NTD-21-060, Draft Written Examination and Operating Test Outlines (Folder 2)
| ML22175A183 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/03/2021 |
| From: | Hargrave W Public Service Enterprise Group |
| To: | Joseph Demarshall Operations Branch I |
| Shared Package | |
| ML21020A061 | List: |
| References | |
| EPID L-2022-OLL-0002, NTD-21-060 | |
| Download: ML22175A183 (45) | |
Text
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
Date of Examination:
Initials Item Task Description a
b*
c**
- 1.
R,J
w b.
Assess whether the outline was systematically and randomly prepared in accordance with
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Section D.1 of ES-401 or ES-401 N and whether all KIA categories are appropriately sampled.
I
(( IJ -
T c.
Assess whether the outline overemphasizes any systems, evolutions, or generic topics.
T E
cl. Assess whether the justifications for deselected or rejected KIA statements are appropriate.
R t/:8 N
- 2.
a.
Using Form ES-301-5, verify that the proposed scenario sets cover the required number of R w fiJ normal evolutions, instrument and component failures, technical specifications, and major s
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b.
Assess whether there are enough scenario sets (and spares) to test the projected number and u
mix of applicants in accordance with the expected crew composition and rotation.!:lchedule
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without compromising exam integrity, and ensure that each applicant can be tested using at A
least one new or significantly modified scenario, that no scenarios are duplicated from the T
applicants' audit test(s), and that scenarios will not be repeated on subsequent days.
0
- c. To the extent possible, assess whether the outline(s) conforms with the qualitative and jJ R
quantitative criteria specified on Form ES-301-4 and described in Appendix D and in R u Section D.5, "Specific Instructions for the 'Simulator Operating Test,"' of ES-301 (including overlap).
- 3.
- a. Verify that the systems walkthrough outline meets the criteria specified on Form ES-301-2:
(1)
The outline(s) contains the required number of control room and in-plant tasks distributed among the safety functions as specified on the form.
R. LI /iJ A
(2) Task repetition from the last two NRC examinations is within the limits specified on the form.
L (3)
No tasks are duplicated from the applicant's audit test(s).
(4)
The number of new or modified tasks meets or exceeds the minimums specified on the form.
T (5) The number of alternate-path, low-power, emergency, and radiologically controlled area H
tasks meets the criteria on the form.
R
()'
0
- b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:
Q. u u
(1) The tasks are distributed among the topics as specified on the form.
G (2)
At least one task is new or significantly modified.
H (3)
No more than one task is repeated from the last two NRC licensing examinations.
C.
Determine whether there are enough different outlines to test the projected number and mix of Cl
applicants and ensure that no items are duplicated on subsequent days.
- 4.
- a. Assess whether plant-specific priorities (including probabilistic risk assessment and individual fl., IJ J!;*
plant examination insights) are covered in the appropriate exam sections.
G
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- b. Assess whether the 10 CFR 55.41, 55.43, and 55.45 sampling is appropriate.
N Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5.
u ttJJ E
c.
R d.
Check for duplication and overlap among exam sections and the last two NRC exams.
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(<. \\) #J*
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- e. Check the entire exam for balance of coverage.
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
{c. V -PJ.
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- a. Author
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- b. Facility Reviewer (*)
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- c. NRC's Chief Examiner (#) -J.o.re,,,0/, li'M.tLc,,l Al /4",.,. g J,"),
ct"1<-lJ NRC Supervisor ihdt. roJ J... ek' /) J 1_,,fJ,L \\ r./
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- d.
- Not applicable for NRG-prepared examination outlines.
- The independent NRC reviewer initials items in column "c"; the chief examiner's concurrence is required.
ES-201, Page 30 of 32 Salem 2/14/2022
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Salem Date of Examination:
2/14/2022 Examination Level: RO SRO IZI Operating Test Number:
20-01 Administrative Topic (see Type Describe activity to be performed Note)
Code*
Determine which ECCS pumps can be stopped to maintain minimum Conduct of Operations required injection flow IAW 2-EOP-LOCA-5, step 16.1, Figure 1 R,P
[2.1. 7, SRO-4. 7: Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.]
Determine the amount of the time to borate for 3 stuck control rods and Conduct of Operations evaluate final BAST levels to determine any applicable TS LCO(s) and R,M action(s). (modified to add TS evaluation and required action)
[2.1.20, SRO-4.6: Ability to interpret and execute procedure steps]
Review and approve a completed Containment Ventilation Valve surveillance.
