9]
Excessive KIA Topic(s)
AK2 Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following:
AK2.03 Controllers and positioners (CFR41.7/45.7)
EA2 Ability to determine or interpret the following as they apply to a small break LOCA:
EA2.37 Existence of adequate natural circulation (CFR 43.5 145.13)
AK2 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:
2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.
M 1.11 Reactor building sump level indicators (CFR 41.7 145.5/45.6)
M 1 Ability to operate and 1or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions:
M1.01 PZR heaters, sprays, and PORVs (CFR 41.7 145.5/45.13)
EK2 Knowledge of the, interrelations between the and the following an ATVVS:
EK2.06 Breakers, relays, and disconnects (CFR 41.7 145.7)
EK3 Knowledge of the, reasons for the following responses as the apply to the SGTR:
EK3.04 Automatic actions provided by each PRM (CFR 41.5/41.10 145*.6/45.13)
AK3 Knowledge of the reasons for the following responses as they apply to the Steam Une Rupture:
AK3.01 Operation of steam line isolation valves (CFR 41.5,41.10 145.6/45.13)
IR 2.5 4.2 2.6 3.9 2.9 4.0 2.9*
3.9 4.2 1
1 NUREG-1021, Revision 9 Supplement 1 RO Page 2 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401*2 Emergency and Abnormal Plant Evolutions* Tier 1/Group 1(RO) Continued
~======================~~~~
E/APE # I Name I Safety Function 000054 Loss of Main Feedwater I 4
[Question 10]
000055 Station Blackout /6
[Question 11]
000057 Loss of Vital AC Electrical I nstrument Bus / 6
[Question 12]
000058 Loss of DC Power /6
[Question 13]
OR5 Loss of I nstrument Air I 8 Jestion 14]
000077 Generator Voltage and Electric Grid Disturbances 16
[Question 15]
W/E04 LOCA Outside Containment 13
[Question 16]
W/E05 Loss of Secondary Heat Sink 14
[Question 17]
KIA Topic(s)
IR AK1 Knowledge ofths* operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW):
3.6 1
AK 1.02 Effects of feedwater introduction on dry SIG (CFR 41.8/41.10 /45.3)
EK1 Knowledge of the operational implications of the following concepts as they apply to the Station Blackout:
4.1 1
EK1.02 Natural circulation cooling (CFR 41.8 141.10/45.3) 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.5 1
(CFR: 41.10/43.2 14S.6)
AK1 Knowledge of thE! operational implications of the following concepts. as they apply to Loss of DC Power:
2.8 AK1.01 Battery charger equipment and instrumentation (CFR 41.8/41.10/45.3)
AK3 Knowledge of the~ reasons for the following responses as they apply to the Loss of Instrument Air:
3.7 AK3.08 Actions contained in EOP for loss of instrument air (CFR 41.5,41.10 145.6/45.13)
AA2 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances:
3.5 AA2.03 Generator current outside the capability curve (CFR: 41.5 and 43.5/45.5, 45.7, and 45.8) 2.1.23 Ability to system integrated plant procedures during all modes of plant operation.
4.3 (CFR: 41.10 143.5/45.2/45.6)
EA 1 Ability to operate and I or monitor the following as they apply to the (Loss of Secondary Heat Sink) 3.7 EA 1.2 Operating behavior characteristics of the facility.
(CFR: 41.7/45.5/45.6)
NUREG-1021, Revision 9 Supplement 1 RO Page 3 of 13 FENOC Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401*2 Emergency and Abnormal Plant Evolutions* Tier 1/Group 1(RO) Continued
~=======================r=r=r=r=
E/APE # I Name I Safety Function W/E11 Loss of Emergency Coolant Recirculation I 4
[Question 18]
KIA Category Point Totals:
KKK 123 A
1 KIA Topic{s)
IR EA2 Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation):
