ML090700422

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GG-2009-03-Final Outlines
ML090700422
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/11/2009
From: Ryan Lantz
Operations Branch IV
To: Douet J
Entergy Operations
References
50-416/09-301
Download: ML090700422 (26)
v • d • e


Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: Grand Gulf Date of Exam: March 9, 2009 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 3 3 3 4 3 4
1. 1 20 3 4 7 Emergency &

Abnormal Plant 2 1 1 1 N/A 1 2 N/A 1 7 2 1 3 Evolutions Tier Totals 4 4 4 5 5 5 27 5 5 10 1 3 2 2 3 2 3 2 2 2 2 3 26 2 3 5 2.

Plant 2 1 1 1 2 1 1 1 1 1 1 1 12 2 1 3 Systems Tier Totals 4 3 3 5 3 4 3 3 3 3 4 38 4 4 8

3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 3 3 2 2 3 2 1 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 ATier 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 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.

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. 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.

ES-401 2 Form ES-401-1 ES-401 BWR Examination OutlineForm 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 Ability to operate and/or monitor the Neutron 295001 Partial or Complete Loss of Forced R monitoring system as they apply to PARTIAL OR 3. 1R Core Flow Circulation / 1 & 4 3 COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.7 / 45.6) (AA1.06 - RO)

S Ability to determine and/or interpret the jet pump 1S operability as it applies to PARTIAL OR 3.

COMPLETE LOSS OF FORCED CORE FLOW 4 CIRCULATION (CFR: 41.10 / 43.5 / 45.13)

(AA2.05 - SRO)

Knowledge of the operational implications of Load 295003 Partial or Complete Loss of AC / 6 R shedding as it applies to PARTIAL OR 3. 2R 1

COMPLETE LOSS OF A.C. POWER (CFR: 41.8 to 41.10) (AK1.02)

Ability to determine and/or interpret the extent of 295004 Partial or Total Loss of DC Pwr / 6 R partial or complete loss of D.C. power as it applies 3. 3R 5

to PARTIAL OR COMPLETE LOSS OF D.C.

POWER (CFR: 41.10 / 43.5 / 45.13) (AA2.02)

Knowledge of the operational implications of 295005 Main Turbine Generator Trip / 3 R Pressure effects on reactor level as it applies to 3. 4R 5

MAIN TURBINE GENERATOR TRIP (CFR:

41.8 to 41.10) (AK1.03)

Ability to evaluate plant performance and make 295006 SCRAM / 1 R operational judgments based on operating 4. 5R 4

characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13)

(2.1.7)

R Knowledge of limiting conditions for operations 295016 Control Room Abandonment / 7 and safety limits. (CFR: 41.5 / 43.2 / 45.2) (2.2.22 4. 6R 0

- RO)

Knowledge of abnormal condition procedures.

S 2S (CFR: 41.10 / 43.5 / 45.13) (2.4.11 - SRO) 4.

2 295018 Partial or Total Loss of CCW / 8 R Knowledge of the interrelations between 3. 7R PARTIAL OR COMPLETE LOSS OF 3 COMPONENT COOLING WATER and system loads (CFR: 41.7 / 45.8) (AK2.01)

R Ability to manage the control room crew during 295019 Partial or Total Loss of Inst. Air / 8 plant transients. (CFR: 41.10 / 43.5 / 45.12 / 45.13) 3. 8R 8

(2.1.6) 295021 Loss of Shutdown Cooling / 4 R Ability to operate and/or monitor Alternate heat 3. 9R removal methods as 7 they apply to LOSS OF SHUTDOWN COOLING (CFR: 41.7 / 45.6) (AA1.04) 295023 Refueling Acc / 8 R Knowledge of the reasons for responses of 3. 10R interlocks associated with fuel handling equipment 4 as they apply to REFUELING ACCIDENTS (CFR:

41.5 / 45.6) (AK3.02) (RO)

295024 High Drywell Pressure / 5 R Ability to operate and/or monitor the emergency 3. 11R generators as they apply to HIGH DRYWELL 7 PRESSURE (CFR: 41.7 / 45.6) (EA1.06) 295025 High Reactor Pressure / 3 R Knowledge of the interrelations between HIGH 3. 12R REACTOR PRESSURE and the reactor/turbine 7 pressure regulating system (Plant Specific) (CFR: (R O) 41.7 / 45.8) (EK2.08 - RO)

Ability to interpret and execute procedure steps. 4. 3S S

(CFR: 41.10 / 43.5 / 45.12) (2.1.20 - SRO) 6 (S

R O) 295026 Suppression Pool High Water Temp. S Ability to determine and/or interpret reactor 4. 4S

/5 pressure as it applies to SUPPRESSION POOL 0 (S

HIGH WATER TEMPERATURE: R (CFR: 41.10 / 43.5 / 45.13) (EA2.03 - SRO) O)