Equipment Control R,N
[2.2.12, SRO-4.1: Knowledge of surveillance procedures]
Radiation Control R,M Emergency Plan R,N Determine personnel exposure and required authorizations for work in a radiologically control area IAW RP-AA-463 (Modified for different room entry)
[2.3.4, SRO-3.7: Knowledge of radiation exposure limits under normal and emeraency conditions]
Classify an Event and Determine PARs (Time Critical)
[2.4.41, SRO-4.6: Knowledge of the emergency action level thresholds and classifications}
NOTE:
All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; ::; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (2! 1)
(P)revious 2 exams {:5 1, randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Salem Date of Examination:
2/14/2022 Exam Level: RO IX]
SRO-I SRO-U Operating Test Number:
20-01 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*
Safety (KIA, Importance RO/SRO)
Function
- a. Control Rod exercise surveillance (001, A2.11, 4.4/4. 7) Alternate Path -
A,D,P,S 1
Control rods continue to insert after placing in Auto & Manual requiring Rx Trip.
- b. Perform manual make up to VCT (004, A4.04, 3.2/3.6)
D,S 2
- c. Isolate ECCS Accumulators in EOP-LOCA-1 (006, A3.01 4.0/3.9) Alternate A,D,E,L,S 3
Path - SJ54 fails to close requiring operator to vent accumulator.
- d. Perform Bleed and Feed IAW 2-EOP-FRHS-1 (002, A2.04, 4.3/4.6) Alternate A,D,E,L,P,S 4-Pri Path - Only one PORV opens requiring operator to open all Rx head vents.
- e. Perform immediate actions for a loss of a SGFP IAW S2.OP-AB.CN-0001 A,E,N,S 4-Sec (059, A4.01 3.1/3.1) Alternate Path - automatic turbine runback fails to actuate and control rods fail to insert in Auto. Operator is required to manually initiate turbine runback and take control rods to manual and insert at 48 spm.
- f. Manually actuate Containment Spray (026, A2.03, 4.1/4.4) Alternate Path -
A,D,E,EN,P,S 5
Phase B valves fail to close automatically on a CS signal requiring operators to manually close valves.
3.1/3.4) Alternate Path - 21 Charging Pump trips on start requiring operator to start 22 Charging Pump.
- h. Perform a containment pressure relief IAW S2.OP-SO.CBV-0002 (103, A,E,N,S 8
A3.01, 3.9/4.2) Alternate Path - 2VC5 and 2VC6 dampers fail to close on high radiation signal requiring operator to manually close dampers to stop the radioactive release.
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. Transfer Rod Position Indication (IRPI) to Emergency Power Supply IAW D,E 1
S2.OP-AB.ROD-0004 (014, A2.02, 3.1/3.6)
- j. Locally open Reactor Trip breakers and M-G set breakers IAW S2.OP-AB.CR-D,E,L 7
0001 (012, A4.06, 4.3/4.3)
- k. Perform a radioactive liquid release IAW S2.OP-SO.WL-0001 (068, A4.03 D,R 9
3.9/3.8)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes I
Criteria for R /SRO-I/SRO-U
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Salem Date of Examination:
2/14/2022 Exam Level: RO SRO-I IZI SRO-U Operating Test Number:
20-01 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*
Safety (KIA, Importance RO/SRO)
Function
- a. Control Rod exercise surveillance (001, A2.11, 4.4/4. 7) Alternate Path -
A,D,P,S 1
Control rods continue to insert after placing in Auto & Manual requiring Rx Trip.
- b. Perform manual make up to VCT (004, A4.04, 3.2/3.6)
D,S 2
- c. Isolate ECCS Accumulators in EOP-LOCA-1 (006, A3.01 4.0/3.9) Alternate A,D,E,L,S 3
Path - SJ54 fails to close requiring operator to vent accumulator.
- d. Perform Bleed and Feed IAW 2-EOP-FRHS-1 (002, A2.04, 4.3/4.6) Alternate A,D,E,L,P,S 4-Pri Path - Only one PORV opens requiring operator to open all Rx head vents.
- e. Perform immediate actions for a loss of a SGFP IAW S2.OP-AB.CN-0001 A,E,N,S 4-Sec (059, A4.01 3.1/3.1) Alternate Path - automatic turbine run back fails to actuate and control rods fail to insert in Auto. Operator is required to manually initiate turbine runback and take control rods to manual and insert at 48 spm.
- f. Manually actuate Containment Spray (026, A2.03, 4.1/4.4) Alternate Path -
A,D,E,EN,P,S 5
Phase B valves fail to close automatically on a CS signal requiring operators to manually close valves.
- h. Perform a containment pressure relief IAW S2.OP-SO.CBV-0002 (103, A,E,N,S 8
A3.01, 3.9/4.2) Alternate Path - 2VC5 and 2VC6 dampers fail to close on high radiation signal requiring operator to manually close dampers to stop the radioactive release.
