Latest revision as of 07:48, 6 February 2020

Text

11 Final Outlines
	ML13029A081
Person / Time
Site:	River Bend
Issue date:	11/15/2012
From:	David Strickland; Operations Branch IV
To:	; Entergy Operations
	Laura Hurley
References
	50-458/12-011
	Download: ML13029A081 (30)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions:

Mode 1, Reactor power 68%. Power ascension in progress following downpower for Feedwater pump C seal replacement. APRM B in bypass due to downscale failure. FWS-P1A & B in service.

Turnover: Shift priorities: 1) Start lube oil system for FWS-P1C in preparation for pump start. 2) Place 3rd Feed Reg Valve in service. 3) Raise reactor power in accordance with Reactivity Control Plan Step 20, then await further guidance from reactor engineering.

Event Malf. Event Event No. No. Type* Description 1 NA N (CRS,BOP) Start Feedwater pump C lube oil system per SOP-0009.

rd 2 NA N (CRS,ATC) Place 3 Feedwater Regulating Valve in service per SOP-0009.

3 NA R (ATC) Raise reactor power in accordance with the reactivity control plan Step 20.

4 NMS015F I (CRS,ATC) (Tech Spec) APRM F Upscale failure due to flow converter downscale failure and half scram.

5 MSC011 C(CRS) (Tech Spec) 171 airlock inner door seal failure.

p870_54a:

6 g_5 C(CRS,BOP) Steam Packing Exhauster failure requiring equipment rotation.

FAIL ON 7 EHC001 M (ALL) Main Turbine Trip/Anticipated Transient Without Scram with MSIVs open due to failure of RPS to completely de-energize.

RPS001A 8 FWS004B C (CRS,ATC) Feedwater Master Level Controller output fails high.

9 EHC002B C (CRS,BOP) Main Turbine Bypass Valves fail closed.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (7)APRM F, 171 airlock, Stm Packing Exh.,Turb trip, ATWS, Master Controller, Turb Bypass Valves.

Malfunctions after EOP entry (1-2) (2) Feedwater Master Controller, Turbine Bypass Valves Abnormal Events (2-4) (2) AOP-2,AOP-3 Major Transients (1-2) (1) ATWS EOPs entered (1-2) (2) EOP-1, EOP-2 EOP contingencies (0-2) (1) EOP-1A Critical Tasks (2-3) (2) Terminate injection to <-56, Begin control rod insertion

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 2 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 100% power, Division 1 work week, Div 1 DG tagged out Turnover: Shift Priorities: 1) Alternate HDL Pumps from A to B due to report of seal leakage on A. 2)

Run STP-402-0201 for scheduled surveillance.

Event Malf. Event Event No. No. Type* Description 1 NA N (CRS,ATC) Alternate HDL Pumps from A to B due to reported seal leakage.

N (CRS,BOP) Run STP-402-0201, MAIN CONTROL ROOM A/C TRAIN A OPERABILITY 2 NA TEST for scheduled surveillance.

CRDM2809 R(ATC) 3 (Tech Spec) Control Rod Drop - Control Rod 28-09 Uncoupled C(CRS)

C 4 CRD001A (CRS,BOP) (Tech Spec) CRD pump trip 5 FWS001A C (CRS, ATC) Feedwater A pump trip 6 ED004F C (ALL) Trip of NJS-LDC1F/Loss of Feed/Reactor Scram RCS007 Coolant leak in the drywell with loss of power to E22-F004 and trip of RCIC E22MOV F004 M (ALL) 7 BREAKER TRIP RCIC001 ED003H ENS-SWG1A bus loss, RHR B fails to auto start, E12-F042C injection valve fails.

8 RHR009B C (CRS,BOP)

RHR001C

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) Rod drop, CRD trip, Feedpump trip, NJS Bus, Leak, E12-F042C Malfunctions after EOP entry (1-2) (2) Leak, E12-F042C Abnormal Events (2-4) (3)AOP-0061, AOP-0006, AOP-0003 Major Transients (1-2) (1) Leak EOPs entered (1-2) (2) EOP-1, EOP-2 EOP contingencies (0-2) (2) Alternate Level Control, Emergency Depressurization Critical Tasks (2-3) (3) Insert control rod 28-09, Open SRVs to depressurize vessel, manually start RHR B.

