ML110450222

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2010-12-Final Operating Test Outlines
ML110450222
Person / Time
Site: River Bend Entergy icon.png
Issue date: 12/10/2010
From:
NRC Region 4
To:
References
50-458/10-12, ES-301
Download: ML110450222 (17)
v • d • e


Text

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Bend Station Date of Examination: 12/6/2010 Examination Level: RO SRO Operating Test Number: __________

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

(A1) Determine corrected Fuel Zone Level indication Conduct of Operations and determine whether or not adequate core cooling R,N exists.

KA 2.1.25 IR 3.9 (A2) Using core monitor print out, determine if thermal Conduct of Operations limits are in spec.

R,D KA 2.1.20 IR 4.6 (A3) Identify components and sequence for a tagout on Equipment Control HVN-STR1B, TURBINE BLDG PUMP 1A SUCTION R,M STRAINER KA 2.2.13 IR 4.1 (A4) Perform a dose assessment and determine Radiation Control acceptability of an RWP.

R,M 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 1

NRC ES-301 Administrative Topics Outline Form ES-301-1 Facility: River Bend Station Date of Examination: 12/6/2010 Examination Level: RO SRO Operating Test Number: __________

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

(A5) Determine time to 200°F and whether or not a Conduct of Operations Recirc Pump may be secured.

R,M KA 2.1.25 IR 4.2 (A6) Given a personnel list and their qualification status, Conduct of Operations determine if minimum staffing requirements are met.

R,M KA 2.1.5 IR 3.9 (A7) Review a tag out of LOS-STR1, TURBINE LUBE Equipment Control OIL TRANSFER PUMP SUCTION HEADER R,D STRAINER.

KA 2.2.13 IR 4.3 (A8) Review a liquid radwaste release permit issued by Radiation Control Chemistry.

R,D KA 2.3.6 IR 3.8 (A9) Determine Protective Action Recommendations.

Emergency Procedures/Plan R,M KA 2.4.44 IR 4.4 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 1

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: River Bend Station Date of Examination: 12/6/2010 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 (S1) Shift Stator Cooling Water Pumps A,D,S 4 (S2) Start LPCS in Sup Pool to Sup Pool Lineup w/ pump trip A,D,S,EN 2 (S3) Start Drywell Low Vol purge to vent the drywell A,EN,N,L 9 (S4) Shift CRD Pumps with trip of on-coming pump A,M,S 1 (S5) Restore Offsite power with AOP-0004 D,L,S 6 (S6) Perform Rod Withdrawal Limiter Surveillance (> HPSP) N,S 7 (C1) Defeat RWCU Level 2 and SLC Initiation Isolation Interlocks C,D,EN,L 5 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

(P1) Inject into the RPV with Fire Water. E,L,M,R 8 (P2) Startup RPS MG Set B with failure to achieve voltage A,M 7 (P3) Place RHR in Sup Pool Cooling mode from Div 2 RSS D,E,L 5

@ 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 (EN)gineered safety feature - / - / 1 (control room system)

(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 Rev 0

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: River Bend Station Date of Examination: 12/6/2010 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 (S1) Shift Stator Cooling Water Pumps A,D,S 4 (S2) Start LPCS in Sup Pool to Sup Pool Lineup w/ pump trip A,D,S,EN 2 (S3) Start Drywell Low Vol purge to vent the drywell A,EN,N,L 9 (S4) Shift CRD Pumps with trip of on-coming pump A,M,S 1 (S5) Restore Offsite power with AOP-0004 D,L,S 6 (S6) Perform Rod Withdrawal Limiter Surveillance (> HPSP) N,S 7 (C1) Defeat RWCU Level 2 and SLC Initiation Isolation Interlocks C,D,EN,L 5 (C2) Stuck open SRV fuse removal per AOP-0035 C,D 3 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

(P1) Inject into the RPV with Fire Water. E,L,M,R 8 (P2) Startup RPS MG Set B with failure to achieve voltage A,M 7 (P3) Place RHR in Sup Pool Cooling mode from Div 2 RSS D,E,L 5