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. Transfer Rod Position Indication (IRPI) to Emergency Power Supply IAW D,E 1
S2.OP-AB.ROD-0004 (014, A2.02, 3.1/3.6)
- j. Locally open Reactor Trip breakers and M-G set breakers IAW S2.OP-AB.CR-D,E,L 7
0001 (012, A4.06, 4.3/4.3)
- k. Perform a radioactive liquid release IAW S2.OP-SO.WL-0001 (068, A4.03 D,R 9
3.9/3.8)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes I
Criteria for R /SRO-I/SRO-U
ES-401 PWR Examination Outline Form ES-401-2 Facility: Salem Nuclear Power Plant Date of Exam: February 14 - 24, 2022 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
Total A2 G*
Total
- 1.
Emergency and Abnormal Plant Evolutions 1
3 2
3 N/A 4
3 N/A 3
18 3
3 6
2 1
2 2
2 1
1 9
2 2
4 Tier Totals 4
4 5
6 4
4 27 5
5 10
- 2.
Plant Systems 1
2 2
4 3
2 2
4 3
2 2
2 28 3
2 5
2 0
0 1
2 1
0 1
1 1
2 1
10 0
1 2
3 Tier Totals 2
2 5
5 3
2 5
4 3
4 3
38 4
4 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 2
2 3
2 2
1 2
Note: 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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 K/A statements.
4.
Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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 a category 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 K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 02 EK2.02 - Knowledge of the interrelations between a reactor trip and the following: Breakers, relays and disconnects.
(CFR: 41.7 / 45.7) 2.6 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 02 AK2.02 - Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Sensors and detectors.
(CFR 41.7 / 45.7) 2.7 2
000009 (EPE 9) Small Break LOCA / 3 08 EA1.08 - Ability to operate and monitor the following as they apply to a small break LOCA: Containment isolation system.
(CFR: 41.7 / 45.5 / 45.6) 4.0 3
000011 (EPE 11) Large Break LOCA / 3 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.
(CFR: 41.8 / 41.10 / 45.3) 4.1 4
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 03 AK3.03 - Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Sequence of events for manually tripping reactor and RCP as a result of an RCP malfunction.
(CFR 41.5,41.10 / 45.6 / 45.13) 3.7 5
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 04 AA1.04 - Ability to operate and/or monitor the following as they apply to the Loss of Reactor Coolant Makeup: Speed demand controller and running indicators (positive displacement pump).
(CFR 41.7 / 45.5 / 45.6) 3.3 6
000025 (APE 25) Loss of Residual Heat Removal System / 4 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Isolation of RHR low-pressure piping prior to pressure increase above specified level.
(CFR 41.5,41.10 / 45.6 / 45.13) 3.3 7
000026 (APE 26) Loss of Component Cooling Water / 8 04 AA2.04 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The normal values and upper limits for the temperatures of the components cooled by CCW.
(CFR: 43.5 / 45.13) 2.5 8
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 02.
44 G2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5 / 43.5 / 45.12) 4.2 9
000029 (EPE 29) Anticipated Transient Without Scram / 1 04.
06 G2.4.6 - Knowledge of EOP mitigation strategies.
(CFR: 41.10 / 45.3 / 45.13) 3.7 10 000038 (EPE 38) Steam Generator Tube Rupture / 3 18 EA1.18 - Ability to operate and monitor the following as they apply to a SGTR: S/G blowdown valve indicators.
(CFR: 41.7 / 45.5 / 45.6) 4.0 11 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Steam Line Rupture:
Operation of steam line isolation valves.
(CFR 41.5,41.10 / 45.6 / 45.13) 4.2 12 000054 (APE 54; CE E06) Loss of Main Feedwater /4 01 AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break).
(CFR 41.8 / 41.10 / 45.3) 4.1 13 000055 (EPE 55) Station Blackout / 6
ES-401 3
Form ES-401-2 000056 (APE 56) Loss of Offsite Power / 6 04 AK1.04 - Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: Definition of saturation conditions, implication for the systems.
(CFR 41.8 / 41.10 / 45.3) 3.1 14 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 01 AA2.01 - Ability to determine and interpret the following as they apply to the Loss of DC Power:
That a loss of dc power has occurred; verification that substitute power sources have come on line.
(CFR: 43.5 / 45.13) 3.7 15 000062 (APE 62) Loss of Nuclear Service Water / 4 02 AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The cause of possible SWS loss.
(CFR: 43.5 / 45.13) 2.9 16 000065 (APE 65) Loss of Instrument Air / 8 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 01.
25 G2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.
(CFR: 41.10 / 43.5 / 45.12) 4.2 17 (W E04) LOCA Outside Containment / 3 01 W E04: EA1.1 - Ability to operate and/or monitor the following as they apply to the (LOCA Outside Containment): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(CFR: 41.7 / 45.5 / 45.6) 4.0 18 (W E11) Loss of Emergency Coolant Recirculation / 4 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 K/A Category Totals:
3 2
3 4
3 3
Group Point Total:
18
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 03 AA2.03 - Ability to determine and interpret the following as they apply to the Dropped Control Rod: Dropped rod, using in-core /
ex-core instrumentation, in-core or loop temperature measurements.