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 3 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 100% power. Startup Feed Reg Valve in Augmentation Mode per SOP-0009 to support maintenance on Feed Reg Valve C. Feed Reg Valve C has been returned to service.

Downpower for sequence exchange this shift.

Turnover: Shift Priorities: 1)Remove Startup Feed Reg Valve from Augmentation Mode. 2)Start RHR B for STP-204-6302 and notify IST personnel when the pump is running at reference conditions.

3)Lower reactor power for sequence exchange per the reactivity control plan while field personnel gather data following RHR B pump start.

Event Malf. Event Event No. No. Type* Description Remove Startup Feedwater Regulating Valve from Augmentation Mode and 1 NA N (CRS,ATC) place in standby 2 NA N (CRS,BOP) Perform STP-204-6302 Section 7.1, RHR B Quarterly Surveillance.

Lower reactor power with Reactor Recirculation flow in accordance with the 3 NA R(ATC)

Reactivity Control Plan Step 1.

4 RHR002B C(CRS,BOP) (Tech Spec) RHR B trips DI-CNM- Feedwater Pump A minimum flow valve fails open.

5 HA68A- C(CRS,ATC)

CAM 6 RCIC005 I(CRS,BOP) (Tech Spec) Inadvertent RCIC initiation.

RCIC004 RCIC steam supply line break in the RCIC Room and Main Steam Tunnel with failure of RCIC Steam Supply Valves fail to isolate. Auto scram signals fail.

7 RCIC006 M(ALL)

RPS001B MSS008G Three Safety Relief Valves fail to energize when required for emergency depressurization.

8 MSS008D C(CRS,BOP)

MSS008I 9 FWS005A C(CRS,ATC) Startup Feedwater Regulating Valve fails closed.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) RHR B trip, A min flow, RCIC initiation, RCIC steam leak, SRV failure, Startup Reg Valve Failure Malfunctions after EOP entry (1-2) (2) SRV failure, Startup Reg Valve Abnormal Events (2-4) (2) AOP-0006-Min flow failure, AOP-0003-Steam Leak Major Transients (1-2) (1) Steam leak with failure to isolate affecting multiple areas EOPs entered (1-2) (2) EOP-1, EOP-3 EOP contingencies (0-2) (1) Emergency Depressurization Critical Tasks (2-3) (2) Place the mode switch in shutdown, Emergency Depressurize when more than one area exceeds Max Safe Temp or Rad Levels.

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 4 Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 75% power.

Turnover: Shift Priorities: 1) Start Feedwater Pump A 2) Continue power ascension with recirc flow per reactivity control plan. 3) Transfer Steam Seal Evaporator to Extraction Steam.

Event Malf. No. Event Type* Event No. Description 1 NA N (SRO, ATC) Start a Reactor Feedwater Pump A 2 NA R (ATC) Raise reactor power with reactor recirculation flow 3 NA N (SRO-BOP) Transfer Steam Seal Evaporator to Extraction Steam 4 RMS016A I(SRO) (Technical Specification) Failure of RMS-RE16A Drywell Radiation Monitor 5 ED004Q C (SRO, BOP) (Technical Specification) Loss of EJS-LDC2B 6 FWS016A I(SRO,ATC) Feedwater flow input to Feedwater Level Control failure 7 ED001 M (ALL) Loss of offsite power 8 RCIC003A C(SRO,BOP) RCIC Flow controller fails low SWP-P2A SWP-P2A pump breaker trip 9 C(SRO,ATC)

BKR TRIP

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (5-8) (6) EJS-LDC2B, RMS-RE16A, FWLC input, Loss of Offsite power, RCIC controller, SWP-P2A Malfunctions after EOP entry (1-2) (2) RCIC controller, SWP-P2A Abnormal Events (2-4) (2) AOP-0006, AOP-0001 Major Transients (1-2) (1) Loss of offsite power EOPs entered (1-2) (1) EOP-0001 EOP contingencies (0-2) (1 potential) Alternate Level Control Critical Tasks (2-3) (2) Take manual control of FW, Maintain reactor water level >-162 with RCIC

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Bend Station____ Date of Examination: 11/12/2012 Examination Level: RO ; SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

(A1) Determine when Hot Shutdown Boron has been Conduct of Operations R,M injected into the core.