3.4 EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facility's license and amendments.
(CFR: 43.5/45.13)
Group Point Total:
18 NUREG-1021, Revision 9 Supplement 1 RO Page 4 of 13 FENoe Facsimile Rev. 0
1 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(RO)
E/APE # I Name I Safety Function K K K KiA Topic(s)
IR
~~~:x/
1 2 3 ~I~'~
~G AA2 Ability to determine and interpret the following 000036 Fuel Handling Incidents I 8 I;<~x 3.4 Il:x; as they apply to the Fuel Handling Incidents:
[Question 19]
AA2.02 Occurrence of a fuel handling incident rt~ l~f~
(CFR: 43.5 I 45.13)
I?i l~lX;XX AK2 Knowledge of the interrelations between the 000061 ARM System Alarms I 7
)(
I:~
r~'~x:
2.5*
1 Area Radiation Monitoring (ARM) System Alarms
(.~
[Question 20]
'x¥;x and the following:
Ix/'
xc:;
AK2.01 Detectors at each ARM system location r~x '" x I;,~ Itx (CFR 41.7 145.7)
AK1 Knowledge of the operational implications of the 000067 Plant Fire On-site I 9
)(
L";i;~
3.1 1
following concepts as they apply to Plant Fire on I;~
[Question 21]
Site:
I, '
AK1.02 Fire fighting
'x Ii"",
I*,~~;
(CFR 41.8 141.10 145.3)
~,~,:
AA 1 Ability to operate and I or monitor the following 000068 Control Room Evacuation I 8 3.2*
1 X
Ix as they apply to the Control Room Evacuation:
[Question 22]
1;/*:
.~,
AA 1.27 Local trip of main feed pumps and Condensate pumps
- b.
Xy\\~ I~
(CFR 41.7 145.5 I 45J3) 000076 High Reactor Coolant Activity I 9
&~
1'1 2.1.31 Ability to locate control room switches, 4.6 1
controls, and indications, and to determine that they
[Question 23]
I~k correctly reflect the desired plant lineup.
IXX('
(CFR: 41.10/45.12)
I~~
EA 1 Ability to operate and I or monitor the following
'vVlE07 Saturated Core Cooling / 4 3.5 1
Xf':Yil;' lx,' as they apply to the (Saturated Core Cooling):
I*'...~
[Question 24]
~
EA 1.3 Desired operating results during abnormal x,
and emergency situations.
t~::r ~ (CFR: 41.7 / 45.5 /45.6)
EK3 Knowledge of the reasons for the following W/E08 RCS Overcooling - PTS I 4
~~~
3.4 1
X U:~ responses as they apply to the (Pressurized Thermal
[Question 25]
~1j~~
Shock):
I~
I',' I,. EK3.1 Facility operating characteristics during r~~~: r,~:~* transient conditions, including coolant chemistry and the effects of temperallure, pressure, and reactivity I~x '*.~
changes and operatin!~ limitations and reasons for these operating characteristics.
(CFR: 41.5 I 41.10,45.6,45.13) b~~.j~1 EA2 Ability to determine and interpret the following E09 Natural Circulation Operations /4 3.1 1
I;~ r~1J~ as they apply to the (Natural Circulation Operations)
[Question 26]
.. ~.'
~ x
~:
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
r;x'~
1~~jX' Iq (CFR: 43.5 I 45.13)
NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions '. Tier 1/Group 2(RO) Continued 1F===========================~9==r=T~
E/APE # I Name I Safety Function K
1 W/E14 High Containment Pressure 15
[Question 27]
KIA Topic(s)
EK2 Knowledge of the interrelations between the (High Containment Pmssure) 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)
Group Point Total:
IR 3.4 1
NUREG-1021, Revision 9 Supplement 1 RO Page 6 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems
- Tier 2/Gt'oup 1(RO)
~~~~ ~~~F=========================~r===r=~
System # 1Name K K KIA Topic(s)
IR 1 2 003 Reactor Coolant Pump
[Question 28]
004 Chemical and Volume Control
[Question 29]
004 Chemical and Volume Control
[Question 30]
[Question 31]
[Question 32]
006 Emergency Core Cooling
[Question 33]
007 Pressurizer Relief/Quench Tank
[Question 34]
008 Component Cooling Water
[Question 35]
010 Pressurizer Pressure Control
[Question 36]
A 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:
A 1.03 RCP motor stator winding temperatures 2.6 K2 Knowledge of bus power supplies to the following:
K2.02 Makeup pumps 2.9 (CFR: 41.7)
K4 Knowledge of CVCS design feature(s) and/or interlod;(s) which provide for the following:
K4.14 Control interlocks on letdown system (letdown tank bypass valve) 2.8*
(CFR: 41.7) 2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10/43.2/45.12) 3.8 K1 Knowledge of the physical connections and/or cause/effect relationships between the RHRS and the following systems:
K1.13 SIS 3.3 (CFR: 41.2 to 41.9/45.7 to 45.8)
K1 ofthe connections and/or cause/effect relationships between the ECCS and the following systems:
K1.07 MFW System 2.9*