@ 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 (EN)gineered safety feature - / - / 1 (control room system)

(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 Rev 0

NRC ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: River Bend Station Date of Examination: 12/6/2010 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 (S1) Shift Stator Cooling Water Pumps A,D,S 4 (S2) Start LPCS in Sup Pool to Sup Pool Lineup w/ pump trip A,D,S,EN 2 (C1) Defeat RWCU Level 2 and SLC Initiation Isolation Interlocks C,D,EN,L 5 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

(P1) Inject into the RPV with Fire Water. E,L,M,R 8 (P2) Startup RPS MG Set B with failure to achieve voltage A,M 7

@ 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 (EN)gineered safety feature - / - / 1 (control room system)

(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 Rev 0

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station_______________ Scenario No.: __1____ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 99% power. Preparing for down power for sequence exchange.

EOOS STATUS = 10 GREEN PROTECTED EQUIPMENT DIV I and RCIC DIV III work week. High Pressure Core Spray is available but not operable until the breaker functional is complete.

Turnover: Complete breaker functional per SOP on the High Pressure Core Spray breaker. The pre-start checks have been completed satisfactory. Lower power per GOP-5 Power Maneuvering and the approved reactivity control plan.

Event Malf. No. Event Event No. Type* Description 1 N Perform High Pressure Core Spray Pump Breaker Functional per SOP.

(BOP,SRO) 2 R(ATC) Lower reactor power with control rods.

3 RCIC009 I (BOP,SRO) Spurious RCIC Isolation. (Technical Specifications)

RCIC007 E51-F063 RCIC Steam Supply Inboard Isolation Valve fails to auto close 4 B21005 I (SRO) B21-PTN078A RPV pressure transmitter fails high. (Technical Specifications) 5 GMC002A C Stator Cooling Pump A trips, Stby pump fails to AUTO start (BOP,SRO) requiring manual start.

GMC001B 6 GMC002B C (ALL) Second Stator Cooling Pump trips / Reactor Scram 7 RPS001A M (ALL) RPS Fails to Scram - All Signals 8 FWS004A C (ATC,SRO) Feedwater Master Controller output fails low 9 EHC002A C (ATC,SRO) Main Turbine Bypass Valves fail OPEN.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8): (8) RCIC, E51-MOVF063, B21-PTN078A, Stator Cooling Pumps A & B, ATWS, FWS Controller, BPVs Malfunctions after EOP entry: (1-2) (2) FWS, BPVs Abnormal events: (2-4): (2) (AOP-3, AOP-1)

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 FW injection, Begin control rod insertion.

Rev 02

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station_______________ Scenario No.: __2____ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1 75% power. Down power in progress. Feedwater pump C is shutdown.

EOOS STATUS 10 GREEN(9.8 GREEN when the FWS pump is tagged) PROTECTED EQUIPMENT DIV I work week DIV II protected.

Turnover: Perform STP-406-0201, DIVISION I FUEL BUILDING HVAC CHARCOAL FILTER A OPERABILITY TEST. Section 6.0 has been completed. Raise reactor power per GOP-005 Power Maneuvering. FWS P1C is off and due to be tagged and drained this shift.

Event Malf. No. Event Event No. Type* Description 1 N (BOP,SRO) Perform STP-406-0201 Division I Fuel Building HVAC Charcoal Filter A Operability Test 2 R (ATC) Raise reactor power with reactor recirculation flow.

3 ED004K C (SRO) Loss of NJS-LDC1K 480 VAC Load Center (Technical Specification).

4 RMS013A C (SRO) RMS-RE13A Control Building Local Intake Monitor fails upscale.(Technical Specification) 5 C (BOP,SRO) HVC-AOD51A Control Room Isolation damper fails to isolate, but can be manually isolated.