KA 2.1.25; IR 3.9 (A2) Determine maintenance requirements of an active Conduct of Operations R,N license.

KA 2.1.4; IR 3.3 (A3) Use plant drawings to determine the effect of Equipment Control R,M removing a fuse.

KA 2.2.15; IR 3.9 (A4) Obtain radiological information from a survey map.

Radiation Control R,N KA 2.3.7; IR 3.5 Emergency Procedures/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 all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

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

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

Rev 0

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Bend Station____ Date of Examination: 11/12/2012 Examination Level: RO SRO ; Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

(A5) Generate a manual LCO tracking sheet.

Conduct of Operations R,M KA 2.1.18; IR 3.8 (A6) Determine Plant Safety Index during shutdown Conduct of Operations R,D conditions KA 2.1.23; IR 4.4 (A7) Review and Approve a Completed Surveillance Equipment Control R,M Test Procedure.

KA 2.2.12; IR 4.1 (A8) Calculate Maximum Permissible Stay Time Radiation Control R,M KA 2.3.7; IR 3.6 (A9) Classify an Emergency.

Emergency Procedures/Plan R,M KA 2.4.41; IR 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) 1 (N)ew or (M)odified from bank ( 1) 4 (P)revious 2 exams ( 1; randomly selected) 0 Rev 1

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: River Bend Station Date of Examination: 11/12/2012 Exam Level: RO ; SRO-I SRO-U Operating Test No.: ______________

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

a. (S1) Respond to High Radiation levels in the Auxiliary Building A,S,EN,N 5

b. (S2) Transfer Reactor Recirculation Pumps from Fast to Slow Speed A,S,D 1

c. (S3) Manual Isolation of a Main Steam Line During Power Operation S,D 3

d. (S4) Shift Divisions of Control Building Chilled Water A,S,D,EN 9

e. (S5) Secure High Pressure Core Spray Following Spurious Initiation A,S,D,EN 2

f. (S6) Start Residual Heat Removal in the Shutdown Cooling Mode S,D,L 4

g. (C1) Respond to a loss of Control Room Annunciators C,N 6

h. (C2) Perform APRM Setdown Channel Functional Test for APRM B C,N 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Transfer RCIC Steam Supply Isolation Valve to Alternate Power E,L,N,R 2

j. (P2) Start of Fire Protection Water Pump A,D,E 8

k. (P3) Initiate Full Scram and NSSSS Isolation from the Electrical D,E,EN 7 Protection Assembly (EPA) breakers

@ 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 5; (C)ontrol room (D)irect from bank 9 / 8 / 4 8; (E)mergency or abnormal in-plant 1 / 1 / 1 2; (EN)gineered safety feature - / - / 1 (control room system) -

(L)ow-Power / Shutdown 1 / 1 / 1 3; (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 4; 1(A) ;

(P)revious 2 exams 3 / 3 / 2 (randomly selected) 0 (R)CA 1 / 1 / 1 1; (S)imulator Rev 0

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: River Bend Station Date of Examination: 11/12/2012 Exam Level: RO SRO-I SRO-U ; Operating Test No.: ______________

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

a. (S1) Respond to High Radiation levels in the Auxiliary Building A,S,EN,N 5

b. (S4) Shift Divisions of Control Building Chilled Water A,S,D,EN 9

c. (C1) Respond to a loss of Control Room Annunciators C,N 6 d.

e.

f.

g.

h.

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Transfer RCIC Steam Supply Isolation Valve to Alternate Power E,L,N,R 2

j. (P2) Start of Fire Protection Water Pump A,D,E 8 k.