(CFR: 41.2 to 41.9/45.7 to 45.8) operation ofthe 2.7*
A3.01 Components which discharge to the PRT (CFR: 41.7/45.5)
A 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:
A1.01 CCW flow rate 2.8 K6 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS:
3.2 K6.03 PZR sprays and heaters (CFR:41.7/4!5.7)
NUREG-1021, Revision 9 Supplement 1 RO Page 7 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401*2 Plant Systems
- Tier 2/Group 1 (RO) Continued System # / Name K K KIA Topic(s)
IR 1
2 012 Reactor Protection K3 Knowledge of the effect that a loss or 3.2*
malfunction of the RPS will have on the
[Question 37]
following:
K3.02 T/G (CFR: 41.7/45.6) 013 Engineered Safety Features Actuation K6 Knowledge of the effect or malfunction on the following wi" have on the 2.7*
1 ESFAS:
[Question 38)
K6.01 Sensors and detectors (CFR: 41.7/45.5 to 45.8) 022 Containment Cooling K2 Knowledge of power supplies to the following:
3.0*
[Question 39]
K2.01 Containment cooling fans (CFR: 41.7) 026 Containment Spray K4 Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
3.7*
1
[Question 40]
K4.09 Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover).
(CFR:41.7) n~q Main and Reheat Steam K5 Knowledge of the operational implications of the following concepts as the apply to the 2.7 estion 41]
MRSS:
K5.05 Bases for RCS cooldown limits (CFR: 41.5/45.7) 059 Main Feedwater K3 Knowledge of the effect that a loss or 3.6 malfunction of the MFW will have on the
[Question 42) following:
K3.02 AFW sy:stem (CFR: 41.7 /45.6) 061 Auxiliary/Emergency Feedwater K5 Knowledge the operational of the following concepts as the apply to the 3.6 AFW:
[Question 43]
K5.01 Relationship between AFW flow and RCS heat transfer (CFR: 41.5 / 45.7) 061 Auxiliary/Emergency Feedwater A 1 Ability to predict andlor monitor changes in parameters (to prevent exceeding design 3.9 limits) associated with operating the AFW
[Question 44]
controls including:
A1.01 S/G leVE!1 (CFR: 41.5/415.5)
NUREG-1 021, Revision 9 Supplement 1 RO Page 8 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems
- Tier 2/Group 1(RO) Continued System # 1Name 062 AC Electrical Distribution
[Question 45]
062 AC Electrical Distribution
[Question 46]
063 DC Electrical Distribution
[Question 47]
063 DC Electrical Distribution
[Question 48]
064 Emergency Diesel Generator
[Question 49]
064 Emergency Diesel Generator
[Question 50]
073 Process Radiation Monitoring
[Question 51]
076 Service Water
[Question 52]
KIA Topic(s)
IR to manually operate andlor monitor in the control room:
3.1*
A4.07 Synchronizing and paralleling of different ac supplies (CFR: 41.7 145.51 to 45.8)
K4 Knowledge of ac distribution system design feature(s) andlor interlock(s) which provide for the following:
3.1 K4.10 Uninterruptable ac power sources (CFR: 41.7) 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
4.4 (CFR: 41.5/4~1.5/45.12/45.13)
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
2.5 A2.01 Grounds, (CFR: 41.5/43.5 145.3 145.13)
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the EDIG system; ;:md (b) based on those predictions, US1~ procedures to correct, control, or mitigate the consequences of those malfunctions Olr operations:
2.6*
1 A2.13 Consequences of opening auxiliary feeder bus (ED/G sub supply)
(CFR: 41.5/43.5 145.3 145.13)
A4 Ability to manually operate in the control mom:
monitor 3.2*
1 A4.04 Remote operation of the air compressor switch (different modes)
(CFR: 41.7/45.5 to 45.8)
K3 Knowledge of the effect that a loss or malfunction of the PRM system will have on the following:
3.6 K3.01 Radioactive effluent releases (CFR: 41.7/41>'6)
A3 Ability to monitor automatic operation of the SWS, including:
3.7 A3.02 Emergency heat loads (CFR: 41.7/415.5)
NUREG-1021, Revision 9 Supplement 1 RO Page 9 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems
- Tier 2/Group 1 (RO) Continued
~=================r=r=F9F9F9F=F=
System # I Name K
KIA Topic(s)
IR 1
078 Instrument Air A3 Ability to monitor automatic operation of the 3.1 lAS, including:
[Question 53]
A3.01 Air pressure (CFR: 41.7 14Ei.5) 103 Containment A2 Ability to (a) predict the impacts of the 3.5*
following malfunctions or operations on the
[Question 54]
containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations A2.03 Phase A and B isolation (CFR: 41.5/43.5 145.3 145.13) 103 Containment 2.4.6 Knowled~le of EOP mitigation strategies.