6 CNM004A C (ATC,SRO) Condensate pump A trip 7 WCS006 M (ALL) RWCU leak in the Main Steam Tunnel 8 WCS004 C(BOP,SRO) G33-MOVF004 RWCU Pumps Outboard Isolation valve fails to WCS005 automatically isolate.

G33-MOVF001 RWCU Pumps Inboard Isolation valve fails to automatically isolate but can be manually isolated.

9 MGEN003 C(ATC,SRO) Main Generator reverse power relay fails.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8) (7) NJS-LDC1K, RMS-RE13A, HVC-AOD51A, CNM-P1A, RWCU leak, G33-MOVs, Main Turbine Malfunctions after EOP entry: (1-2) (2) G33-MOVs, Main Turbine Abnormal events: (2-4) (4) AOP-3, AOP-1, AOP-2, AOP-6 Major transients: (1-2) (1) Steam Tunnel leak EOPs entered: (1-2) (2) EOP-1, EOP-3 EOP contingencies: (0-2) (0)

Critical tasks: (2-3) (2) Isolate leak, Trip the main turbine Rev 02

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%, RCIC tagged out for pump repairs. EOOS STATUS 8.6 YELLOW.

DIV III protected. Non-Divisional work week Turnover: Perform STP-256-0202 Standby Cooling Tower Fan Operability. Perform OSP-0101 section 4.11.3 for the turning gear oil pump pressure switch replacement. .

Event Malf. No. Event Event No. Type* Description 1 N Perform OSP-0101 Turbine Generator Periodic Testing Section (SRO,ATC) 4.11.3 2 N Perform STP-256-0202 Division II Standby Cooling Tower Fans (SRO,BOP) Operability Test. Bank 1 fans only.

3 FWS012 R(ATC) Loss of Extraction Steam to Feedwater Heater 4 C HVR-UC1A Containment Unit Cooler trips. (Technical (SRO,BOP) Specifications) 5 CRDM1617 I (SRO,ATC) Control Rod 16-17 Drifts out (Technical Specifications).

6 CCP001B C CCP Component Cooling Water Pump B trips, CCP Component (SRO,BOP) Cooling Water Pump A fails to Auto start CCP004A ED001 M(ALL)

Station Blackout 7

  • Loss of offsite power EDG001A
  • Div 1 DG trips EDG002B
  • Div 2 DG fails to start 8 SWP004 C SWP-AOV599 Standby Cooling Tower Inlet Valve fails to auto (SRO,BOP) open.

9 HPCS003 C High Pressure Core Spray fails to automatically initiate (Pump only, (SRO,BOP) DG starts on LOP to require SWP-AOV599 actions).

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8) (7) Feedwater Heating, HVR UC, Rod Drift, CCP, SBO, SWP-AOV599, HPCS Malfunctions after EOP entry: (1-2) (2) SWP-AOV599, HPCS Abnormal events: (2-4) (2) AOP-1, AOP-50 Major transients: (1-2) (1) SBO EOPs entered: (1-2) (2) EOP-1, EOP-2 EOP contingencies: (0-2) (1) Alternate Level Control Critical tasks: (2-3) (2) Open SWP-AOV599, Maintain Adequate Core Cooling with HPCS Rev 02

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%, RCIC tagged out for pump repairs. EOOS STATUS 8.6 YELLOW.

DIV III protected. Non-Divisional work week Turnover: Perform STP-256-0202 Standby Cooling Tower Fan Operability. Perform OSP-0101 section 4.11.3 for the turning gear oil pump pressure switch replacement. .

Event Malf. No. Event Event No. Type* Description 1 N Perform OSP-0101 Turbine Generator Periodic Testing Section (SRO,ATC) 4.11.3 2 N Perform STP-256-0202 Division II Standby Cooling Tower Fans (SRO,BOP) Operability Test. Bank 1 fans only.

3 FWS012 R(ATC) Loss of Extraction Steam to Feedwater Heater 4 C HVR-UC1A Containment Unit Cooler trips. (Technical (SRO,BOP) Specifications) 5 CRDM1617 I (SRO,ATC) Control Rod 16-17 Drifts out (Technical Specifications).

