ML081200405

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2008-03 - Final - Outlines
ML081200405
Person / Time
Site: Waterford Entergy icon.png
Issue date: 03/24/2008
From:
Division of Reactor Safety IV
To:
Entergy Operations
References
50-382/08-301
Download: ML081200405 (22)
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Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: WATERFORD 3 Date of Examination: 3/24/2008 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

A1 R, M Perform a Shutdown Margin Calculation Conduct of Operations 2.1.23 Ability to perform specific and integrated plant procedures during all modes of plant operation.(3.9)

A2 R, M Determine Time to SDC (Condenser Inventory)

Conduct of Operations 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 R, M Equipment Control 2.2.13 Knowledge of tagging and clearance procedures.

(3.6)

A4 R, N Complete Pre-requisites for GDT Release Radiation Control 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 ( 3 for ROs; for SROs & RO retakes)

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

(P)revious 2 exams ( 1; randomly selected)

(S)imulator NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: WATERFORD 3 Date of Examination: 3/24/2008 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

A5 R, M Calculate Shutdown Margin with ONE Untrippable CEA Conduct of Operations 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs and tables which contain performance data.(3.1)

A6 R, N Determine Event Notification Requirements 2.1.2 Knowledge of operator responsibilities during all Conduct of Operations modes of plant operation. (4.0)

A7 R, M Approve an Equipment Tagout 2.2.13 Knowledge of tagging and clearance procedures.

Equipment Control (3.8)

A8 P, R Approve liquid Release Permit 2.3.6 Knowledge of the requirements for reviewing and Radiation Control approving release permits.(3.1)

Determine Protective Action Recommendations A9 R, M 2.4.44 Knowledge of emergency plan protective action Emergency Plan 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 ( 3 for ROs; for SROs & RO retakes)

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

(P)revious 2 exams ( 1; randomly selected)

(S)imulator NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 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 R,L,D,E 8 During Control Room Evacuation and Loss of Offsite power P2 061-Reset EFW Pump AB Mechanical Overspeed During CR L,D,E 4-S Evacuation With Fire P3 062-Transfer AB SUPS From Alternate To Normal Power N 6 Supply

@ 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 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 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 R,L,D,E 8 During Control Room Evacuation and Loss of Offsite power P2 061-Reset EFW Pump AB Mechanical Overspeed During CR L,D,E 4-S Evacuation With Fire P3 062-Transfer AB SUPS From Alternate To Normal Power N 6 Supply

@ 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 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 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 R,L,D,E 8 During Control Room Evacuation and Loss of Offsite power P2 061-Reset EFW Pump AB Mechanical Overspeed During CR L,D,E 4-S Evacuation With Fire

@ 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 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected)

(R)CA 1/ 1/ 1 (S)imulator NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 EXAM SUBMITTAL Rev. 1 Facility: WATERFORD 3 Scenario No.: 2 Op Test No.: NRC Examiners: Operators:

Initial Conditions: ~60% power, MOC, AB buses aligned to B side.

A EFW pump OOS for seal replacement, A ACCW pump OOS for motor pm,.

Turnover: 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: Ensuring Reactivity control post trip by actions to initiate Diverse Trip.

Ensuring feedwater to at least one SG utilizing Auxiliary Feedwater.

Event Malf. No. Event Event No. Type* Description 1 R - ATC 15 MW/MIN downpower to remove A Main feed pump from service due to high vibration.

N-BOP/SRO 2 FW26B I - BOP, Steam Generator Feedwater Flow instrument fails HIGH to SRO FWCS #2.

3 RD02A72 C - ALL Dropped Regulating group CEA, #72 and recovery.

TS - SRO 4 CV12A2 I - ATC, VCT level inst., CVC-ILT-0227, fails LOW.

SRO TS - SRO 5 FW03B M - ALL Second main feed pump trips, reactor fails to auto or manually RP01A-D trip. Diverse Scram successful.

RP02A-D 6 FW05 C - BOP, AB EFW pump trips on overspeed, B EFW pump fails to FW07B SRO start, manual start is also unsuccessful.