3.7
[Question 55]
(CFR: 41.10/43.5/45.13)
Point Totals:
28 NUREG-1021, Revision 9 Supplement 1 RO Page 10 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems
- Tier 2/Group 2(RO)
System # / Name K K K K K
KIA Topic(s)
AlA A~
1 2
3 4
~ 6 1, ' 3 41, IR r:
~l K2 Knowledge of bus power supplies to the 001 Control Rod Drive System 3.1*
1
- x following:
[Question 56]
K2.05 M/G sets r~
(CFR: 41.7) 2.2.37 Ability tCl determine operability and/or 015 Nuclear Instrumentation 3.6 1
availability of safety related equipment.
It!
[Question 57]
11 (CFR 41.7/4:1.5/45.12) 016 Non-nuclear Instrumentation
[Question 58]
017 In-Core Temperature Monitor System (ITM)
[Question 59]
(l.d1 Steam Dump System (SDS)
Turbine Bypass Control
[Question 60]
- )
033 Spent Fuel Pool Cooling
[Question 61]
034 Fuel Handling Equipment
[Question 62]
055 Condenser Air Removal
[Question 63]
)(
071 Waste Gas Disposal
[Question 64]
- )
['::1:
I', t;t i~~~
J'
- x ~t~**
.~.~
I~~
I'Y;"
)(
I~?
r~~~.
)(
I~
~!
I~
I~';~
I 1~
K5 n.1
- ., of the operational implication of the following concepts as they apply to the NNIS:
K5.01 Separation of control and protection circuits (CFR: 41.5/45.7)
A 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ITM system controls including:
A1.01 Core exit temperature (CFR: 41.5/45.7)
K 1 Knowledge of the Physical connections and/or cause-effect relationships between the SDS and the fc)lIowing systems:
K1.02 S/G level (CFR: 41.2 to 41.9 145.7 to 45.8)
K4 Knowledge of design feature(s) and/or interlock(s) whilch provide for the following:
K4.05 Adequale SDM (boron concentration)
(CFR: 41.7)
K6 Knowledge of the effect of a loss or malfunction on the following will have on the Fuel Handling System:
K6.02 Radiation monitoring systems (CFR: 41.7/45.7)
K1 Knowledge of the physical connections and/or cause/effect relationships between the CARS and the following systems:
K1.06 PRM system (CFR: 41.2 to 41.9/45.7 to 45.8)
A4 Ability to manually operate and/or monitor in the control room:
A4.05 Gas decay tanks, including valves, indicators, and sample line (CFR: 41.7 145.5 to 45.8) 2.7*
3.7 2.7 3.1 2.6*
2.6 2.6*
1 1
1 1
1 1
1 NUREG-1021, Revision 9 Supplement 1 RO Page 11 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems 1~===================9r=r=T=~~~~=
System # I Name 075 Circulating Water.
[Question 65]
KIA Category Point Totals:
2 1
1 1 0 0
1
- Tier 2/Group 2(RO) Continued KIA Topic(s)
K3 Knowledge of the effect that a loss or malfunctions of the circulating water system will have on the following:
K3.07 ESFAS (CFR: 41.7 14e'.6)
Group Point Tc,tal:
IR 3.4*
NUREG-1 021, Revision 9 Supplement 1 RO Page 12 of 13 FENoe Facsimile Rev. 0
01 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 racility: BVPS UNIT 2 RO Date ofExam 9/24 thru 10/5 2012 RO Category KlA#
Topic IR
- 1.
