ML081200405
| ML081200405 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/24/2008 |
| From: | Division of Reactor Safety IV |
| To: | Entergy Operations |
| References | |
| 50-382/08-301 | |
| Download: ML081200405 (22) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Revision 9 Facility:
WATERFORD 3 Date of Examination:
3/24/2008 Examination Level (circle one):
RO / SRO Operating Test Number:
1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Perform a Shutdown Margin Calculation A1 Conduct of Operations R, M 2.1.23 Ability to perform specific and integrated plant procedures during all modes of plant operation.(3.9)
Determine Time to SDC (Condenser Inventory)
A2 Conduct of Operations R, M 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs and tables which contain performance data.(2.8)
Prepare an Equipment Tagout A3 Equipment Control R, M 2.2.13 Knowledge of tagging and clearance procedures.
(3.6)
Complete Pre-requisites for GDT Release A4 Radiation Control R, N 2.3.11 Ability to control radiation releases.(2.7)
Not selected Emergency Plan NOTE:
All items (5 total are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (d 3 for ROs; d for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (d 1; randomly selected)
(S)imulator
ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Revision 9 Facility:
WATERFORD 3 Date of Examination:
3/24/2008 Examination Level (circle one):
RO / SRO Operating Test Number:
1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Calculate Shutdown Margin with ONE Untrippable CEA A5 Conduct of Operations R, M 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs and tables which contain performance data.(3.1)
Determine Event Notification Requirements A6 Conduct of Operations R, N 2.1.2 Knowledge of operator responsibilities during all modes of plant operation. (4.0)
Approve an Equipment Tagout A7 Equipment Control R, M 2.2.13 Knowledge of tagging and clearance procedures.
(3.8)
Approve liquid Release Permit A8 Radiation Control P, R 2.3.6 Knowledge of the requirements for reviewing and approving release permits.(3.1)
Determine Protective Action Recommendations A9 Emergency Plan R, M 2.4.44 Knowledge of emergency plan protective action recommendations. (4.0)
NOTE:
All items (5 total are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (d 3 for ROs; d for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (d 1; randomly selected)
(S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9 Facility:
WATERFORD 3 Date of Examination:
3/24/2008 Exam Level (circle one):
RO Operating Test No.:
1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function S1 003-Start A Reactor Coolant Pump (Alternate Path)
P,A,D,L,S 4-P S2 015-Perform NI Startup Channel Functional Test (RO ONLY)
S,D,L 7
S3 064-Start and Load B EDG From CR S,M,A 6
S4 APE068-Perform BOP Immediate Actions On CR Evacuation S,M,A 8
S5 004-Blended Makeup To VCT Using Manual Mode S,D 1
S6 026-Align LPSI Pump To Replace Containment Spray Pump S,D,L 5
S7.
013-Verify SIAS Automatic Actions -Train A S, N, L, A 2
S8 071-Respond To Waste Gas Discharge High Activity N,S,A 9
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
P1 008-Restore Power to Dry Cooling Tower Sump Pumps During Control Room Evacuation and Loss of Offsite power R,L,D,E 8
P2 061-Reset EFW Pump AB Mechanical Overspeed During CR Evacuation With Fire L,D,E 4-S P3 062-Transfer AB SUPS From Alternate To Normal Power Supply N
6 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank d 9 / d 8 / d 4 (E)mergency or abnormal in-plant t 1 / t 1 / t 1 (L)ow-Power / Shutdown t 1 / t 1 / t 1 (N)ew or (M)odified from bank including 1(A) t 2 / t 2 / t 1 (P)revious 2 exams d 3 / d 3 / d 2 (randomly selected)
(R)CA t 1 / t 1 / t 1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9 Facility:
WATERFORD 3 Date of Examination:
3/24/2008 Exam Level (circle one):
SRO(I)
Operating Test No.:
1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function S1 003-Start A Reactor Coolant Pump (Alternate Path)
P,A,D,L,S 4-P S3 064-Start and Load B EDG From CR S,M,A 6
S4 APE068-Perform BOP Immediate Actions On CR Evacuation S,M,A 8
S5 004-Blended Makeup To VCT Using Manual Mode S,D 1
S6 026-Align LPSI Pump To Replace Containment Spray Pump S,D,L 5
S7.