6 CCP001B C CCP Component Cooling Water Pump B trips, CCP Component (SRO,BOP) Cooling Water Pump A fails to Auto start CCP004A ED001 M(ALL)

Station Blackout 7

  • Loss of offsite power EDG001A
  • Div 1 DG trips EDG002B
  • Div 2 DG fails to start 8 SWP004 C SWP-AOV599 Standby Cooling Tower Inlet Valve fails to auto (SRO,BOP) open.

9 HPCS003 C High Pressure Core Spray fails to automatically initiate (Pump only, (SRO,BOP) DG starts on LOP to require SWP-AOV599 actions).

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8) (7) Feedwater Heating, HVR UC, Rod Drift, CCP, SBO, SWP-AOV599, HPCS Malfunctions after EOP entry: (1-2) (2) SWP-AOV599, HPCS Abnormal events: (2-4) (2) AOP-1, AOP-50 Major transients: (1-2) (1) SBO EOPs entered: (1-2) (2) EOP-1, EOP-2 EOP contingencies: (0-2) (1) Alternate Level Control Critical tasks: (2-3) (2) Open SWP-AOV599, Maintain Adequate Core Cooling with HPCS Rev 02

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station_______________ Scenario No.: __4____ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 50% power. Plant startup in progress. GOP-0001 Step G.29. (2 FWS pumps in service.) EOOS = 10 GREEN. Non-divisional work week. Division III is Protected Turnover: Start HDL pumps A & C. Then raise power to 55% per reactivity control plan Step 90. Hold at 55% until chemistry is adequate to Pump Forward. Start RHR A in Sup Pool Cooling lineup to support system flush.

Event Malf. No. Event Event No. Type* Description 1 N (ALL) Start Heater Drain Pumps A & C in Recirc mode.

2 R(ATC) Raise power to 55% with control rods.

3 N Start RHR A Residual Heat Removal Pump in Suppression Pool (SRO,BOP) Cooling mode per SOP-0031 to support system flush to reduce dose rates in pump room.

4 RHR002A C RHR A Residual Heat Removal Pump trips. (Technical (SRO,BOP) Specifications) 5 RPS003B C (ALL) LOSS OF POWER TO RPS CHANNEL B 6 Overrides C (SRO) Containment Monitoring System H2 analyzer failure (Technical Specifications) 7 CNM006 M (ALL) Condensate filter high differential pressure. Total loss of feedwater.

RPS001C Reactor Scram. ARI inserts rods. HPCS failure.

8 RCIC001 C Reactor Core Isolation Cooling pump turbine trips, but can be (SRO,BOP) manually reset for level control.

9 MSS111P C MSS-MOV111/112 MSR Steam Supply Valve fails to isolate (SRO,BOP) causing uncontrolled pressure drop.

MSS112P

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8) (7) RHR A, RPS-B loss, CMS, CNM dp, RPS, RCIC, MSS Malfunctions after EOP entry: (1-2) (2) RCIC, MSS Abnormal events: (2-4) (3) AOP-1, AOP-2, AOP-10 Major transients: (1-2) (1) Loss of FW, HPCS injection valve failure EOPs entered: (1-2) (2) EOP-1, EOP-2 EOP contingencies: (0-2) (1) Alternate level control Critical tasks: (2-3) (3) Insert rods with ARI, Adequate core cooling with RCIC, Close MSIVs or MSS to avoid exceeding cooldown rate.

Rev 02

NRC RO ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: River Bend Station Date of Exam: 12/3/2010 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 4 4 3 4 2 20 0 0 0 Emergency &

Abnormal 2 0 1 0 N/A 1 3 N/A 2 7 0 0 0 Plant Evolutions Tier Totals 3 5 4 4 7 4 27 0 0 0 1 2 3 2 1 1 2 3 3 4 1 4 26 0 0 0 2.