(CFR: 43.5 / 45.13) 3.6 19 000005 (APE 5) Inoperable/Stuck Control Rod / 1 02 AK2.02 - Knowledge of the interrelations between the Inoperable / Stuck Control Rod and the following: Breakers, relays, disconnects, and control room switches.
(CFR 41.7 / 45.7) 2.5 20 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 01 AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Pressurizer Level Control Malfunctions and the following:
PZR reference leak abnormalities.
(CFR 41.8 / 41.10 / 45.3) 2.8 21 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 04.
46 G2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.
(CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 22 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 02 AK2.02 - Knowledge of the interrelations between the Accidental Gaseous Radwaste Release and the following:
Auxiliary building ventilation system.
(CFR 41.7 / 45.7) 2.7 23 000061 (APE 61) Area Radiation Monitoring System Alarms
/ 7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /
4 29 EA1.29 - Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: Quench tank temperature, pressure, and level instrumentation.
(CFR: 41.7 / 45.5 / 45.6) 3.4 24 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3
ES-401 5
Form ES-401-2 (W E01 & E02) Rediagnosis & SI Termination / 3 03 W E01: EK3.3 - Knowledge of the reasons for the following responses as they apply to the (Reactor Trip or Safety Injection/Rediagnosis):
Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
(CFR: 41.5 / 41.10 / 45.6 / 45.13) 3.5 25 (W E13) Steam Generator Overpressure / 4 02 W E13: EK3.2 - Knowledge of the reasons for the following responses as they apply to the (Steam Generator Overpressure):
Normal, abnormal and emergency operating procedures associated with (Steam Generator Overpressure).
(CFR: 41.5 / 41.10 / 45.6 / 45.13) 2.9 26 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05) Emergency Diesel Actuation / 6 (BW A07) Flooding / 8 (BW E03) Inadequate Subcooling Margin / 4 (BW E08; W E03) LOCA CooldownDepressurization / 4 01 W E03: EA1.1 - Ability to operate and/or monitor the following as they apply to the (LOCA Cooldown and Depressurization):
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(CFR: 41.7 / 45.5 / 45.6) 4.0 27 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals:
1 2
2 2
1 1
Group Point Total:
9
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 003 (SF4P RCP) Reactor Coolant Pump 07 K4.07 - Knowledge of RCPS design feature(s) and/or interlock(s) which provide for the following: Minimizing RCS leakage (mechanical seals).
(CFR: 41.7) 3.2 28 004 (SF1; SF2 CVCS) Chemical and Volume Control 11 01.
32 G2.1.32 - Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12)
K4.11 - Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: Temperature/pressure control in letdown line: prevent boiling, lifting reliefs, hydraulic shock, piping damage, and burst.
(CFR: 41.7) 3.8 3.1 29 30 005 (SF4P RHR) Residual Heat Removal 01 02 K3.01 - Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: RCS.
(CFR: 41.7 / 45.6)
K5.02 - Knowledge of the operational implications of the following concepts as they apply to the RHRS: Need for adequate subcooling.
(CFR: 41.5 / 45.7) 3.9 3.4 31 32 006 (SF2; SF3 ECCS) Emergency Core Cooling 06 K5.06 - Knowledge of the operational implications of the following concepts as they apply to ECCS: Relationship between ECCS flow and RCS pressure.
(CFR: 41.5 / 45.7) 3.5 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 03 A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Overpressurization of the PZR.
(CFR: 41.5 /43.5/ 45.3/45.13) 3.6 34 008 (SF8 CCW) Component Cooling Water 04 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low surge tank level.
(CFR: 41.5 /43.5/ 45.3/45.13)
K1.04 - Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems: RCS, in order to determine source(s) of RCS leakage into the CCWS.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.2 3.3 35 36 010 (SF3 PZR PCS) Pressurizer Pressure Control 07 A1.07 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including:
RCS pressure.
(CFR: 41.5 / 45.5) 3.7 37
ES-401 7
Form ES-401-2 012 (SF7 RPS) Reactor Protection 02 K3.02 - Knowledge of the effect that a loss or malfunction of the RPS will have on the following: T/G.
(CFR: 41.7 / 45.6) 3.2 38 013 (SF2 ESFAS) Engineered Safety Features Actuation 07 01 K6.01 - Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors.
(CFR: 41.7 / 45.5 to 45.8)
K4.07 - Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following: Power supply loss.
(CFR: 41.7) 2.7 3.7 39 40 022 (SF5 CCS) Containment Cooling 04 A4.04 - Ability to manually operate and/or monitor in the control room: Valves in the CCS.