013-Verify SIAS Automatic Actions -Train A S, N, L, A 2
S8 071-Respond To Waste Gas Discharge High Activity N,S,A 9
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
P1 008-Restore Power to Dry Cooling Tower Sump Pumps During Control Room Evacuation and Loss of Offsite power R,L,D,E 8
P2 061-Reset EFW Pump AB Mechanical Overspeed During CR Evacuation With Fire L,D,E 4-S P3 062-Transfer AB SUPS From Alternate To Normal Power Supply N
6 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank d 9 / d 8 / d 4 (E)mergency or abnormal in-plant t 1 / t 1 / t 1 (L)ow-Power / Shutdown t 1 / t 1 / t 1 (N)ew or (M)odified from bank including 1(A) t 2 / t 2 / t 1 (P)revious 2 exams d 3 / d 3 / d 2 (randomly selected)
(R)CA t 1 / t 1 / t 1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9 Facility:
WATERFORD 3 Date of Examination:
3/24/2008 Exam Level (circle one):
SRO (U)
Operating Test No.:
1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function S1 003-Start A Reactor Coolant Pump (Alternate Path)
P,A,D,L,S 4-P S7.
013-Verify SIAS Automatic Actions -Train A S, N, L, A 2
S8 071-Respond To Waste Gas Discharge High Activity N,S,A 9
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
P1 008-Restore Power to Dry Cooling Tower Sump Pumps During Control Room Evacuation and Loss of Offsite power R,L,D,E 8
P2 061-Reset EFW Pump AB Mechanical Overspeed During CR Evacuation With Fire L,D,E 4-S All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank d 9 / d 8 / d 4 (E)mergency or abnormal in-plant t 1 / t 1 / t 1 (L)ow-Power / Shutdown t 1 / t 1 / t 1 (N)ew or (M)odified from bank including 1(A) t 2 / t 2 / t 1 (P)revious 2 exams d 3 / d 3 / d 2 (randomly selected)
(R)CA t 1 / t 1 / t 1 (S)imulator
Appendix D Scenario Outline Form ES-D-1 EXAM SUBMITTAL Rev. 1 Scenario 2 Exam Submittal Rev 1 Facility:
WATERFORD 3 Scenario No.:
2 Op Test No.:
NRC Examiners:
Operators:
Initial Conditions:
x
~60% power, MOC, AB buses aligned to B side.
x A EFW pump OOS for seal replacement, A ACCW pump OOS for motor pm,.
Turnover:
x The A main feed pump outboard pump bearing vibration is elevated shortly after being placed in service and the crew is holding power while engineering evaluates.
Critical Task:
x Ensuring Reactivity control post trip by actions to initiate Diverse Trip.
x Ensuring feedwater to at least one SG utilizing Auxiliary Feedwater.
Event No.
Malf. No.
Event Type*
Event Description R - ATC 1
N -
BOP/SRO 15 MW/MIN downpower to remove A Main feed pump from service due to high vibration.
2 FW26B I - BOP, SRO Steam Generator Feedwater Flow instrument fails HIGH to FWCS #2.
C - ALL 3
RD02A72 TS - SRO Dropped Regulating group CEA, #72 and recovery.
CV12A2 TS - SRO VCT level inst., CVC-ILT-0227, fails LOW.
5 FW03B RP01A-D RP02A-D M - ALL Second main feed pump trips, reactor fails to auto or manually trip. Diverse Scram successful.