Plant 2 2 1 3 2 1 1 0 0 1 1 0 12 0 0 0 0 Systems Tier Totals 4 4 5 3 2 3 3 3 5 2 4 38 0 0 0

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 0 Categories 2 2 3 3 0 0 0 0 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).

Note: 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.

Note: 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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

Note: 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.

Note: 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.

Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

Note: 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.

Note: 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.

Note: 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.

ES-401, Page 17 of 34 Rev 0

ES-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)

K K K A A K/A Topic(s)

Q# E/APE # / Name / Safety Function G IR #

1 2 3 1 2 Knowledge of the reasons for reactor scram as it applies to 295001 Partial or Complete Loss of Forced 0 Partial or Complete Loss of Forced Core Flow Circulation.

1 3.4 1 Core Flow Circulation / 1 & 4 4 Ability to evaluate plant performance and make operational

01. judgments based on operating characteristics, reactor behavior, 2 295003 Partial or Complete Loss of AC / 6 4.4 1 07 and instrument interpretation.

Ability to determine and interpret system lineups as it applies to 0 Partial or Total Loss of DC Power.

3 295004 Partial or Total Loss of DC Pwr / 6 3.2 1 4

Ability to operate and/or monitor reactor turbine pressure 0 regulating system as it applies to Main Turbine Generator Trip.

4 295005 Main Turbine Generator Trip / 3 3.6 1 5

Knowledge of the operational implications of reactivity control as 0 it applies to SCRAM.

5 295006 SCRAM / 1 3.7 1 3

Knowledge of local auxiliary operator tasks during an emergency

04. and the resultant operational effects.

6 295016 Control Room Abandonment / 7 3.8 1 35 295018 Partial or Total Loss of CCW / 8 0 Knowledge of the reasons for service air isolation as it applies to 0 Partial or Total Loss of Instrument Air.

7 295019 Partial or Total Loss of Inst. Air / 8 3.2 1 3

Ability to operate and/or monitor reactor recirculation as it applies 0 to Loss of Shutdown Cooling.

8 295021 Loss of Shutdown Cooling / 4 3 1 5

Ability to determine and interpret pool levels as it applies to refuel 0 accident.

9 295023 Refueling Acc / 8 3.4 1 2

Knowledge of the interrelations between High Drywell Pressure 0 and Emergency Generators.

10 295024 High Drywell Pressure / 5 3.9 1 6

Knowledge of the operational implications of pressure effects on 0 reactor power as it applies to High Reactor Pressure.

11 295025 High Reactor Pressure / 3 3.9 1 1

Knowledge of the operational implications of steam condensation 295026 Suppression Pool High Water 0 as it applies to Suppression Pool High Water Temperature.

12 3.5 1 Temp. / 5 2 Knowledge of the interrelations between High Containment 0 Temeprature and components internal to the containment.

13 295027 High Containment Temperature / 5 3.2 1 2

Knowledge of the interrelations between High Drywell 0 Temperature and reactor water level indication.

14 295028 High Drywell Temperature / 5 3.6 1 3

Ability to determine and interpret reactor pressure as it applies to 0 Low Suppression Pool Water Level.

15 295030 Low Suppression Pool Wtr Lvl / 5 3.7 1 3

Ability to determine and interpret adequate core cooling as it 0 applies to Reactor Low Water Level.

16 295031 Reactor Low Water Level / 2 4.6 1 4

Knowledge of the interrelations between SCRAM condition 295037 SCRAM Condition Present and 0 present and reactor power above APRM downscale or unknown 17 Reactor Power Above APRM Downscale or and ARI/RPT/ATWS. 4.1 1 3

Unknown / 1 Knowledge of the reasons for system isolations as it applies to 0 High Off-site Release Rate.

18 295038 High Off-site Release Rate / 9 3.9 1 2

Ability to operate and/or monitor plant and control room 0 ventilation systems as it applies to Plant Fire On Site.