DI-08A07S09-1

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 2 Exam Submittal Rev 1 Scenario Event Description NRC 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.

Scenario 2 Exam Submittal Rev 1 Appendix D Scenario Outline Form ES-D-1 EXAM SUBMITTAL REV 1 Facility: WATERFORD 3 Scenario No.: 3 Op Test No.: NRC Examiners: Operators:

Initial Conditions: 25% power, MOC, AB buses aligned to B side.

Turnover: Plant startup is in progress after being off-line for 2 days.

Critical Task: Preventing RCS repressurization by actions to stabilize RCS temperature using the non-ESD SG.

Isolating the SG with SG Tube Leak.

Emergency borate or actuate SIAS due to uncontrolled cooldown.

Event Malf. Event Event No. No. Type* Description 1 R - ATC Raising power from 25%.

N - BOP, SRO 2 RX14A I - ATC, Controlling Pressurizer Pressure channel fails HIGH.

SRO 3 NI01F I - ATC, Safety Channel B ENI middle detector fails HIGH.

SRO TS - SRO 4 CC01A C - BOP, A CCW pump trip.

SRO TS - SRO 5 SG01A TS - SRO 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.

7 RP08H C - BOP, #2 SG MSIV and #2 SG MFIV fail to auto close on MSIS.

RP09H SRO

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 3 Exam Submittal Rev 1 Scenario Event Description NRC 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.

Scenario 3 Exam Submittal Rev 1 ES-401 PWR Examination Outline Form ES-401-2 Exam Submittal Rev 3 Facility: Waterford 3 2008 NRC Exam Date of Exam: 3/24/2008 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 2 1 1 2 2 1 9 2 2 4 Plant Evolutions Tier 5 4 4 5 5 4 27 5 5 10 Totals 1 3 2 3 3 2 2 2 2 4 3 2 28 3 2 5

2. Plant Systems 2 1 0 0 1 1 1 1 2 1 1 1 10 0 2 1 3 Tier 4 2 3 4 3 3 3 4 5 4 3 38 5 3 8 Totals
3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 3 2 2 2 2 1 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, Attachment 2, 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 NUREG-1021 1

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Ability to determine or interpret the following as they 007 / Reactor Trip - Stabilization - Recovery / 1 X EA2.02 apply to a reactor trip: Proper actions to be taken if 4.6 76 the automatic safety functions have not taken place Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal 025 / Loss of RHR System / 4 X AA2.05 3.5 77 System: Limitations on LPI flow and temperature rates of change Ability to determine and interpret the following as they apply to the Loss of Component Cooling 026 / Loss of Component Cooling Water / 8 X AA2.06 Water. The length of time after the loss of CCW flow 3.1 78 to a component before that component may be damaged Emergency Procedures / Plan Knowledge of which 027 / Pressurizer Pressure Control System Malfunction X 2.4.30 events related to system operations/status should 3.6 79

/3 be reported to outside agencies.

Emergency Procedures / Plan Ability to recognize abnormal indications for system operating 038 / Steam Gen. Tube Rupture / 3 X 2.4.4 4.3 80 parameters which are entry level conditions for emergency and abnormal operating procedures.

Emergency Procedures / Plan Knowledge symptom E06 / Loss of Main Feedwater / 4 X 2.4.6 4.0 81 based EOP mitigation strategies.

Knowledge of the reasons for the following as the 007 / Reactor Trip - Stabilization - Recovery / 1 X EK3.01 apply to a reactor trip: Actions contained in EOP for 4.0 39 reactor trip Knowledge of the operational implications of the following concepts as they apply to a Pressurizer 008 / Pressurizer Vapor Space Accident / 3 X AK1.02 3.1 40 Vapor Space Accident: Change in leak rate with change in pressure Knowledge of the interrelations between the small 009 / Small Break LOCA / 3 X EK2.03 3.0 41 break LOCA and the following: S/Gs Emergency Procedures / Plan Ability to verify 011 / Large Break LOCA / 3 X 2.4.50 system alarm setpoints and operate controls 3.3 42 identified in the alarm response manual.