6 FW05 FW07B DI-08A07S09-1 C - BOP, SRO AB EFW pump trips on overspeed, B EFW pump fails to start, manual start is also unsuccessful.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description NRC Scenario 2 EXAM SUBMITTAL Rev. 1 Scenario 2 Exam Submittal Rev 1 Waterford 3 2008 NRC Scenario #2 The crew assumes the shift at ~60% power with elevated vibrations on the A FWPT outboard pump bearing which had just been placed in service. A team consisting of Engineering, Maintenance and Operations Management are in the field evaluating. Shortly after turnover the crew will be directed by the Ops Manager to reduce power to 50% at 15 MW/MIN and take the A FWPT OOS. As the crew arrives at 55% the vibrations worsen on indications in the control room and the team reports from the field that local vibrations are excessive on A FWPT. The crew will then trip the A FWPT and verify feedwater control systems restore SG levels automatically.
When SG levels have stabilized the Feed Flow input to the FWCS #2 fails high requiring the BOP to take manual control of the #2 SG feedwater control.
After the plant is stabilized then a regulating group CEA drops into the core. OP-901-102, CEA or CEDMCS Malfunction is entered and the CEA can be recovered.
When the CEA has been recovered or during the recovery the VCT level instrument, CVC-ILT-0227, fails low, causing the charging pump suction to shift to the RWSP. The crew implements OP-901-113, Volume Control Tank Makeup Control Malfunction.
After the crew completes the actions for the VCT level instrument failure the B FWPT trips and the crew attempts a manual Rx trip which is unsuccessful and the crew must utilize the Diverse Reactor Trip. If the crew doesnt manually trip the auto trips are also not successful.
Post-trip the AB EFW pump trips on overspeed when started and the B EFW pump failed to auto start and manual start is also unsuccessful.
EOP flowpath is OP-902-000, STANDARD POST TRIP ACTIONS, OP-902-006, LOSS OF MAIN FEEDWATER RECOVERY. Feedwater recovery success path is aligning Auxiliary feedwater IAW App 32 of OP-902-009 Standard Appendices.
If NRC Lead Examiner asks SRO candidate(s) to determine Emergency Plan classification, the candidate should determine the following: No E-Plan call unless auto trip indicated first. If auto trip failed, then manual Diverse Reactor Trip was used, then the call would be Alert (SA3),
Failure of Reactor Protection System instrumentation to complete or initiate an automatic reactor trip once a Reactor Protection System setpoint has been exceeded and manual trip was successful.
Appendix D Scenario Outline Form ES-D-1 EXAM SUBMITTAL REV 1 Scenario 3 Exam Submittal Rev 1 Facility:
WATERFORD 3 Scenario No.:
3 Op Test No.:
NRC Examiners:
Operators:
Initial Conditions:
x 25% power, MOC, AB buses aligned to B side.
Turnover:
x Plant startup is in progress after being off-line for 2 days.
Critical Task:
x Preventing RCS repressurization by actions to stabilize RCS temperature using the non-ESD SG.
x Isolating the SG with SG Tube Leak.
x Emergency borate or actuate SIAS due to uncontrolled cooldown.
Event No.
Malf.
No.
Event Type*
Event Description R - ATC 1
N - BOP, SRO Raising power from 25%.
2 RX14A I - ATC, SRO Controlling Pressurizer Pressure channel fails HIGH.
NI01F TS - SRO Safety Channel B ENI middle detector fails HIGH.
CC01A TS - SRO A CCW pump trip.
TS - SRO 5
SG01A SGTL ramp from 0 - 15 gpm over 10 minutes on SG #1.
6 MS13A M - ALL ESDE on #1 SG outside containment, upstream of MSIV.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Event Description NRC Scenario 3 EXAM SUBMITTAL REV 1 Scenario 3 Exam Submittal Rev 1 Waterford 3 2008 NRC Scenario #3 The crew assumes the shift at 25% power during a plant startup from a short notice outage. The crew is to continue the startup to 100% using OP-010-004, Power Operations.
During the up-power the controlling Pressurizer Pressure channel fails high which will cause heater output to go to zero and the in-service spray valve(s) will open. Operators take action IAW OP-901-120, Pressurizer Pressure Control Malfunction to select the operable channel and reset heaters.