19 600000 Plant Fire On Site / 8 3 1 5

Knowledge of the reasons for reactor and turbine trip criteria as it 700000 Generator Voltage and Electric Grid 0 applies to Generator Voltage and Electric Grid Disturbances.

20 3.9 1 Disturbances / 6 1 K/A Category Totals: 3 4 4 3 4 2 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)

K K K A A K/A Topic(s)

Q# E/APE # / Name / Safety Function G IR #

1 2 3 1 2 Ability to explain and apply system limits and precautions.

01.

21 295002 Loss of Main Condenser Vac / 3 3.8 1 32 295007 High Reactor Pressure / 3 0 Ability to determine and interpret steam flow feed flow mismatch 0 as it applies to High Reactor Water Level.

22 295008 High Reactor Water Level / 2 3.4 1 2

295009 Low Reactor Water Level / 2 0 295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 295012 High Drywell Temperature / 5 0 295013 High Suppression Pool Temp. / 5 0 Ability to operate and/or monitor recirculation flow control system 0 as it applies to Inadvertent Reactivity Addition.

23 295014 Inadvertent Reactivity Addition / 1 3.6 1 2

295015 Incomplete SCRAM / 1 0 Ability to determine and interpret readiation levels as it applies to 0 High Offsite Release Rate.

24 295017 High Off-site Release Rate / 9 3.1 1 3

295020 Inadvertent Cont. Isolation / 5 & 7 0 295022 Loss of CRD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 0 Knowledge of the interrelations between High Secondary 295032 High Secondary Containment Area 0 Containment Area Temperature and area room coolers.

25 3.5 1 Temperature / 5 1 Knowledge of how abnormal operating procedures are used in 295033 High Secondary Containment Area 04. conjunction with EOPs.

26 3.8 1 Radiation Levels / 9 08 295034 Secondary Containment Ventilation 0

High Radiation / 9 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 0

Sump/Area Water Level / 5 Ability to determine and interpret combustible limits for drywell as 0 it applies to High CTMT Hydrogen Concentration.

27 500000 High CTMT Hydrogen Conc. / 5 3.3 1 3

K/A Category Totals: 0 1 0 1 3 2 Group Point Total: 7 ES-401, Page 19 of 34

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A K/A Topic(s)

Q# System # / Name G IR #

1 2 3 4 5 6 1 2 3 4

04. Knowledge of the specific bases for EOPs.

28 203000 RHR/LPCI: Injection Mode 3.3 1 18 Ability to (a) predict the impact of SDC/RHR pump trips on 0 Shutdown Cooling and (b) based on those predictions, use 29 205000 Shutdown Cooling procedures to correct, control, or mitigate the consequences 3.4 1 6

of that abnormal operation.

206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser Knowledge of the effect that a loss or malfunction of the 0

30 209001 LPCS LPCS will have on ADS logic. 3.8 1 2

Knowledge of HPCS design feature(s) and or interlock(s) 0 which provide for preventing overfilling of the reactor 31 209002 HPCS 3.4 1 2 vessel.

Ability to predict and/or monitor changes in parameters associated with operating SLC controls including pump 0 0 discharge pressure.

32,33 211000 SLC 3.6; 4 2 3 6 Ability to monitor automatic operations of SLC including RWCU system isolation.

Knowledge of the operational implications of specific logic 0

34 212000 RPS arrangements as it applies to RPS. 3.3 1 2

Knowledge of the electrical power supplies to IRM channels/detectors.

0 0 Ability to predict and/or monitor changes in parameters 2.5; 35,36 215003 IRM 2 1 1 associated with operating IRMs controls including detector 3.4 position.

Ability to (a) predict the impact of degraded power supply on 0 the Source Range Monitor and (b) based on those 37 215004 Source Range Monitor predictions, use procedures to correct, control, or mitigate 2.7 1 1

the consequences of that abnormal operation.

Knowledge of the physical connections and/or cause-effect 0 relationships between APRM/LPRM and LPRM channels.