(CFR: 41.7 / 45.5 to 45.8) 3.1 41 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 01 K2.01 - Knowledge of bus supplies to the following: Containment spray pumps.
(CFR: 41.7) 3.4 42 039 (SF4S MSS) Main and Reheat Steam 07 A4.07 - Ability to manually operate and/or monitor in the control room: Steam dump valves.
(CFR: 41.7 / 45.5 to 45.8) 2.8 43 059 (SF4S MFW) Main Feedwater 03 02 A1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including:
Power level restrictions for operation of MFW pumps and valves.
(CFR: 41.5 / 45.5)
A3.02 - Ability to monitor automatic operation of the MFW, including:
Programmed levels of the S/G.
(CFR: 41.7 / 45.5) 2.7 2.9 44 45 061 (SF4S AFW) Auxiliary/Emergency Feedwater 01 K6.01 - Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Controllers and positioners.
(CFR: 41.7 / 45.7) 2.5 46 062 (SF6 ED AC) AC Electrical Distribution 02 K3.02 - Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: ED/G.
(CFR: 41.7 / 45.6) 4.1 47 063 (SF6 ED DC) DC Electrical Distribution 02 01.
30 K3.02 - Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: Components using DC control power.
(CFR: 41.7 / 45.6)
G2.1.30 - Ability to locate and operate components, including local controls.
(CFR: 41.7 / 45.7) 3.5 4.4 48 49 064 (SF6 EDG) Emergency Diesel Generator 08 A1.08 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: Maintaining minimum load on ED/G (to prevent reverse power).
(CFR: 41.5 / 45.5) 3.1 50
ES-401 8
Form ES-401-2 073 (SF7 PRM) Process Radiation Monitoring 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.
(CFR: 41.5 /43.5/ 45.3/45.13) 2.7 51 076 (SF4S SW) Service Water 02 A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:
Reactor and turbine building closed cooling water temperatures.
(CFR: 41.5 / 45.5) 2.6 52 078 (SF8 IAS) Instrument Air 01 K2.01 - Knowledge of bus power supplies to the following: Instrument air compressor.
(CFR: 41.7) 2.7 53 103 (SF5 CNT) Containment 01 01 A3.01 - Ability to monitor automatic operation of the containment system, including: Containment isolation.
(CFR: 41.7 / 45.5)
K1.01 - Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: CCS.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.9 3.6 54 55 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:
2 2
4 3
2 2
4 3
2 2
2 Group Point Total:
28
ES-401 9
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 001 (SF1 CRDS) Control Rod Drive 04 K5.04 - Knowledge of the following operational implications as they apply to the CRDS: Rod insertion limits.
(CFR: 41.5 / 45.7) 4.3 56 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 07 K4.07 - Knowledge of NIS design feature(s) and/or interlock(s) which provide for the following: Permissives.
(CFR: 41.7) 3.7 57 016 (SF7 NNI) Nonnuclear Instrumentation 12 K3.12 - Knowledge of the effect that a loss or malfunction of the NNIS will have on the following: S/G.
(CFR: 41.7 / 45.6) 3.4 58 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 03 A4.03 - Ability to manually operate and/or monitor in the control room: CIRS fans.
(CFR: 41.7 / 45.5 to 45.8) 3.3 59 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 01 A4.01 - Ability to manually operate and/or monitor in the control room: HRPS controls.
(CFR: 41.7 / 45.5 to 45.8) 4.0 60 029 (SF8 CPS) Containment Purge 01 A3.01 - Ability to monitor automatic operation of the Containment Purge System including:
CPS isolation.
(CFR: 41.7 / 45.5) 3.8 61 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 02 K4.02 - Knowledge of design feature(s) and/or interlock(s) which provide for the following:
Fuel movement.
(CFR: 41.7) 2.5 62 035 (SF4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 01 A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SDS controls including: T-ave., verification above low/low setpoint.
(CFR: 41.5 / 45.5) 2.9 63 045 (SF4S MTG) Main Turbine Generator 01.
23 G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.3 64 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 04 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.
(CFR: 41.5 /43.5/ 45.3/45.13) 2.6 65 068 (SF9 LRS) Liquid Radwaste
ES-401 10 Form ES-401-2 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 (SF8 FPS) Fire Protection 050 (SF9 CRV*) Control Room Ventilation K/A Category Point Totals:
0 0
1 2
1 0
1 1
1 2
1 Group Point Total:
10
ES-401 11 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space Accident / 3 04.
18 G2.4.18 - Knowledge of the specific bases for EOPs.
(CFR: 41.10 / 43.1 / 45.13) 4.0 76 000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 000025 (APE 25) Loss of Residual Heat Removal System / 4 000026 (APE 26) Loss of Component Cooling Water / 8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main Feedwater /4 000055 (EPE 55) Station Blackout / 6 04 EA2.04 - Ability to determine and interpret the following as they apply to a Station Blackout:
Instruments and controls operable with only dc battery power available.