@ 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 3; (C)ontrol room (D)irect from bank 9 / 8 / 4 2; (E)mergency or abnormal in-plant 1 / 1 / 1 2; (EN)gineered safety feature -/ - / 1 (control room system) 2; (L)ow-Power / Shutdown 1 / 1 / 1 2; (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 3; 1(A);

(P)revious 2 exams 3/ 3 / 2 (randomly selected) 0; (R)CA 1 / 1 / 1 1; (S)imulator Rev 0

ES-401 BWR Examination Outline (RBS RO) Form ES-401-1 Facility: Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 3 4 4 3 3 3 20 Emergency &

Abnormal Plant 2 1 1 1 N/A 2 1 N/A 1 7 Evolutions Tier Totals 4 5 5 5 4 4 27 1 2 2 2 2 2 3 2 3 3 2 3 26 2.

Plant 2 2 1 1 1 1 1 1 1 1 1 1 12 Systems Tier Totals 4 3 3 3 3 4 3 4 4 3 4 38

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 3 3 2 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 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/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 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 10 CFR 55.43.

Rev 1

S-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced X K2.06 - knowledge of the interrelationships between 3.8 1 Core Flow Circulation / 1 & 4 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULAION: Reactor Power. (41.7) 295003 Partial or Complete Loss of AC / 6 X K3.02 - Knowledge of the reasons for the following 2.9 2 responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Selective tripping. (41.5) 295004 Partial or Total Loss of DC Pwr / 6 X A1.01 - Ability to operate and/or monitor the following 3.3 3 as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: D.C. Electrical distribution systems.

(41.7) 295005 Main Turbine Generator Trip / 3 X A.2.01 - Ability to determine and/or interpret the 2.6 4 following as they apply to MAIN TURBINE GENERATOR TRIP: Turbine speed. (41.10) 295006 SCRAM / 1 X 2.4.46 - Ability to verify that the alarms are consistent 4.2 5 with the plant conditions. SCRAM (41.10) 295016 Control Room Abandonment / 7 X K2.03 - Knowledge of the interrelations between the 2.9 6 CONTROL ROOM ABANDONMENT and the following: Control Room HVAC. (41.5) 295018 Partial or Total Loss of CCW / 8 X K1.01 - Knowledge of the operational implications of the 3.5 7 following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLOING WATER: Effects on component/system operation. (41.8) 295019 Partial or Total Loss of Inst. Air / 8 X K3.02 - Knowledge of the reasons for the following 3.5 8 responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Standby air compressor operation. (41.5) 295021 Loss of Shutdown Cooling / 4 X K2.03 - Knowledge of the interrelations between LOSS 3.6 9 OF SHUTDOWN COOLING and RHR Shutdown Cooling (41.7) 295023 Refueling Acc / 8 X A.1.02 - Ability to operate and/or monitor the following 2.9 10 as they apply to REFUELING ACCIDENTS: Fuel pool cooling and cleanup system. (41.7) 295024 High Drywell Pressure / 5 X A2.06 - Ability to determine and/or interpret the 4.1 11 following as they apply to HIGH DRYWELL PRESSURE: Suppression pool temperature. (41.10) 295025 High Reactor Pressure / 3 X 2.1.32 - Ability to explain and apply system limits and 3.8 12 precautions: High Reactor Pressure. (41.10) 295026 Suppression Pool High Water X K1.02 - Knowledge of the operational implications of the 3.5 13 Temp. / 5 following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Steam Condensation. (41.8) 295027 High Containment Temperature / 5 Mark III only 295028 High Drywell Temperature / 5 X K3.01 - Knowledge of the reasons for the following 3.6 14 responses as they apply to HIGH DRYWELL TEMPERATURE: Emergency Depressurization (41.5) 295030 Low Suppression Pool Wtr Lvl / 5 X A1.03 - Ability to operate and/or monitor the following 3.4 15 as they apply to LOW SUPPRESSION POOL WATER LEVEL: HPCS (41.7)

295031 Reactor Low Water Level / 2 X A2.03 - Ability to determine and/or interpret the 4.2 16 following as they apply to REACTOR LOW WATER LEVEL: Reactor Pressure. (41.10) 295037 SCRAM Condition Present X 2.2.37 - Ability to determine operability and/or 3.6 17 and Reactor Power Above APRM availability of safety related equipment: (41.7)

Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 X K1.01 - Knowledge of the operational implications of the 2.5 18 following concepts as they apply to HIGH OFF-SITE RELEASE RATE: Biological effects of radioisotope injestion. (41.8).