After pressurizer pressure has been restored then there will be a failure of Safety Channel B ENI middle detector. Operators diagnose the failure and bypass appropriate channels IAW Technical Specifications.
When appropriate channels are bypassed there will then be a trip of the A CCW pump on overload. Restoration actions will be IAW OP-901-510, Component Cooling Water System Malfunction.
While CCW restoration actions are on-going there will be a steam generator tube leak ramp in from 0-15 gpm over ~10 minutes on the #1 SG. Once identified operator actions are IAW OP-901-202, Steam Generator Tube Leakage or High Activity when primary to secondary leakage is identified.
Once the crew determines the shutdown requirements of the tube leakage then an ESDE will be initiated on the #1 Steam Generator, outside containment but upstream of the MSIV. It will ramp in slowly requiring the operators to manually trip and address the uncontrolled cooldown by either Emergency boration or initiation of SIAS. The ESD will worsen after the crew trips and addresses the uncontrolled cooldown.
Post trip/MSIS the #2 SG MSIV and #2 SG FWIV fail to auto close due to a relay failure requiring manual closure.
EOP flowpath is OP 902-000, SPTAs to OP 902-008, Safety Function Recovery.
If NRC Lead Examiner asks SRO candidate(s) to determine Emergency Plan classification, the candidate should determine the following: Unusual Event (FU1) Loss of Containment due to CNB3, Primary-to-Secondary leakrate >10 gpm with non-isolable steam release from affected S/G to the environment.
ES-401 PWR Examination Outline Form ES-401-2 Exam Submittal Rev 3 NUREG-1021 1
Facility:
Waterford 3 2008 NRC Exam Date of Exam:
3/24/2008 RO K/A Category Points SRO-Only Points Tier Group K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total 1
3 3
3 3
3 3
18 3
3 6
2 2
1 1
2 2
1 9
2 2
4
- 1.
Emergency &
Abnormal Plant Evolutions Tier Totals 5
4 4
5 5
4 27 5
5 10 1
3 2
3 3
2 2
2 2
4 3
2 28 3
2 5
2 1
0 0
1 1
1 1
2 1
1 1
10 0
2 1
3
- 2. Plant Systems Tier Totals 4
2 3
4 3
3 3
4 5
4 3
38 5
3 8
1 2
3 4
1 2
3 4
- 3. Generic Knowledge and Abilities Categories 2
3 3
2 10 2
2 2
1 7
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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A 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 that are not included on the outline should be added. Refer to ES-401,, for guidance regarding 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 KAs 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.
- 8.
On the following pages, enter the K/A 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 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 10CFR55.43
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-401-2 NUREG-1021 E/APE # / Name Safety Function G
K1 K2 K3 A1 A2 Number K/A Topic(s)
Imp.
Q#
2 007 / Reactor Trip - Stabilization - Recovery / 1 X
EA2.02 Ability to determine or interpret the following as they apply to a reactor trip: Proper actions to be taken if the automatic safety functions have not taken place 4.6 76 025 / Loss of RHR System / 4 X
AA2.05 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Limitations on LPI flow and temperature rates of change 3.5 77 026 / Loss of Component Cooling Water / 8 X
AA2.06 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water. The length of time after the loss of CCW flow to a component before that component may be damaged 3.1 78 027 / Pressurizer Pressure Control System Malfunction
/ 3 X
2.4.30 Emergency Procedures / Plan Knowledge of which events related to system operations/status should be reported to outside agencies.
3.6 79 038 / Steam Gen. Tube Rupture / 3 X
2.4.4 Emergency Procedures / Plan Ability to recognize abnormal indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures.