Knowledge of the operational implications of the following concepts as they apply to the Reactor 015 / 17 / RCP Malfunctions / 4 X AK1.01 4.4 43 Coolant Pump Malfunctions (Loss of RC Flow):

Natural circulation in a nuclear reactor power plant Ability to operate and / or monitor the following as 022 / Loss of Rx Coolant Makeup / 2 X AA1.03 they apply to the Loss of Reactor Coolant Makeup: 3.2 44 PZR level trend NUREG-1021 2

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Conduct of Operations: Ability to perform specific 025 / Loss of RHR System / 4 X 2.1.23 system and integrated plant procedures during all 3.9 45 modes of plant operation.

Equipment Control Knowledge of limiting conditions 026 / Loss of Component Cooling Water / 8 X 2.2.22 3.4 46 for operations and safety limits.

Ability to operate and / or monitor the following as 027 / Pressurizer Pressure Control System Malfunction they apply to the Pressurizer Pressure Control X AA1.05 3.3 47

/3 Malfunctions: Transfer of heaters to backup power supply Knowledge of the interrelations between the and 029 / ATWS / 1 X EK2.06 the following an ATWS: Breakers, relays, and 2.9 48 disconnects Knowledge of the operational implications of the 038 / Steam Gen. Tube Rupture / 3 X EK1.01 following concepts as they apply to the SGTR: Use 3.1 49 of steam tables Knowledge of the interrelations between the Steam 040 / Steam Line Rupture - Excessive Heat Transfer / 4 X AK2.01 2.6 50 Line Rupture and the following: Valves Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW):

054 / Loss of Main Feedwater / 4 X AA1.01 4.5 51 AFW controls, including the use of alternate AFW sources Ability to determine and interpret the following as they apply to the Loss of Offsite Power: ED/G 056 / Loss of Off-site Power / 6 X AA2.37 3.7 52 indicators for the following: voltage, frequency, load, load-status, and closure of bus tie breakers Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC 057 / Loss of Vital AC Inst. Bus / 6 X AK3.01 4.1 53 Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus Knowledge of the reasons for the following 058 / Loss of DC Power / 6 X AK3.02 responses as they apply to the Loss of DC Power: 4.0 54 Actions contained in EOP for loss of dc power Ability to determine and interpret the following as 062 / Loss of Nuclear Svc. Water / 4 X AA2.02 they apply to the Loss of Nuclear Service Water: 2.9 55 The cause of possible SWS loss Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to 065 / Loss of Instrument Air / 8 X AA2.05 3.4 56 commence plant shutdown if instrument air pressure is decreasing NUREG-1021 3

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

K/A Category Point Totals: 3/3 3 3 3 3 3/3 Group Point Total: 18/6 NUREG-1021 4

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Ability to determine and interpret the following as 003 / Dropped Control Rod / 1 X AA2.01 they apply to the Dropped Control Rod: Rod 3.9 82 Position Indication to actual Rod Position Equipment Control Knowledge of bases in technical 069 (W/E14) Loss of CTMT Integrity / 5 X 2.2.25 specifications for limiting conditions for operations 3.7 83 and safety limits.

Emergency Procedures / Plan Knowledge of 028 / Pressurizer Level Malfunction / 2 X 2.4.31 annunciators alarms and indications, and use of the 3.4 84 response instructions.

Ability to determine and interpret the following as 068 / Control Room Evac. / 8 X AA2.07 they apply to the Control Room Evacuation: PZR 4.3 85 level Ability to determine and interpret the following as they apply to the Dropped Control Rod: Dropped 003 / Dropped Control Rod / 1 X AA2.03 3.6 57 rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements Knowledge of the operational implications of the following concepts as they apply to Inoperable /