(CFR: 43.5 / 45.13) 4.1 77 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 02.
25 G2.2.25 - knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits (CFR: 41.5 / 41.7 / 43.2) 4.2 78 000058 (APE 58) Loss of DC Power / 6 000062 (APE 62) Loss of Nuclear Service Water / 4 000065 (APE 65) Loss of Instrument Air / 8 04.
31 G2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.
(CFR: 41.10 / 45.3) 4.1 79 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 01 W E11: EA2.1 - Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(CFR: 43.5 / 45.13) 4.2 80
ES-401 12 Form ES-401-2 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 02 W E05: EA2.2 - Ability to determine and interpret the following as they apply to the (Loss of Secondary Heat Sink): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
(CFR: 43.5 / 45.13) 3.7 81 K/A Category Totals:
0 0
0 0
3 3
Group Point Total:
6
ES-401 13 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 08 AA2.08 - Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation:
Intermediate range channel operability.
(CFR: 43.5 / 45.13) 3.4 82 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms
/ 7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /
4 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 04.
41 W E16: G2.4.41 - Knowledge of the emergency action level thresholds and classifications.
(CFR: 41.10 / 43.5 / 45.11) 4.6 83 (BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05) Emergency Diesel Actuation / 6 (BW A07) Flooding / 8 (BW E03) Inadequate Subcooling Margin / 4
ES-401 14 Form ES-401-2 (BW E08; W E03) LOCA CooldownDepressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 02 W E10: EA2.2 - Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
(CFR: 43.5 / 45.13) 3.9 84 (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 04.
21 W E08: G2.4.21 - Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
(CFR: 41.7 / 43.5 / 45.12) 4.6 85 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals:
0 0
0 0
2 2
Group Point Total:
4
ES-401 15 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 003 (SF4P RCP) Reactor Coolant Pump 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP.
(CFR: 41.5 /43.5/ 45.3/45.13) 3.9 86 004 (SF1; SF2 CVCS) Chemical and Volume Control 005 (SF4P RHR) Residual Heat Removal 006 (SF2; SF3 ECCS) Emergency Core Cooling 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 008 (SF8 CCW) Component Cooling Water 010 (SF3 PZR PCS) Pressurizer Pressure Control 012 (SF7 RPS) Reactor Protection 04.
30 G2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
(CFR: 41.10 / 43.5 / 45.11) 4.1 87 013 (SF2 ESFAS) Engineered Safety Features Actuation 022 (SF5 CCS) Containment Cooling 05 A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Major leak in CCS.
(CFR: 41.5 /43.5/ 45.3/45.13) 3.5 88 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 039 (SF4S MSS) Main and Reheat Steam 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)
Auxiliary/Emergency Feedwater 062 (SF6 ED AC) AC Electrical Distribution 063 (SF6 ED DC) DC Electrical Distribution 064 (SF6 EDG) Emergency Diesel Generator 02.
36 G2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
(CFR: 41.10 / 43.2 / 45.13) 4.2 89
ES-401 16 Form ES-401-2 073 (SF7 PRM) Process Radiation Monitoring 076 (SF4S SW) Service Water 01 A2.01 - 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: Loss of SWS.
(CFR: 41.5 /43.5/ 45.3/45.13) 3.7 90 078 (SF8 IAS) Instrument Air 103 (SF5 CNT) Containment 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:
0 0
0 0
0 0
0 3
0 0
2 Group Point Total:
5
ES-401 17 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant 02.
40 G2.2.40 - Ability to apply Technical Specifications for a system.
(CFR: 41.10 / 43.2 / 43.5 / 45.3) 4.7 91 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 04 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Misaligned rod.
(CFR: 41.5 /43.5/ 45.3/45.13) 3.9 92 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 (SF8 FPS) Fire Protection 02.
38 G2.2.38 - Knowledge of conditions and limitations in the facility license.
(CFR: 41.7 / 41.10 / 43.1 / 45.13) 4.5 93 050 (SF9 CRV*) Control Room Ventilation K/A Category Point Totals:
0 0
0 0
0 0
0 1
0 0
2 Group Point Total:
3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Salem Nuclear Power Plant Date of Exam: February 14 - 24, 2022 Category K/A #
Topic RO SRO-only IR IR
- 1. Conduct of Operations 2.1.1 G2.1.1 - Knowledge of conduct of operations requirements.
(CFR: 41.10 / 45.13) 3.8 66 2.1.3 G2.1.3 - Knowledge of shift or short-term relief turnover practices.
(CFR: 41.10 / 45.13) 3.7 67 2.1.26 G2.1.26 - Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
(CFR: 41.10 / 45.12) 3.4 68 2.1.35 G2.1.35 - Knowledge of fuel-handling responsibilities of SROs.