2.1.21 Ability to verify the controlled procedure copy.
3.5*
1 Conduct
[Question 66] (CFR: 41.10 145.10 I 45.13) of Operations 2.1.39 Knowledge of conservative decision making practices.
3.6
[Question 67] (CFR: 41.10/43.5/45.12) 2.1.45 Ability to identify and interpret diverse indications to validate the 4.3 1
response of another indication.
[Question 68] (CFR: 41.7/43.5/45.4)
Subtotal
- 2.
2.2.23 Ability to track Technical Specification limiting conditions for operations.
Equipment
[Question 69] (CFR: 41.10 143.2 145.13)
Control 2.2.41 Ability to obtain and interpret station electrical and mechanical drclwings.
3.5
[Question 70] (CFR: 41.10/45.12/45.13)
Subtotal 2.3.14 Knowledge of radiation or contamination hazards that may arise during
,ation normal. abnormal. or emergency conditions or activities.
Control
[Question 71] (CFR: 41.12/43.4 145.10) 2.3.15 Knowledge of radiation monitoring systems. such as fixed radiation 2.9 monitors and alarms, portable survey instruments. personnel monitoring equipment, etc.
[Question 72] (CFR: 41.12/43.4 145.9)
Subtotal
- 4.
2.4.3 Ability to identify post-aCCident instrumentation.
Emergency
[Question 73] (CFR: 41.6145.4)
Proceduresl Plan 2.4.13 I Knowledge of crew roles and responsibilities during EOP usage.
4.0 1
I [Question 74] (CFR: 41.10/45.12) 2.4.34 Knowledge of RO tasks performed outside the main control room during 4.2 an emergency and the resultant operational effects.
[Question 75] (CFR: 41.10/43.5/45.13)
Subtotal Tier 3 Point Total NUREG-1021, Revision 9 Supplement 1 RO Page 13 of 13 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Facility:
SRO ONL Y Points Tier G*
TOTAL 1
3 3
6
- 1.
Emergency 2
2 2
4 Abnormal Tier Plant 5
5 10 Totals Evolutions 1
3 2
5
- 2.
Plant Systems 1
1 3
5 3
8
- 3. Generic Knowledge and 7
Abilities Category 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 (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 cate!~ories.
7.*
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D. 1.b of ES-401 for the applicable KlAs.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
NUREG-1 021, Revision 9 Supplement 1 SRO Page 1 of 6 FENOC Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(SRO)
~=======================F=F~~~
E/APE # 1Name 1Safety Function KKK 123 KiA Topic(s)
IR 000007 Reactor Trip -Stabilization /1
[Question 76]
2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.
(CFR: 41.10/43.5/41;.13) 4.3 000011 Large Break LOCA 13 4.4
[Question 77]
000026 Loss of Component Cooling Water I 8
[Question 78]
000056 Loss of Offsite Power /6
[Question 79]
"",'C L'7;',"
2.1.20 Ability to interpret and execute procedure steps.
(CFR: 41.10 143.5/45.12)
AA2. Ability to determine and interpret the following as they apply to the Loss of Offsite Power:
AA2.45 Indicators to assess status of ESF breakers (tripped/not-tripped) and validity of alarms (false/not false) 4.6 3.9 1
(CFR: 43.5/45.13) 000062 Loss of Nuclear Service Water I 4
[Question 80]
AA2. Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water:
AA2.01 Location of a leak in the SWS 3.5 W/E12 Steam Line Rupture - Excessive Heat Transfer 14
'..... *.estion 81]
"'J".'w..;,:.,
EA2. Ability to determine and interpret the as they apply to the (Uncontrolled Depressurization of all Steam Generators) 4.0 1
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(CFR: 43.5/45.13)
KIA Category Point Totals:
o 0 0
0 3
3 Group Point Total:
6 NUREG-1021. Revision 9 Supplement 1 SRO Page 2 of 6 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions** Tier 1/Group 2(SRO) 1F=======================~~=r=r=
E/APE # I Name I Safety Function KKK 1 2 3 A
1 KIA Topic(s)
IR 000003 Dropped Control Rod 11
[Question 82]
AA2. Ability to determine and interpret the following as they apply to the Dropped Control Rod:
AA2.03 Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements 3.8 1
(CFR: 43.5/45.13) 000074 Inadequate Core Cooling /4
[Question 83]