005 / Inoperable/Stuck Control Rod / 1 X AK1.05 3.3 58 Stuck Control Rod: Calculation of minimum shutdown margin Ability to operate and / or monitor the following as they apply to the Pressurizer Level Control 028 / Pressurizer Level Control System Malfunctions / 2 X AA1.07 3.3 59 Malfunctions: Charging pumps maintenance of PZR level Ability to operate and / or monitor the following as 060 / Accidental Gaseous RadWaste Rel. / 9 X AA1.02 they apply to the Accidental Gaseous Radwaste: 2.9 60 Ventilation system Knowledge of the interrelations between the Area Radiation Monitoring (ARM) System Alarms and 061 / ARM System Alarms / 7 X AK2.01 2.5 61 the following: Detectors at each ARM system location Ability to determine or interpret the following as they apply to a Inadequate Core Cooling: Relationship 074 / Inad. Core Cooling / 4 X EA2.04 3.7 62 between RCS temperature and main steam pressure Knowledge of the operational implications of the following concepts as they apply to the (Natural A13 / Natural Circ. / 4 X AK1.2 Circulation Operations) Normal, abnormal and 3.2 63 emergency operating procedures associated with (Natural Circulation Operations).

NUREG-1021 5

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Conduct of Operations: Knowledge of system status A16 / Excess RCS Leakage / 2 X 2.1.14 criteria which require the notification of plant 2.5 64 personnel.

Knowledge of the reasons for the following responses as they apply to the (Functional Recovery) RO or SRO function as a within the E09 / Functional Recovery X EK3.4 control room team as appropriate to the assigned 3.3 65 position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

K/A Category Point Total: 1/2 2 1 1 2 2/2 Group Point Total: 9/4 NUREG-1021 6

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Emergency Procedures / Plan Knowledge 010 Pressurizer Pressure Control X 2.4.6 4.0 86 symptom based EOP mitigation strategies.

Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to 012 Reactor Protection X A2.02 3.6 87 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of Instrument Power Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to 059 Main Feedwater X A2.05 3.4 88 correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in MFW suction of discharge line Emergency Procedures / Plan Ability to recognize abnormal indications for system operating 063 DC Electrical Distribution X 2.4.4 4.3 89 parameters which are entry-level conditions for emergency and abnormal operating procedures.

Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to 076 Service Water X A2.02 3.1 90 correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure Knowledge of the physical connections and/or 003 Reactor Coolant Pump X K1.08 cause-effect relationships between the RCPS and 2.7 1 the following systems: Containment isolation Knowledge of the operational implications of the 004 Chemical and Volume following concepts as they apply to the CVCS:

X K6.26 3.8 2 Control Methods of pressure control of solid plant (PZR relief and water inventory)

Knowledge of bus power supplies to the following:

005 Residual Heat Removal X K2.03 2.7 3 RCS pressure boundary motor-operated valves Ability to manually operate and/or monitor in the 006 Emergency Core Cooling X A4.01 4.1 4 control room: Pumps Ability to monitor automatic operation of the 006 Emergency Core Cooling X A3.03 4.1 5 ECCS, including: ESFAS-operated valves 007 Pressurizer Relief/Quench Conduct of operations: Ability to explain and apply X 2.1.32 all system limits and precautions. 3.4 6 Tank NUREG-1021 7

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:

008 Component Cooling Water X K4.07 2.6 7 Operation of the CCW swing-bus power supply and its associated breakers and controls Knowledge of the effect that a loss or malfunction 010 Pressurizer Pressure Control X K3.01 3.8 8 of the PZR PCS will have on the following: RCS Knowledge of the effect of a loss or malfunction of 012 Reactor Protection X K6.06 the following will have on the RPS: Sensors and 2.7 9 detectors Knowledge of ESFAS design feature(s) and/or 013 Engineered Safety Features X K4.12 interlock(s) which provide for the following: Safety 3.7 10 Actuation Injection block Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to 022 Containment Cooling X A2.03 2.6 11 correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor thermal overload/high-speed operation Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following:

022 Containment Cooling X K4.05 2.6 12 Containment cooling after LOCA destroys ventilation ducts Conduct of Operations: Ability to locate and 026 Containment Spray X 2.1.30 3.9 13 operate components, including local controls Knowledge of the physical connections and/or 026 Containment Spray X K1.01 cause-effect relationships between the CSS and 4.2 14 the following systems: ECCS Knowledge of the operational implications of the 039 Main and Reheat Steam X K5.08 following concepts as the apply to the MRSS: 3.6 15 Effect of steam removal on reactivity Knowledge of the effect that a loss or malfunction 059 Main Feedwater X K3.03 3.5 16 of the MFW will have on the following: S/GS Ability to monitor automatic operation of the MFW, 059 Main Feedwater X A3.02 2.9 17 including: Programmed levels of the S/G 061 Auxillary/Emergency Knowledge of bus power supplies to the following:

X K2.02 AFW electric drive pumps 3.7 18 Feedwater Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 062 AC Electrical Distribution X A1.01 associated with operating the ac distribution 3.4 19 system controls including: Significance of D/G load limits NUREG-1021 8

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Knowledge of the effect that a loss or malfunction 063 DC Electrical Distribution X K3.01 of the dc electrical system will have on the 3.7 20 following: ED/G Knowledge of the physical connections and/or cause-effect relationships between the dc 063 DC Electrical Distribution X K1.03 2.9 21 electrical system and the following systems:

Battery charger and battery Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use 064 Emergency Diesel Generator X A2.09 procedures to correct, control, or mitigate the 3.1 22 consequences of those malfunctions or operations: Synchronization of the ED/G with other electric power supplies 010 Pressurizer Pressure Control X A4.02 Ability to manually operate and/or monitor in the 3.6 23 control room: Pressurizer Heaters Knowledge of the operational implications as they apply to concepts as they apply to the PRM 073 Process Radiation Monitoring X K5.03 2.9 24 system: Relationship between radiation intensity and exposure limits Ability monitor automatic operation of the SWS, 076 Service Water X A3.02 3.7 25 including: Emergency Heat Loads Ability to manually operate and/or monitor in the 078 Instrument Air X A4.01 3.1 26 control room: Pressure gauges Ability to monitor automatic operation of the 103 Containment X A3.01 containment system, including: Containment 3.9 27 isolation Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 103 Containment X A1.01 associated with operating the containment system 3.7 28 controls including: Containment pressure, temperature, and humidity K/A Category Point Totals: 2/2 3 2 3 3 2 2 2 2/3 4 3 Group Point Total: 28/5 NUREG-1021 9

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Equipment Control: Knowledge of new and spent 034 Fuel Handling Equipment X 2.2.28 3.5 91 fuel movement procedures 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 035 Steam Generator X A2.03 3.6 92 correct, control, or mitigate the consequences of those malfunctions or operations: Pressure/level transmitter failure Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use 075 Circulating Water X A2.02 2.7 93 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps Knowledge of the physical connections and/or 001 Control Rod Drive X K1.05 cause-effect relationships between the CRDS and 4.5 29 the following systems: NIS and RPS Knowledge of the operational implication of the 016 Non-nuclear Instrumentation X K5.01 following concepts as they apply to the NNIS: 2.7 30 Separation of control and protection circuits Ability to monitor automatic operation of the ITM 017 In-core Temperature Monitor X A3.01 system including: Indications of normal, natural, 3.6 31 and interrupted circulation of RCS 028 Hydrogen Recombiner and Ability to manually operate and/or monitor in the X A4.01 control room: HRPS controls 4.0 32 Purge Control Conduct of Operations: Ability to explain and 056 Condensate System X 2.1.32 3.4 33 apply all system limits and precautions.

Knowledge of the effect of a loss or malfunction 068 Liquid Radwaste X K6.10 on the following will have on the Liquid Radwaste 2.5 34 System : Radiation monitors Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System ; and (b) based on those 071 Waste Gas Disposal X A2.02 predictions, use procedures to correct, control, or 3.3 35 mitigate the consequences of those malfunctions or operations: Use of Waste Gas release monitors, radiation, gas flow rate, and totalizer.