600000 Plant Fire On Site / 8 X K2.04 - Knowledge of the interrelations between Plant 2.5 19 Fire on Site and the following: Breakers, relays and disconnects.

700000 Generator Voltage and Electric Grid X K3.01 - Knowledge of the reasons for the following 3.9 20 Disturbances / 6 responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Reactor and turbine trip criteria. (41.4,5 or 7)

K/A Category Totals: 3 4 4 3 3 3 Group Point Total: 20

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 A1.05 - Ability to operate and/or monitor the following as 295007 High Reactor Pressure / 3 X they apply to HIGH REACTOR PRESSURE: 3.7 21 Reactor/turbine pressure regulating system (41.7) 295008 High Reactor Water Level / 2 A2.02 - Ability to determine and/or interpret the following 295009 Low Reactor Water Level / 2 X as they apply to LOW REACTOR WATER LEVEL : Steam 3.6 22 flow/feed flow mismatch (41.10) 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 K2.01: Knowledge of the interrelations between HIGH 295013 High Suppression Pool Temp. / 5 X SUPPRESSION POOL TEMPERATURE and the 3.6 23 following: Suppression pool cooling (41.7) 295014 Inadvertent Reactivity Addition / 1 K3.01 - Knowledge of the reasons for the following 295015 Incomplete SCRAM / 1 X responses as they apply to INCOMPLETE SCRAM : 3.4 24 Bypassing rod insertion blocks

( (41.5 )

295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 2.1.28 - Knowledge of the purpose and function of major 295022 Loss of CRD Pumps / 1 X system components and controls. (41.7) 4.1 25 295029 High Suppression Pool Wtr Lvl / 5 A1.03 - Ability to operate and/or monitor the following as 295032 High Secondary Containment X they apply to HIGH SECONDARY CONTAINMENT 3.7 26 Area Temperature / 5 AREA TEMPERATURE : Secondary containment ventilation (41.7 )

295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 K1 Knowledge of the operational implications of the 295035 Secondary Containment High X following concepts as they apply to SECONDARY 3.9 27 Differential Pressure / 5 CONTAINMENT HIGH DIFFERENTIAL PRESSURE

Secondary Containment Integrity (41.8 to 41.10) 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5

K/A Category Point Totals: 1 1 1 2 1 1 Group Point Total: 7 ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A2.09 - Ability to (a) predict the impacts of the 203000 RHR/LPCI: Injection X following on the RHR/LPCI: INJECTION MODE 3.3 28 Mode (PLANT SPECIFIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow (

41.5)

A3.03 - Ability to monitor automatic operations of 205000 Shutdown Cooling X the SHUTDOWN COOLING SYSTEM (RHR 3.5 29 SHUTDOWN COOLING MODE) including:

Lights and alarms (41.7) 206000 HPCI Suppressed K/A 207000 Isolation (Emergency) Suppressed K/A Condenser A4.03 - Ability to manually operate and/or 209001 LPCS X monitor in the control room: Injection valves 3.7 30 (41.7) 2.2.22 Knowledge of limiting conditions for 209002 HPCS X operations and safety limits. (41.5) 4.0 31 K1.07 - Knowledge of the physical connections 211000 SLC X and/or cause/effect relationships between 2.6 32 STANDBY LIQUID CONTROL SYSTEM and the following: Jet pump differential pressure indication: Plant-Specific (41.2 to 41.9)

K2.01 - Knowledge of electrical power supplies to 212000 RPS X the following: RPS motor-generator sets (41.7) 3.2 33 K3.01 - Knowledge of the effect that a loss or 215003 IRM X malfunction of the INTERMEDIATE RANGE 3.9 34 MONITOR (IRM) SYSTEM will have on following: RPS (41.7)

K4.05 - Knowledge of SOURCE RANGE 215004 Source Range Monitor X MONITOR (SRM) SYSTEM design feature(s) 2.5 35 and/or interlocks which provide for the following: Alarm seal-in (41.7)

K5.05 - Knowledge of the operational implications 215005 APRM / LPRM X of the following concepts as they apply to 3.6 36 AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM : Core flow effects on APRM trip setpoints (41.5)

K6.03 - Knowledge of the effect that a loss or 217000 RCIC X malfunction of the following will have on the 3.5 37 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) : Suppression pool water supply (41.7)