(CFR: 41.10 / 43.7) 3.9 94 2.1.37 G2.1.37 - Knowledge of procedures, guidelines, or limitations associated with reactivity management.
(CFR: 41.1 / 43.6 / 45.6) 4.6 95 Subtotal 3
2
- 2. Equipment Control 2.2.3 G2.2.3 - (multi-unit license) Knowledge of the design, procedural, and operational differences between units.
(CFR: 41.5 / 41.6 / 41.7 / 41.10 / 45.12) 3.8 69 2.2.13 G2.2.13 - Knowledge of tagging and clearance procedures.
(CFR: 41.10 / 45.13) 4.1 70 2.2.11 G2.2.11 - Knowledge of the process for controlling temporary design changes.
(CFR: 41.10 / 43.3 / 45.13) 3.3 96 2.2.17 G2.2.17 - Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.
(CFR: 41.10 / 43.5 / 45.13) 3.8 97 Subtotal 2
2
- 3. Radiation Control 2.3.4 G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.
(CFR: 41.12 / 43.4 / 45.10) 3.2 71 2.3.12 G2.3.12 - Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(CFR: 41.12 / 45.9 / 45.10) 3.2 72 2.3.6 G2.3.5 - Ability to approve release permits.
(CFR: 41.13 / 43.4 / 45.10) 3.8 98 Subtotal 2
1
- 4. Emergency Procedures/Plan 2.4.17 G2.4.17 - Knowledge of EOP terms and definitions.
(CFR: 41.10 / 45.13) 3.9 73 2.4.39 G2.4.39 - Knowledge of RO responsibilities in emergency plan implementation.
(CFR: 41.10 / 45.11) 3.9 74
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 2.4.43 G2.4.43 - Knowledge of emergency communications systems and techniques.
(CFR: 41.10 / 45.13) 3.2 75 2.4.26 G2.4.26 - Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.
(CFR: 41.10 / 43.5 / 45.12) 3.6 99 2.4.38 G2.4.38 - Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.
(CFR: 41.10 / 43.5 / 45.11) 4.4 100 Subtotal 3
2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Page 1 of 3 Tier / Group Randomly Selected K/A Reason for Rejection Tier 1 / Group 1
000015 AK3.03 RO Q5 Overlap/balance of coverage concern with SRO Q86 regarding RCP Seal Malfunctions and High Seal-Leak Off Flows.
CHIEF EXAMINER randomly re-selected K/A AK2.08 to address the overlap/balance of coverage concern and to maintain K/A category balance within the outline.
AK2.08 - Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: CCWS. (IR 2.6)
Tier 1 / Group 1
000027 G2.2.44 RO Q9 Overlap/balance of coverage concern with RO Q37 regarding failure of the controlling Pressurizer Pressure Channel.
CHIEF EXAMINER randomly re-selected K/A AK3.03 to address the overlap/balance of coverage concern and to maintain K/A category balance within the outline.
AK3.03 - Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in AOP for PZR PCS malfunction. (IR 3.7)
Tier 1 / Group 1
000038 EA1.18 RO Q11 Facility was unable to develop an operationally valid and discriminating RO level question to test the selected K/A; i.e., Ability to operate and monitor the following as they apply to a SGTR: S/G blowdown valve indicators..
CHIEF EXAMINER randomly re-selected K/A EA1.33 to maintain K/A category balance within the outline.
EA1.33 - Ability to operate and monitor the following as they apply to a SGTR: Use of S/G for natural circulation cooldown. (IR 4.4)
Tier 1 / Group 1
000056 AK1.04 RO Q14 Facility was unable to develop an operationally valid and discriminating RO level question to test the selected K/A; i.e., Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: Definition of saturation conditions, implication for the systems.
CHIEF EXAMINER randomly re-selected K/A AA2.03 to maintain K/A category balance within the outline.
AA2.03 - Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Operational status of safety injection pump. (IR 3.8)
Tier 1 / Group 1
000077 G2.1.25 RO Q17 Facility was unable to develop an operationally valid and discriminating RO level question to test the combination of APE 77 (Generator Voltage and Electric Grid Disturbances) and the selected Generic K/A; i.e., Ability to interpret reference materials, such as graphs, curves, tables, etc.
CHIEF EXAMINER randomly re-selected K/A G2.1.27 to maintain K/A category balance within the outline.
G2.1.27 - Knowledge of system purpose and/or function. (IR 3.9)
Tier 1 / Group 2
000074 EA1.29 RO Q24 Facility was unable to develop an operationally valid and discriminating RO level question to test the selected K/A; i.e., Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: Quench tank temperature, pressure, and level instrumentation.
CHIEF EXAMINER randomly re-selected K/A EA1.06 to maintain K/A category balance within the outline.