2.1.19 Ability to use pl.ant computers to evaluate system or component status.
(CFR: 41.10 145.12) 3.8 WE02 SI Termination /3
[Question 84]
EA2. Ability to determine and interpret the following as they apply to the (SI Termination)
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
4.2 1
(CFR: 43.5/45.13)
WE10 Natural Circulation with Steam Void in Vessel with/without RVLlS 14
[Question 85]
2.2.38 Knowledge of conditions and limitations in the facility license.
(CFR: 41.7/41.10 14:3.1/45.13) 4.5 ory Point Totals:
Group Point Total:
4 NUREG-1021, Revision 9 Supplement 1 SRO Page 3 of 6 FENoe Facsimile Rev. 0
ES-401 PWR Examination Outline Form ES-401*2 Plant Systems
- Tier 2/Group 1 (SRO)
~==================~==r=r=T=~9F=F=
System # 1Name K K KIA Topic(s)
IR 1 2 010 Pressurizer Pressure A2 Ability to (a) predict the impacts of the 4.2 Control System (PZR PCS) following malfunctions or operations on the
[Question 86]
PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.03 PORV failures (CFR: 41.5 143.5 145.3/45.13) 012 Reactor Protection System
[Question 87]
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use 3.7 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.07 Loss of de control power (CFR: 41.5 14~L5 145.3/45.5) 013 Engineered Safety Features Actuation System (ESFAS) 2.2.37 Ability to determine operability and/or availability of safety related equipment.
4.6 1
[Question 88]
(CFR: 41.7/43.5/45.12) 039 Main and Reheat Steam A2 Ability to (a) predict the impacts of the 3.6 System (MRSS) following malfunctions or operations on the
[Question 89]
MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.05 Increasing steam demand, its relationship to increases in reactor power 061 Auxiliary 1Emergency Feedwater (APN) System
[Question 90]
2.1.7 to evaluate ance make operational judgments based on operating char:acteristics, reactor behavior, and instrument interpretation.
4.7 (CFR: 41.5/ 4:~.5/45.12 145.13)
Group Point Total:
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ES401 PWR Examination Outline Form ES401-2 Plant Systems
- Tier 2/GI'oup 2(SRO)
=9~==========================~==~~
System # 1 Name KKK KIA Topic(s) lR 123 A2 Ability to (a) predict the impacts of the 3.5*
015 Nuclear Instrumentation following malfunctions or operations on the NIS; System and (b) based on those predictions, use
[Question 91]
procedures to correct. control, or mitigate the consequences of those malfunctions or operations:
A2.02 Faulty or erratic operation of detectors or compensating components CFR: 41.5/43.5/45.3/45.5 K4 Knowledge of design feature(s) and/or 034 Fuel Handling Equipment 3.4 1
interlock(s) which provide for the following:
System (FHES)
K4.01 Fuel protection from binding and
[Question 92]
dropping (CFR: 41.7) 041 Steam Dump System (50S) 2.1.31 Ability to locate control room switches, 4.3 and Turbine Bypass Control controls, and indications, and to determine that they correctly reflect the desired plant lineup.
[Question 93]
(CFR: 41.10/45.12)
KIA Category Point Totals:
Group Point Total:
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Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 BVPS UNIT 2 SRO Date of Exam 9/24 thru 10/5 2012 SRO Only Category KJA#
Topic IR
- 1.
2.1.5 Ability to use procedures related to shift staffing, such as minimum 3.9 1
Conduct crew complement, overtime limitations, etc.
of Operations
[Question 94] (CFR: 41.10/43.5/45.12) 2.1.32 Ability to explain and apply system limits and precautions.
4.0 1
[Question 95] (CFR: 41.10 143.2 145.12)
Subtotal 2
- 2.
2.2.20 Knowledge of the process for managing troubleshooting activities.
Equipment
[Question 96] (CFR: 41.10 143.5/45.13)
Control Subtotal 1
- 3.
2.3.6 Ability to approve release permits.
1 Radiation
[Question 97] (CFR: 41.13 143.4 145.10)
Control 2.3.11 Ability to control radiation releases.
4.3
[Question 98] (CFR: 41.11 143.4 145.10)
Subtotal 2
~.
2.4.20 Knowledge of the operational implications of EOP warningls, 1
Emergency cautions, and notes.