R Knowledge of conservative decision making 3. 13R practices. (CFR: 41.10 / 43.5 / 45.12) (2.1.39 - 6 RO) (R O) 295027 High Containment Temperature / 5 R Knowledge of the interrelations between HIGH 3. 14R CONTAINMENT TEMPERATURE (MARK III 2 CONTAINMENT ONLY) and the containment spray (plant-specific): (CFR: 41.7 / 45.8) (EK2.01)

Ability to determine and/or interpret the Drywell 295028 High Drywell Temperature / 5 R pressure as it applies to HIGH DRYWELL 4. 15R 1

TEMPERATURE :

(CFR: 41.10 / 43.5 / 45.13) (EA2.04 - RO) (R O)

Knowledge of EOP mitigation strategies. (CFR:

S 41.10 / 43.5 / 45.13) (2.4.6 - SRO) 4. 5S 7

(S R

O)

Ability to determine and/or interpret the 295030 Low Suppression Pool Wtr Lvl / 5 R Suppression pool temperature as it applies to LOW 3. 16R 9

SUPPRESSION POOL WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13) (EA2.02) 295031 Reactor Low Water Level / 2 R Ability to operate and/or monitor low pressure 4. 17R core spray as it applies to REACTOR LOW 4 WATER LEVEL : (CFR: 41.7 / 45.6) (EA1.03 -

RO)

S Ability to determine and/or interpret adequate core 4. 6S cooling as it applies to REACTOR LOW WATER 8 LEVEL : (CFR: 41.10 / 43.5 / 45.13) (EA2.04 - (S SRO) R O) 295037 SCRAM Condition Present R Knowledge of the operational implications of the 4. 18R and Power Above APRM Downscale reactor pressure effects on reactor power as it 1

or Unknown / 1 applies to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.8 to 41.10) (EK1.01) 295038 High Off-site Release Rate / 9 R Knowledge of the reasons for emergency 3. 19R depressurization as it applies to HIGH OFF-SITE 6 RELEASE RATE: (CFR: 41.5 / 45.6) (EK3.04) 600000 Plant Fire On Site / 8 R Knowledge of the reasons for actions contained in 2. 20R the abnormal procedure for plant 8 fire on site as it applies to PLANT FIRE ON SITE: (R O)

(AK3.04 - RO)

S Ability to identify post-accident instrumentation. 4. 7S (CFR: 41.6 / 45.4) (2.4.3 - SRO) (REJECTED) 4 (S

Knowledge of the emergency plan. (CFR: 43.5) R (2.4.29 - SRO) O) 3 4 K/A Category Totals: 3 3 3 4 R R Group Point Total: 20/7 3 4 S S

ES-401 3 Form ES-401-1 ES-401 BWR Examination OutlineForm 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 R Ability to identify and interpret diverse indications to 4. 21R validate the response of another indication. 3 (CFR: 41.7 / 43.5 / 45.4) (2.1.45) 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 R Ability to determine and/or interpret Reactor water 4. 22R level as it applies to LOW REACTOR WATER 2 LEVEL :(CFR: 41.10 / 43.5 / 45.13) (AA2.01) 295010 High Drywell Pressure / 5 R Knowledge of the operational implications of 3. 23R temperature increases as it applies to HIGH 2 DRYWELL PRESSURE : (CFR: 41.8 to 41.10)

(AK1.03) 295011 High Containment Temp / 5 R Knowledge of the reasons for the increased 3. 24R containment cooling (Mark-III) response as it applies 6 to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): (CFR: 41.5 /

45.6) (AK3.01) 295012 High Drywell Temperature / 5 S Ability to determine and/or interpret the drywell 3. 8S temperature as it applies to HIGH DRYWELL 9 TEMPERATURE : (CFR: 41.10 / 43.5 / 45.13)

(AA2.01) 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 R Knowledge of the interrelations between HIGH OFF- 3. 25R SITE RELEASE RATE and the standby gas 4 treatment/FRVS: (CFR: 41.7 / 45.8) (AK2.12) 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 R Knowledge of the operational implications of the 3. 26R Reactivity control concepts as they apply to LOSS OF 6 CRD PUMPS: (CFR: 41.8 to 41.10) (AK1.02) 295029 High Suppression Pool Wtr Lvl / 5 S Ability to determine and/or interpret reactor pressure 3. 9S as it applies to HIGH SUPPRESSION POOL 6 WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13)

(EA2.02) 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area S Knowledge of radiation monitoring systems, such as 3. 10S Radiation Levels / 9 fixed radiation monitors and alarms, portable survey 1 instruments, personnel monitoring equipment, etc.