EA1.06 - Ability to operate and monitor the following as they apply to a Inadequate Core Cooling: RCPs. (IR 3.6)
Tier 1 / Group 2
W E01 EK3.3 RO Q25 Facility was unable to develop an operationally valid and discriminating RO level question to test the selected K/A, Knowledge of the reasons for the following responses as they apply to the (Reactor Trip or Safety Injection/Rediagnosis): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
CHIEF EXAMINER randomly re-selected K/A EK3.2 to maintain K/A category balance within the outline.
EK3.2 - Knowledge of the reasons for the following responses as they apply to the (Reactor Trip or Safety Injection/Rediagnosis): Normal, abnormal, and emergency operating procedures associated with (Reactor Trip or Safety Injection/Rediagnosis). (IR 3.0)
ES-401 Record of Rejected K/As Form ES-401-4 Page 2 of 3 Tier 2 / Group 1
005 K5.02 RO Q32 Facility was unable to develop an operationally valid and discriminating RO level question to test the selected K/A; i.e., Knowledge of the operational implications of the following concepts as they apply to the RHRS: Need for adequate subcooling.
CHIEF EXAMINER randomly re-selected K/A K5.05 to maintain K/A category balance within the outline.
K5.05 - Knowledge of the operational implications of the following concepts as they apply to the RHRS: Plant response during solid plant pressure change due to the relative incompressibility of water. (IR 2.7)
Tier 2 / Group 1
059 A1.03 RO Q44 Overlap/balance of coverage concern between Main Feedwater System (059) K/A A1.03, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including: Power level restrictions for operation of MFW pumps and valves, and Control Room Systems JPM e for Safety Function 4 (Secondary System) on the Operating Test..
CHIEF EXAMINER randomly re-selected K/A K4.19 to address the overlap/balance of coverage concern and to maintain K/A category balance within the outline.
K4.19 - Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic feedwater isolation of MFW. (IR 3.2)
Tier 2 / Group 1
076 A1.02 RO Q52 Facility was unable to develop an operationally valid and discriminating RO level question to test the selected K/A; i.e., Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:
Reactor and turbine building closed cooling water temperatures.
CHIEF EXAMINER randomly re-selected K/A K1.16 to maintain K/A category balance within the outline.
K1.16 - Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: ESF. (IR 3.6)
Tier 2 / Group 2
029 A3.01 RO Q61 Facility was unable to develop an operationally valid and discriminating RO level question to test System 029 (Containment Purge) using the selected K/A; i.e., Ability to monitor automatic operation of the Containment Purge System including: CPS isolation.
CHIEF EXAMINER (a) randomly re-selected System 033 (Spent Fuel Pool Cooling) from amongst the available Tier 2/Group 2 Systems on the RO/SRO outlines to maintain balance of coverage, and (b) randomly re-selected K/A K1.05 to maintain K/A category balance within the outline.
K1.05 - Knowledge of the physical connections and/or cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems: RWST. (IR 2.7)
Tier 3 G2.2.3 RO Q69 Facility was unable to develop an operationally valid and discriminating RO level question that would test and maintain a plant-wide generic focus for the selected Tier 3 K/A, i.e.,
(multi-unit license) Knowledge of the design, procedural, and operational differences between units. (IR 3.6)
CHIEF EXAMINER randomly re-selected Generic K/A G2.2.6.
G2.2.6 - Knowledge of the process for making changes to procedures. (IR 3.0)
Tier 1 / Group 1
000008 G2.4.18 SRO Q76 Facility was unable to develop an operationally valid and discriminating SRO level question to test the combination of APE 8 (Pressurizer Vapor Space Accident) and the selected Generic K/A; i.e., Knowledge of the specific bases for EOPs.
CHIEF EXAMINER randomly re-selected EPE 29 (Anticipated Transient Without Scram) from amongst the available Tier 1/Group 1 Emergency and Abnormal Plant Evolutions on the RO/SRO outlines, to maintain balance of coverage. Retained Generic K/A G2.4.18 to ensure K/A category balance within the outline.
Tier 2 / Group 1
022 A2.05 SRO Q88 Facility was unable to develop an operationally valid and discriminating SRO level question to test System 022 (Containment Cooling) using the selected K/A; i.e., Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Major leak in CCS.
CHIEF EXAMINER (a) randomly re-selected System 078 (Instrument Air) from amongst the available Tier 2/Group 1 Systems on the RO/SRO outlines to maintain balance of coverage, and (b) randomly re-selected Generic K/A G2.2.44 to maintain K/A category balance within the outline.
G2.2.44 - Ability to interpret control room indications to verify the status and operation of a
ES-401 Record of Rejected K/As Form ES-401-4 Page 3 of 3 system, and understand how operator actions and directives affect plant and system conditions. (IR 4.4)