38 215005 APRM / LPRM 3.6 1 4

01. Ability to perform specific system and integrated plant 39 217000 RCIC procedures during all modes of plant operation. 4.3 1 23 Knowledge of the physical connections and/or cause-effect relationships between ADS and drywell/coontainment 0 01. pressures; Ability to explain and 3.9; 40,41 218000 ADS 2 4 32 apply system limits and precautions. 3.8 Ability to monitor automatic operations of Nuclear Steam Supply Shutoff including system indicating lights and 223002 PCIS/Nuclear Steam Supply 0 0 alarms. 3.4; 42,43 Ability to manually operate and/or monitor manually 2 Shutoff 1 2 initiation of the Nuclear Steam Supply Shutoff in the control 3.9 room.

Knowledge of the electrical power supplies to SRV 0

44 239002 SRVs solenoids. 2.8 1 1

Knowledge of the effect that a loss or malfunction of the 0 Reactor Water Level Control System will have on reactor 45 259002 Reactor Water Level Control 3.8 1 1 water level.

Ability to predict and/or monitor changes in parameters associated with operating SGTS controls including primary 0 02.

46,47 261000 SGTS containment pressure. 3.1; 4 2 2 22 Knowledge of limiting conditions for operations and safety limits.

Knowledge of the electrical power supplies to Offsite Power 0

48 262001 AC Electrical Distribution Sources. 3.3 1 1

Ability to (a) predict the impact of undervoltage on the UPS 0 and (b) based on those predictions, use procedures to 49 262002 UPS (AC/DC) correct, control, or mitigate the consequences of that 2.6 1 1

abnormal operation.

Ability to monitor automatic operations of DC Electrical 0 Distribution including meters, dials, recorders, alarms, and 50 263000 DC Electrical Distribution 3.2 1 1 indicating lights.

Ability to monitor automatic operations of EDGs including 0 automatic starting of compressor and emergency generator.

51 264000 EDGs 3 1 1

Knowledge of the effect that a loss or malfunction of filters 1

52 300000 Instrument Air will have on Instrument Air. 2.8 1 3

Knowledge of the effect that a loss or malfunction of heat 0 exchanges will have on Component Cooling Water.

53 400000 Component Cooling Water 2.9 1 6

0 K/A Category Totals: 2 3 2 1 1 2 3 3 4 1 4 Group Point Total: 26 ES-401, Page 20 of 34

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

K K K K K K A A A A K/A Topic(s)

Q# System # / Name G IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 0 201002 RMCS 0 201003 Control Rod and Drive Mechanism 0 201004 RSCS 0 0 Ability to manually operate and/or monitor RC&IS back panel 54 201005 RCIS 3 indicating lights in the control room. 3.4 1 201006 RWM 0 202001 Recirculation 0 Knowledge of the physical connections and/or cause-effect 1

55 202002 Recirculation Flow Control relationships between Recirculation Flow Control and 3.7 1 2

recirculation flow control valves.

204000 RWCU 0 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 RBM 0 Knowledge of Nuclear Boiler Instrumentation design feature(s) 1 and or interlock(s) which provide for overpressure protection 56 216000 Nuclear Boiler Inst. 3 3.4 1 for various low pressure systems.

219000 RHR/LPCI: Torus/Pool Cooling Mode 0 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 Knowledge of the physical connections and/or cause-effect 1 relationships between Fuel Pool Cooling/Cleanup and storage 57 233000 Fuel Pool Cooling/Cleanup 5 2.9 1 pools.

234000 Fuel Handling Equipment 0 0 Knowledge of the effect that a loss or malfunction of the Main 58 239001 Main and Reheat Steam 1 and Reheat System will have on turbine generator. 3.2 1 0 Ability to monitor automatic operations of MSIV Leakage 59 239003 MSIV Leakage Control 2 Control including main steamline pressure. 3.1 1 Knowledge of the effect that a loss or malfunction of the 0

60 241000 Reactor/Turbine Pressure Regulator 8 Reactor/Turbine Pressure Regulator will have on control 3.7 1 valves.