4.3 80 E06 / Loss of Main Feedwater / 4 X
2.4.6 Emergency Procedures / Plan Knowledge symptom based EOP mitigation strategies.
4.0 81 007 / Reactor Trip - Stabilization - Recovery / 1 X
EK3.01 Knowledge of the reasons for the following as the apply to a reactor trip: Actions contained in EOP for reactor trip 4.0 39 008 / Pressurizer Vapor Space Accident / 3 X
AK1.02 Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Change in leak rate with change in pressure 3.1 40 009 / Small Break LOCA / 3 X
EK2.03 Knowledge of the interrelations between the small break LOCA and the following: S/Gs 3.0 41 011 / Large Break LOCA / 3 X
2.4.50 Emergency Procedures / Plan Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
3.3 42 015 / 17 / RCP Malfunctions / 4 X
AK1.01 Knowledge of the operational implications of the following concepts as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):
Natural circulation in a nuclear reactor power plant 4.4 43 022 / Loss of Rx Coolant Makeup / 2 X
AA1.03 Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Makeup:
PZR level trend 3.2 44
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-401-2 NUREG-1021 E/APE # / Name Safety Function G
K1 K2 K3 A1 A2 Number K/A Topic(s)
Imp.
Q#
3 025 / Loss of RHR System / 4 X
2.1.23 Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation.
3.9 45 026 / Loss of Component Cooling Water / 8 X
2.2.22 Equipment Control Knowledge of limiting conditions for operations and safety limits.
3.4 46 027 / Pressurizer Pressure Control System Malfunction
/ 3 X
AA1.05 Ability to operate and / or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: Transfer of heaters to backup power supply 3.3 47 029 / ATWS / 1 X
EK2.06 Knowledge of the interrelations between the and the following an ATWS: Breakers, relays, and disconnects 2.9 48 038 / Steam Gen. Tube Rupture / 3 X
EK1.01 Knowledge of the operational implications of the following concepts as they apply to the SGTR: Use of steam tables 3.1 49 040 / Steam Line Rupture - Excessive Heat Transfer / 4 X
AK2.01 Knowledge of the interrelations between the Steam Line Rupture and the following: Valves 2.6 50 054 / Loss of Main Feedwater / 4 X
AA1.01 Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW):
AFW controls, including the use of alternate AFW sources 4.5 51 056 / Loss of Off-site Power / 6 X
AA2.37 Ability to determine and interpret the following as they apply to the Loss of Offsite Power: ED/G indicators for the following: voltage, frequency, load, load-status, and closure of bus tie breakers 3.7 52 057 / Loss of Vital AC Inst. Bus / 6 X
AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus 4.1 53 058 / Loss of DC Power / 6 X
AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of DC Power:
Actions contained in EOP for loss of dc power 4.0 54 062 / Loss of Nuclear Svc. Water / 4 X
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 2.9 55 065 / Loss of Instrument Air / 8 X
AA2.05 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to commence plant shutdown if instrument air pressure is decreasing 3.4 56
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-401-2 NUREG-1021 E/APE # / Name Safety Function G
K1 K2 K3 A1 A2 Number K/A Topic(s)
Imp.
Q#
4 K/A Category Point Totals:
3/3 3
3 3
3 3/3 Group Point Total:
18/6
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-401-2 NUREG-1021 E/APE # / Name Safety Function G
K1 K2 K3 A1 A2 Number K/A Topic(s)
Imp.
Q#
5 003 / Dropped Control Rod / 1 X
AA2.01 Ability to determine and interpret the following as they apply to the Dropped Control Rod: Rod Position Indication to actual Rod Position 3.9 82 069 (W/E14) Loss of CTMT Integrity / 5 X
2.2.25 Equipment Control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
3.7 83 028 / Pressurizer Level Malfunction / 2 X
2.4.31 Emergency Procedures / Plan Knowledge of annunciators alarms and indications, and use of the response instructions.