Proceduresl
[Question 99] (CFR: 41.10/43.5/45.13)
Plan 2.4.41 Knowledge of the emergency action level thresholds and 4.6 1
classifications.
[Question 100] (CFR: 41.10/43.5/45.11)
Subtotal 2
Tier 3 Point Total 7
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ES-401 Record 0 f R'eJected KIA s F orm ES-4014 Facility: BVPS UNIT 2 Date of Exam 9/24 thru 10/5 2012 Operating Test No.: 2LOT8 NRC
- ier I Randomly Reason for Rejection I Group Selected KIA RO OUTLINE 1/1 0000222.2.6 Question # 4; 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. Randomly reselected 2.2.39 from same generic group.
1/1 000057 2.4.19 Question # 12; 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. Randomly reselected 2.4.4 from same
- generic group.
1/2 0000762.1.5 Question # 23; 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. Randomly reselected 2.1.31 from same generic group.
2/1 025 K4.02 Question # 30; Beaver Valley Unit 2 does noj[ have ice condensers. Randomly reselected 004 K4.14 as a replacement.
2/1 0052.1.5 Question # 31; 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. Randomly reselected 2.1.32 from same generic group.
2/1 025 A4.02 Question # 44; Beaver Valley Unit 2 does noit have ice condensers. Randomly reselected 061 A 1.01 as a replacement.
2/1 0632.1.39 Question # 47; 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. Randomly reselected 2.1.7 from same generic group.
2/2 0272.2.37 Question # 57; Beaver Valley Unit 2 has removed the CNMT Iodine Removal system and replaced it with a passive sodium tetraborate basket system.
Randomly reselected the 015 system as a replacement.
2/2 028 K1.01 Question # 60; Beaver Valley Unit 2 has removed the Hydrogen Recombiner system. Hydrogen Recombiner functions are now directed by the TSC and the equipment that will be used is on skid that will be hooked-up and utilized as necessary. Randomly reselected 041 K1.02 as a replacement.
2/1 062 K4.05 Question # 46; KA is too similar to 062 A4.07 KA that was randomly selected for question # 45. Randomly reselected 062 K4.10 as a replacement.
1/1 WE042.1.27 Question # 16; Knowledge of system purpose/function does not apply to a LOCA outside containment. Randomly reselected 2.1.23 from same generic group 1/2 WE08 EK3.2 Question # 25; Unable to construct a discriminatory question about the reason for having procedures to address PTS. Randomly reselected EK3.1 for the same Emergency Plant evolution.
2/1 007 K5.02 Question # 34; The PRT is no longer used at Beaver Valley Unit 2 during PZR steam bubble formation. Randomly reselected A3.01 as a replacement 2/1 103 A2.04 Question 54; Beaver Valley Unit 2 does not have any operations procedures that address how to correct a containment evacuation that has failed. This would be dealt with through the work order process. Randomly reselected A2.03 as a II replacement.
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II ES-401 Facility: BVPS UNIT 2 2/2 055 A3.03 1/1 000007 2.4.26 1/2 0000742.1.36 2/1 0132.3.15 2/1 041 2.3.11 1/1 056 AA2.58 2/2 015 A2.05 1/1 000026 2.1.25 Record 0 f R*eJected KIA s Form ES-401-4 Date of Exam 9/24 thru 10/52012 Operating Test No.: 2LOT8 NRC Question # 63; Beaver Valley Unit 2 does not have any automatic diversion of CARS exhaust. Re-alignment of CARS exhaust is done manually. Randomly reselected K1.06 as a replacement.
SRO OUTLINE Question # 76; 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. Handomly reselected 2.4.20 from same generic group.
Question # 83; 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. Handomly reselected 2.1.19 from same generic group.
Question # 88; 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. Handomly reselected 2.2.37 as a replacement.
Question # 93; 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. Handomly reselected 2.1.31 as a replacement.
Question # 79; Unable to construct a discriminatory question at the SRO level around the air compressor indicating light status during a Loss of Offsite Power.
Randomly reselected AA2.45 as a replacemE~nt.
Question # 91, Unable to construct a discriminatory question at the SRO level around the impact of core voiding on the NIS and the procedural guidance to correct or mitigate. Randomly reselected A2.02 as a replacement.
Question # 78,, Unable to construct a discriminatory question at the SRO level around the use of graphs and charts during CI loss of CCW. Randomly reselected 2.1.20 as a replacement.
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