A1.04 - Ability to predict and/or monitor changes 218000 ADS X in parameters associated with operating the 4.1 38 AUTOMATIC DEPRESSURIZATION SYSTEM controls including: Reactor pressure (41.5 )

A2.09 - Ability to (a) predict the impacts of the 223002 PCIS/Nuclear Steam X following on the PRIMARY CONTAINMENT 3.6 39 Supply Shutoff ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation (41.5)

A3.06 - Ability to monitor automatic operations of 239002 SRVs X the RELIEF/SAFETY VALVES including: 4.1 40 Reactor pressure (41.7 )

A4.01 - Ability to manually operate and/or 259002 Reactor Water Level X monitor in the control room: All individual 3.8 41 Control component controllers in the manual mode (41.7 )

2.4.2 - Knowledge of system setpoints, interlocks 261000 SGTS X and automatic actions associated with EOP entry. 4.5 42 (41.7)

K1.03 - Knowledge of the physical connections 262001 AC Electrical Distribution X and/or cause/effect 3.4 43 relationships between A.C. ELECTRICAL DISTRIBUTION and the following: Off-site power sources (41.2 to 41.9) 262002 UPS (AC/DC) X K3.01. Knowledge of the effect that a loss or 3.1 44 malfunction of the Uninterruptible Power Supply (AC/DC) will have on Water Level Control K2.01 - Knowledge of electrical power supplies to 263000 DC Electrical Distribution X the following: Major D.C. loads (CFR: 41.7) 3.1 45 K4.04 - Knowledge of EMERGENCY 264000 EDGs X GENERATORS (DIESEL/JET) design feature(s) 2.6 46 and/or interlocks which provide for the following:

Field flashing (CFR: 41.7)

K5.01 - Knowledge of the operational implications 300000 Instrument Air X of the following concepts as they apply to the 2.5 47 INSTRUMENT AIR SYSTEM: Air compressors (41.5)

K6.05 - Knowledge of the effect that a loss or 400000 Component Cooling Water X malfunction of the following will have on the 2.8 48 CCWS: Motors (41.7)

A1.01 - Ability to predict and/or monitor changes 203000 RHR/LPCI: Injection X in parameters associated with operating the 4.2 49 Mode RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) controls including: Reactor water level (41.5)

A2.06 - Ability to (a) predict the impacts of the 212000 RPS X following on the REACTOR PROTECTION 4.1 50 SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High reactor power (41.5)

A3.03 - Ability to monitor automatic operations of 262001 AC Electrical Distribution X the A.C. ELECTRICAL DISTRIBUTION 3.4 51 including: Load shedding (41.7)

K6.02 Knowledge of the effect that a loss or 262002 UPS (AC/DC) X malfunction of the following will have on the 2.8 52 Uninterruptible Power Supply (AC/DC) DC electrical power (41.7) 2.1.7 - Ability to evaluate plant performance and 400000 Component Cooling Water X make operational judgments based on operating 4.4 53 characteristics, reactor behavior, and instrument interpretation. +(41.5)

K/A Category Point Totals: 2 2 2 2 2 3 2 3 3 2 3 Group Point Total: 26

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K1.01 - Knowledge of the physical 201001 CRD Hydraulic X connections and/or cause/effect 3.1 54 relationships between CONTROL ROD DRIVEHYDRAULIC SYSTEM and the following: Condensate system (41.2 to 41.9) 201002 RMCS Suppressed K/A K3.01 - Knowledge of the effect that a loss 201003 Control Rod and Drive X or malfunction of the CONTROL ROD 3.2 55 Mechanism AND DRIVE MECHANISM will have on following: Reactor power

( 41.7 )

201004 RSCS Suppressed K/A 201005 RCIS 201006 RWM Suppressed K/A 202001 Recirculation K2.02 - Knowledge of electrical power 202002 Recirculation Flow Control X supplies to the following: Hydraulic power 2.6 56 unit: Plant-Specific (CFR: 41.7) 204000 RWCU 214000 RPIS Suppressed K/A 215001 Traversing In-core Probe 215002 RBM Suppressed K/A K4.09 - Knowledge of NUCLEAR BOILER 216000 Nuclear Boiler Inst. X INSTRUMENTATION design feature(s) 3.3 57 and/or interlocks which provide for the following: Protection against filling the main steam lines from the feed system (41.7)