3.4 84 068 / Control Room Evac. / 8 X
AA2.07 Ability to determine and interpret the following as they apply to the Control Room Evacuation: PZR level 4.3 85 003 / Dropped Control Rod / 1 X
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 3.6 57 005 / Inoperable/Stuck Control Rod / 1 X
AK1.05 Knowledge of the operational implications of the following concepts as they apply to Inoperable /
Stuck Control Rod: Calculation of minimum shutdown margin 3.3 58 028 / Pressurizer Level Control System Malfunctions / 2 X
AA1.07 Ability to operate and / or monitor the following as they apply to the Pressurizer Level Control Malfunctions: Charging pumps maintenance of PZR level 3.3 59 060 / Accidental Gaseous RadWaste Rel. / 9 X
AA1.02 Ability to operate and / or monitor the following as they apply to the Accidental Gaseous Radwaste:
Ventilation system 2.9 60 061 / ARM System Alarms / 7 X
AK2.01 Knowledge of the interrelations between the Area Radiation Monitoring (ARM) System Alarms and the following: Detectors at each ARM system location 2.5 61 074 / Inad. Core Cooling / 4 X
EA2.04 Ability to determine or interpret the following as they apply to a Inadequate Core Cooling: Relationship between RCS temperature and main steam pressure 3.7 62 A13 / Natural Circ. / 4 X
AK1.2 Knowledge of the operational implications of the following concepts as they apply to the (Natural Circulation Operations) Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).
3.2 63
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-401-2 NUREG-1021 E/APE # / Name Safety Function G
K1 K2 K3 A1 A2 Number K/A Topic(s)
Imp.
Q#
6 A16 / Excess RCS Leakage / 2 X
2.1.14 Conduct of Operations: Knowledge of system status criteria which require the notification of plant personnel.
2.5 64 E09 / Functional Recovery X
EK3.4 Knowledge of the reasons for the following responses as they apply to the (Functional Recovery) RO or SRO function as a within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
3.3 65 K/A Category Point Total:
1/2 2
1 1
2 2/2 Group Point Total:
9/4
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 1 Form ES-401-2 NUREG-1021 System #/Name G
K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp.
Q#
7 010 Pressurizer Pressure Control X
2.4.6 Emergency Procedures / Plan Knowledge symptom based EOP mitigation strategies.
4.0 86 012 Reactor Protection X
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of Instrument Power 3.6 87 059 Main Feedwater X
A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in MFW suction of discharge line 3.4 88 063 DC Electrical Distribution X
2.4.4 Emergency Procedures / Plan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.3 89 076 Service Water X
A2.02 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: Service water header pressure 3.1 90 003 Reactor Coolant Pump X
K1.08 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems: Containment isolation 2.7 1
004 Chemical and Volume Control X
K6.26 Knowledge of the operational implications of the following concepts as they apply to the CVCS:
Methods of pressure control of solid plant (PZR relief and water inventory) 3.8 2
005 Residual Heat Removal X
K2.03 Knowledge of bus power supplies to the following:
RCS pressure boundary motor-operated valves 2.7 3
006 Emergency Core Cooling X
A4.01 Ability to manually operate and/or monitor in the control room: Pumps 4.1 4
006 Emergency Core Cooling X
A3.03 Ability to monitor automatic operation of the ECCS, including: ESFAS-operated valves 4.1 5
007 Pressurizer Relief/Quench Tank X
2.1.32 Conduct of operations: Ability to explain and apply all system limits and precautions.
3.4 6
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 1 Form ES-401-2 NUREG-1021 System #/Name G
K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp.
Q#
8 008 Component Cooling Water X
K4.07 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:
Operation of the CCW swing-bus power supply and its associated breakers and controls 2.6 7
010 Pressurizer Pressure Control X
K3.01 Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: RCS 3.8 8
012 Reactor Protection X
K6.06 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Sensors and detectors 2.7 9
013 Engineered Safety Features Actuation X
K4.12 Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following: Safety Injection block 3.7 10 022 Containment Cooling X
A2.03 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: Fan motor thermal overload/high-speed operation 2.6 11 022 Containment Cooling X
K4.05 Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following:
Containment cooling after LOCA destroys ventilation ducts 2.6 12 026 Containment Spray X
2.1.30 Conduct of Operations: Ability to locate and operate components, including local controls 3.9 13 026 Containment Spray X
K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: ECCS 4.2 14 039 Main and Reheat Steam X
K5.08 Knowledge of the operational implications of the following concepts as the apply to the MRSS:
Effect of steam removal on reactivity 3.6 15 059 Main Feedwater X
K3.03 Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/GS 3.5 16 059 Main Feedwater X
A3.02 Ability to monitor automatic operation of the MFW, including: Programmed levels of the S/G 2.9 17 061 Auxillary/Emergency Feedwater X
K2.02 Knowledge of bus power supplies to the following:
AFW electric drive pumps 3.7 18 062 AC Electrical Distribution X
A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Significance of D/G load limits 3.4 19
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 1 Form ES-401-2 NUREG-1021 System #/Name G
K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp.