Knowledge of ARM system design feature(s) 072 Area Radiation Monitoring X K4.01 and/or interlock(s) which provide for the following: 3.3 36 Containment ventilation isolation NUREG-1021 10

ES-401 Waterford 3 2008 NRC Exam Form ES-401-2 Written Examination Outline Rev 3 Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

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 075 Circulating Water X A2.03 2.5 37 mitigate the consequences of those malfunctions or operations: Safety features and relationship between condenser vacuum, turbine trip, and steam dump Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 086 Fire Protection X A1.03 2.7 38 associated with Fire Protection System operating the controls including: Fire doors K/A Category Point Totals: 1/1 1 0 0 1 1 1 1 2/2 1 1 Group Point Total: 10/3 NUREG-1021 11

ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 Rev 3 Facility: Waterford 3 2008 NRC Exam Date of Exam: 3/24/2008 RO SRO-Only Category K/A # Topic IR Q# IR Q#

Knowledge of conditions and limitations in the 2.1.10 3.9 94 facility license.

Knowledge of less than one hour technical 2.1.11 3.8 95 specification action statements for systems.

1.

Conduct of Ability to make accurate, clear and concise logs, 2.1.18 2.9 66 Operations records, status boards, and reports.

Ability to apply technical specifications for a 2.1.12 2.9 67 system.

Subtotal 2 2 Knowledge of bases in technical specifications 2.2.25 for limiting conditions for operations and safety 3.7 96 limits.

Knowledge of the process for managing 2.2.18 maintenance activities during shutdown 3.6 97 operations.

2.

Equipment Control Knowledge of refueling administrative 2.2.26 2.5 68 requirements.

2.2.27 Knowledge of the refueling process. 2.6 69 2.2.23 Ability to track limiting conditions for operations. 2.6 70 Subtotal 3 2 Knowledge of the process for performing a 2.3.9 2.9 98 containment purge Ability to perform procedures to reduce 2.3.10 excessive levels of radiation and guard against 3.3 99 personnel exposure.

Knowledge of radiation exposure limits and

3. 2.3.4 contamination control, including permissible 2.5 71 Radiation Control levels in excess of those authorized.

Knowledge of the process for performing a 2.3.9 2.5 72 containment purge.

Knowledge of 10 CFR: 20 and related facility 2.3.1 2.6 73 radiation control requirements Subtotal 3 2 Knowledge of the organization of the operating 2.4.5 procedures network for normal, abnormal, and 3.6 100 emergency evolutions.

4.

Knowledge of communications procedures Emergency 2.4.15 3.0 74 associated with EOP implementation Procedures / Plan 2.4.18 Knowledge of the specific bases for EOPs. 2.7 75 Subtotal 2 1 Tier 3 Point Total 10 7 NUREG-1021 12

ES-401 Record of Rejected K/As Form ES-401-4 Rev 2 Tier / Randomly Reason for Rejection Group Selected K/A 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 Q #25. No RBCCW at facility, and also topic overlap with SRO #90.

2/1 076 A1.02 Randomly selected 076 A3.02 2/2 001 K1.09 Q #29. No credible tie between systems. Randomly selected 001 K1.05 Q #35. Topic selected not suitable for RO level test item. Randomly selected 2/2 071 A2.08 071 A2.05.

Q #37. Excessive selection of simple power supply topics. Randomly 2/2 075 K2.03 reselected 075 A2.03 Q #6. No LCOs or technical specifications associated with system/component.

2/1 007 G2.2.22 Randomly reselected G2.1.32 Q #80. After significant time expenditure, unable to develop a test item that 1/1 038 G2.4.49 would satisfy SRO criteria and meet the KA. Randomly reselected. G2.4.4.

Q #35. Topic overlapped a simulator JPM task. Randomly reselected 071 2/2 071 A2.05 A2.02.

Q #98. Question developed not adequately supported by facility references at 3/3 G2.3.2 SRO level. Systematically reselected G2.3.9 Q #91 Topic would not support SRO knowledge. Systematically reselected 2/2 028 G2.1.32 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 Q # 15 After significant time expenditure, unable to develop a psychometrically 2/1 039 K5.01 sound test item that would satisfy the KA. Systematically reselected K5.08 Q # 43 Question developed not adequately supported by facility references.

1/1 015 AK1.04 Systematically reselected AK1.01 Q # 78 After significant time expenditure, unable to develop a psychometrically 1/1 026 AA2.03 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 NUREG-1021 13

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