K5.04 - Knowledge of the operational 219000 RHR/LPCI: Torus/Pool X implications of the following concepts as 2.9 58 Cooling Mode they apply to RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE : Heat exchanger operation ( 41.5)

K6.13 - Knowledge of the effect that a loss 223001 Primary CTMT and Aux. X or malfunction of the following will have on 3.2 59 the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES : Applicable plant air system/ nitrogen make-up system (41.7) 226001 RHR/LPCI: CTMT Spray Suppressed K/A Mode 230000 RHR/LPCI: Torus/Pool Spray Suppressed K/A Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator

245000 Main Turbine Gen. / Aux.

A1.01 - Ability to predict and/or monitor 256000 Reactor Condensate X changes in parameters associated with 2.9 60 operating the REACTOR CONDENSATE SYSTEM controls including: System flow (41.5) 259001 Reactor Feedwater 268000 Radwaste A2.03 - Ability to (a) predict the impacts of 271000 Offgas X the following on the OFFGAS SYSTEM ; 3.5 61 and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Main steamline high radiation (41.5)

A3.10 - Ability to monitor automatic 272000 Radiation Monitoring X operations of the RADIATION 3.3 62 MONITORING SYSTEM including: Lights and alarms (41.7 )

A4.04 - Ability to manually operate and/or 286000 Fire Protection X monitor in the control room: Fire main 2.8 63 pressure: Plant-Specific (41.7) 2.4.11 Knowledge of abnormal condition 288000 Plant Ventilation X procedures. (41.10) 4.0 64 K1.06 - Knowledge of the physical 290001 Secondary CTMT X connections and/or cause/effect 3.4 65 relationships between SECONDARY CONTAINMENT and the following:

Auxiliary building isolation: BWR-6 (41.2 to 41.9) 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals: 2 1 1 1 1 1 1 1 1 1 1 Group Point Total: 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3)(RBS RO) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

Ability to interpret and execute procedure steps.(41.10) 2.1.20 4.6 66 Ability to interpret reference materials, such as graphs, 2.1.25 3.9 67

1. curves, tables, etc. (41.10)

Conduct Ability to locate and operate components, including local of Operations 2.1.30 4.4 68 controls. (41.7)

Subtotal 3 Ability to analyze the effect of maintenance activities, 2.2.36 3.1 69 such as degraded power sources, on the status of limiting conditions for operations. (41.10)

2. Ability to apply Technical Specifications for a system.

2.2.40 3.4 70 Equipment (41.10)

Control Ability to interpret control room indications to verify the 2.2.44 4.2 71 status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (41.5)

Subtotal 3 Knowledge of radiation exposure limits under normal or 2.3.4 3.2 72 emergency conditions.

(41.12)

3. Knowledge of radiation or contamination hazards that 2.3.14 3.4 73 Radiation may arise during normal, abnormal, or emergency Control conditions or activities. (41.12)

Subtotal 2 Knowledge of EOP entry conditions and immediate action 2.4.1 4.6 74 steps. (41.10)

4. Ability to prioritize and interpret the significance of each 2.4.45 4.1 75 Emergency annunciator or alarm.

Procedures / (41.10)

Plan Subtotal 2 Tier 3 Point Total 10

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 295028 K3.05 There is no correlation between this Emergency Plant Evolution and this category. Re-selected 295028 K3.01. (Q#14) 2/1 261000 G 2.4.49 There are no immediate actions associated with this plant system.

Re-selected 261000 G 2.4.2 (Q#42) 2/1 262002 A4.01 There are no controls, nor indications in the main control room for this system. Re-selected 262002 K6.02 (Q#52)

ES-401 BWR Examination Outline (RB SRO) Form ES-401-1 Facility: Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 4 3 7 Emergency &

Abnormal Plant 2 N/A N/A 1 2 3 Evolutions Tier Totals 5 5 10 1 3 2 5 2.

Plant 2 1 2 3 Systems Tier Totals 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 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 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).