Q#
9 063 DC Electrical Distribution X
K3.01 Knowledge of the effect that a loss or malfunction of the dc electrical system will have on the following: ED/G 3.7 20 063 DC Electrical Distribution X
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the dc electrical system and the following systems:
Battery charger and battery 2.9 21 064 Emergency Diesel Generator X
A2.09 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Synchronization of the ED/G with other electric power supplies 3.1 22 010 Pressurizer Pressure Control X
A4.02 Ability to manually operate and/or monitor in the control room: Pressurizer Heaters 3.6 23 073 Process Radiation Monitoring X
K5.03 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits 2.9 24 076 Service Water X
A3.02 Ability monitor automatic operation of the SWS, including: Emergency Heat Loads 3.7 25 078 Instrument Air X
A4.01 Ability to manually operate and/or monitor in the control room: Pressure gauges 3.1 26 103 Containment X
A3.01 Ability to monitor automatic operation of the containment system, including: Containment isolation 3.9 27 103 Containment X
A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: Containment pressure, temperature, and humidity 3.7 28 K/A Category Point Totals:
2/2 3
2 3
3 2
2 2
2/3 4
3 Group Point Total:
28/5
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 2 Form ES-401-2 NUREG-1021 System #/Name G
K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp.
Q#
10 034 Fuel Handling Equipment X
2.2.28 Equipment Control: Knowledge of new and spent fuel movement procedures 3.5 91 035 Steam Generator X
A2.03 Ability to (a) predict the impacts of the following mal-functions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure/level transmitter failure 3.6 92 075 Circulating Water X
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps 2.7 93 001 Control Rod Drive X
K1.05 Knowledge of the physical connections and/or cause-effect relationships between the CRDS and the following systems: NIS and RPS 4.5 29 016 Non-nuclear Instrumentation X
K5.01 Knowledge of the operational implication of the following concepts as they apply to the NNIS:
Separation of control and protection circuits 2.7 30 017 In-core Temperature Monitor X
A3.01 Ability to monitor automatic operation of the ITM system including: Indications of normal, natural, and interrupted circulation of RCS 3.6 31 028 Hydrogen Recombiner and Purge Control X
A4.01 Ability to manually operate and/or monitor in the control room: HRPS controls 4.0 32 056 Condensate System X
2.1.32 Conduct of Operations: Ability to explain and apply all system limits and precautions.
3.4 33 068 Liquid Radwaste X
K6.10 Knowledge of the effect of a loss or malfunction on the following will have on the Liquid Radwaste System : Radiation monitors 2.5 34 071 Waste Gas Disposal X
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Use of Waste Gas release monitors, radiation, gas flow rate, and totalizer.
3.3 35 072 Area Radiation Monitoring X
K4.01 Knowledge of ARM system design feature(s) and/or interlock(s) which provide for the following:
Containment ventilation isolation 3.3 36
ES-401 Waterford 3 2008 NRC Exam Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 2 Form ES-401-2 NUREG-1021 System #/Name G
K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp.