Knowledge of Main Turbine Generator Auxiliaries design 0 feature(s) and or interlock(s) which provide for Generator 61 245000 Main Turbine Gen. / Aux. 6 2.7 1 Protection.

0 Knowledge of the electrical power supplies to system pumps.

62 256000 Reactor Condensate 1 2.7 1 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 0 Knowledge of the effect that a loss or malfunction of AC 63 286000 Fire Protection 1 electrical distribution will have on Fire Protection. 3.1 1 288000 Plant Ventilation 0 Knowledge of the effect that a loss or malfunction of the 0

64 290001 Secondary CTMT 1 Secondary Containment will have on offsite radioactive release 4 1 rates.

290003 Control Room HVAC 0 0 Knowledge of the operational implications of heat transfer 65 290002 Reactor Vessel Internals 6 mechanism as it applies to Reactor Vessel Internals. 2.8 1 K/A Category Totals: 2 1 3 2 1 1 0 0 1 1 0 Group Point Total: 12 ES-401, Page 22 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:River Bend Station Date of Exam:12/3/2010 RO SRO-Only Category K/A # Topic Q# IR # IR #

66 2.1. 01 Knowledge of conduct of operations requirements. 3.8 1 Ability to locate control room switches, controls, and indications, and to determine that 67 2.1. 31 they correctly reflect the desired plant lineup. 4.6 1

1. 2.1.

Conduct of 2.1.

Operations 2.1.

2.1.

Subtotal 2 0 Knowledge of less than or equal to one hour Technical Specification action statements for 68 2.2. 39 systems. 3.9 1 69 2.2. 40 Ability to apply Technical Specifications for a system. 3.4 1

2. 2.2.

Equipment 2.2.

Control 2.2.

2.2.

Subtotal 2 0 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 70 2.3. 05 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 Knowledge of radiological safety procedures pertaining to licensed operator duties, such 71 2.3. 13 as response to radiation monitor alarms, containment entry requirements, fuel handling 3.4 1 responsibilities, access to locked high-radiation areas, aligning filters, etc.

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 72

3. 2.3. 14 or emergency conditions or activities. 3.4 1 Radiation 2.3.

Control 2.3.

2.3.

Subtotal 3 0 73 2.4. 01 Knowledge of EOP entry conditions and immediate action steps. 4.6 1 Ability to perform without reference to procedures those actions that require immediate 74 2.4. 49 operation of system components and controls. 4.6 1 Ability to verify system alarm setpoints and operate controls identified in the alarm 75 4. 2.4. 50 response manual. 4.2 1 Emergency Procedures 2.4.

/ Plan 2.4.

2.4.

Subtotal 3 0 Tier 3 Point Total 10 0 ES-401, Page 27 of 34

NRC RO ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 295005 AA1.06 Importance rating for this KA is <2.5 and there is no site-specific priority associated with this KA. Re-selected 295005 AA1.05 1/1 600000 AA1.07 Importance rating for this KA is <2.5 and there is no site-specific priority associated with this KA. Re-selected 600000 AA1.05 2/1 223002 A3.04 Importance rating for this KA is <2.5 and there is no site-specific priority associated with this KA. Re-selected 223002 A3.01 2/1 300000 K6.11 Importance rating for this KA is <2.5 and there is no site-specific priority associated with this KA. Re-selected 300000 K6.13 2/2 239003 A3.05 Importance rating for this KA is <2.5 and there is no site-specific priority associated with this KA. Re-selected 239003 A3.02 1/1 295023 AA2.05 Inability to write a discriminatory RO level question for this KA.

Re-selected 295023 AA2.02 1/2 295002 G.2.2.36 There is no associated limiting condition for operation for this abnormal event. Re-selected 295002 G.2.1.32.

2/1 261000 G.2.4.50 Inability to write a discriminatory RO level question for this KA.

Re-selected 261000 G.2.2.22.

Rev 0

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