Q#
11 075 Circulating Water X
A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Circulating Water System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safety features and relationship between condenser vacuum, turbine trip, and steam dump 2.5 37 086 Fire Protection X
A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: Fire doors 2.7 38 K/A Category Point Totals:
1/1 1
0 0
1 1
1 1
2/2 1
1 Group Point Total:
10/3
ES-401 Generic Knowledge and Abilities Outline (Tier3)
Form ES-401-3 Rev 3 NUREG-1021 12 Facility:
Waterford 3 2008 NRC Exam Date of Exam:
3/24/2008 RO SRO-Only Category K/A #
Topic IR Q#
IR Q#
2.1.10 Knowledge of conditions and limitations in the facility license.
3.9 94 2.1.11 Knowledge of less than one hour technical specification action statements for systems.
3.8 95 2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports.
2.9 66 2.1.12 Ability to apply technical specifications for a system.
2.9 67
- 1.
Conduct of Operations Subtotal 2
2 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
3.7 96 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations.
3.6 97 2.2.26 Knowledge of refueling administrative requirements.
2.5 68 2.2.27 Knowledge of the refueling process.
2.6 69 2.2.23 Ability to track limiting conditions for operations.
2.6 70
- 2.
Equipment Control Subtotal 3
2 2.3.9 Knowledge of the process for performing a containment purge 2.9 98 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
3.3 99 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
2.5 71 2.3.9 Knowledge of the process for performing a containment purge.
2.5 72 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements 2.6 73
- 3.
Radiation Control Subtotal 3
2 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
3.6 100 2.4.15 Knowledge of communications procedures associated with EOP implementation 3.0 74 2.4.18 Knowledge of the specific bases for EOPs.
2.7 75
- 4.
Emergency Procedures / Plan Subtotal 2
1 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Rev 2 NUREG-1021 13 Tier /
Group Randomly Selected K/A Reason for Rejection 2 / 1 026 G2.4.30 Q #13. Importance less than 2.5 for RO. Randomly reselected 026 G2.1.30 1 / 2 003 AA2.03 Q #82. Same KA as #57 on RO exam. Randomly reselected 003 AA2.01 2 / 1 013 K4.22 Q #10. Not applicable to facility. Randomly selected 013 K4.12 2 / 1 076 A1.02 Q #25. No RBCCW at facility, and also topic overlap with SRO #90.
Randomly selected 076 A3.02 2 / 2 001 K1.09 Q #29. No credible tie between systems. Randomly selected 001 K1.05 2 / 2 071 A2.08 Q #35. Topic selected not suitable for RO level test item. Randomly selected 071 A2.05.
2 / 2 075 K2.03 Q #37. Excessive selection of simple power supply topics. Randomly reselected 075 A2.03 2 / 1 007 G2.2.22 Q #6. No LCOs or technical specifications associated with system/component.
Randomly reselected G2.1.32 1 / 1 038 G2.4.49 Q #80. After significant time expenditure, unable to develop a test item that would satisfy SRO criteria and meet the KA. Randomly reselected. G2.4.4.
2 / 2 071 A2.05 Q #35. Topic overlapped a simulator JPM task. Randomly reselected 071 A2.02.
3 / 3 G2.3.2 Q #98. Question developed not adequately supported by facility references at SRO level. Systematically reselected G2.3.9 2 / 2 028 G2.1.32 Q #91 Topic would not support SRO knowledge. Systematically reselected system 034 G2.2.28 1 / 2 036 AA1.01 Q #59 Excessive topic overlap. Systematically reselected 028 AA1.07 2 / 1 064 A4.07 Q #23 Excessive topic overlap. Systematically reselected 010 A4.02 2 / 1 039 K5.01 Q # 15 After significant time expenditure, unable to develop a psychometrically sound test item that would satisfy the KA. Systematically reselected K5.08 1 / 1 015 AK1.04 Q # 43 Question developed not adequately supported by facility references.
Systematically reselected AK1.01 1 / 1 026 AA2.03 Q # 78 After significant time expenditure, unable to develop a psychometrically sound SRO test item that would satisfy the KA Systematically reselected A2.06 1 / 2 005 2.2.25 Q #83 Excessive topic overlap. Systematically reselected 069