(CFR: 41.12 / 43.4 / 45.9) (2.3.15) 295034 Secondary Containment Ventilation

High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 R Ability to determine and / or interpret the Hydrogen 3. 27R monitoring system availability as it applies to HIGH 1 PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: (CFR: 41.10 / 43.5 / 45.13)

(EA2.01)

K/A Category Point Totals: 1 1 1 1 2 1 Group Point Total: 7/3 R R 2 1 S S

ES-401 4 Form ES-401-1 ES-401BWR 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 203000 RHR/LPCI: Injection R Knowledge of how to conduct system 4.1 28R Mode lineups, such as valves, breakers, switches, etc. (CFR: 41.10 / 45.1 / 45.12) (2.1.29) 205000 Shutdown Cooling R Knowledge of the effect that a loss or 3.2( 29R malfunction of the SHUTDOWN COOLING RO)

SYSTEM (RHR SHUTDOWN COOLING MODE) will have on reactor water level (plant-specific): (CFR: 41.7 / 45.4) (K3.02 -

RO) 4.1(

SR S Knowledge of procedures and limitations O) 11S involved in core alterations. (CFR: 41.10 /

43.6 / 45.7) (2.1.36 - SRO) 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS R Knowledge of the process for conducting 2.9 30R special or infrequent tests. (CFR: 41.10 /

43.3 / 45.13) (2.2.7) 209002 HPCS R Knowledge of the effect that a loss or 2.5 31R malfunction of the Suppression pool suction strainer (BWR-5,6) will have on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS): (CFR: 41.7 / 45.7) (K6.04) 211000 SLC R Knowledge of the effect that a loss or 3.0 32R malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on the core spray line break detection system (plant-specific): (CFR: 41.7 / 45.4) (K3.02) 212000 RPS R Knowledge of electrical power supplies to 3.2 33R the RPS motor-generator sets:

(CFR: 41.7) (K2.01) 215003 IRM R Knowledge of INTERMEDIATE RANGE 3.7 34R MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the rod withdrawal blocks:

(CFR: 41.7) (K4.01) 215004 Source Range Monitor R Knowledge of the effect that a loss or 3.2( 35R malfunction of the RPS will have on the RO)

SOURCE RANGE MONITOR (SRH)

SYSTEM : (CFR: 41.7 / 45.7) (K6.01 - RO)

Ability to verify system alarm setpoints and 4.0 operate controls identified in the alarm (SR S response manual. (CFR: 41.10 / 43.5 / 45.3) O) 12S (2.4.50 - SRO) This KA was rejected Ability to diagnose and recognize trends in a timely manner utilizing the appropriate control room reference material. (CFR: 41.10

/ 43.5 / 45.12). (G-2.4.47) 215005 APRM / LPRM R Knowledge of the operational implications of 2.5 36R Assignment of LPRM's to specific APRM channels as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

(CFR: 41.5 / 45.3) (K5.06) 217000 RCIC R Knowledge of electrical power supplies to 2.6 37R the gland seal compressor (vacuum pump):

(CFR: 41.7) (K2.04) 3.5 R Knowledge of the effect that a loss or 38R malfunction of the condensate storage and transfer system will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): (CFR: 41.7 / 45.7) (K6.04) 218000 ADS R Knowledge of the physical connections 3.7 39R and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the nuclear boiler instrument system:

(CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.03) 3.4 R Ability to (a) predict the impacts of the Loss 40R of A.C. or D.C. power to ADS valves on the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6) (A2.05) 223002 PCIS/Nuclear Steam R Ability to predict and/or monitor changes in 3.7( 41R Supply Shutoff parameters associated with operating the RO)

PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including valve closures: (CFR: 41.5 / 45.5) (A1.02 - RO) 4.5(

SR S Knowledge of less than or equal to one hour O) 13S Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2 / 45.13)

(2.2.39 - SRO) 239002 SRVs R Ability to (a) predict the impacts of the 4.1 42R following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

ADS Actuation (CFR: 41.5 / 45.6) (A2.04)

259002 Reactor Water Level R Ability to monitor automatic operations of 3.0 43R Control the REACTOR WATER LEVEL CONTROL SYSTEM including runout flow control (plant-specific): (CFR: 41.7 / 45.7)

(A3.01) 261000 SGTS R Ability to predict and/or monitor changes in 2.9 44R parameters associated with operating the (RO STANDBY GAS TREATMENT SYSTEM )

controls including system flow:

(CFR: 41.5 / 45.5) (A1.01 - RO)

Ability to (a) predict the impacts of the 3.2(

S following on the STANDBY GAS SR 14S TREATMENT SYSTEM; and (b) based on O) those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

High system pressure (plant-specific)

(CFR: 41.5 / 45.6) (A2.14 - SRO) 262001 AC Electrical R Knowledge of the operational implications of 3.1 45R Distribution the following concepts as they apply to A.C.

ELECTRICAL DISTRIBUTION: principle involved with paralleling two A.C. sources (CFR: 41.5 / 45.3) (K5.01) 3.3 R Ability to manually operate and/or monitor 46R in the control room: voltage, current, power, and frequency on A.C. buses (CFR: 41.7 / 45.5 to 45.8) (A4.05) 262002 UPS (AC/DC) R Knowledge of UNINTERRUPTABLE 3.1 47R POWER SUPPLY (A.C./D.C.)

design feature(s) and/or interlocks which provide for the following: transfer from preferred power to alternate power supplies (CFR: 41.7) (K4.01) 2.8 R Ability to manually operate and/or monitor 48R in the control room: transfer from alternative source to preferred source (CFR: 41.7 / 45.5 to 45.8) (A4.01) 263000 DC Electrical R Knowledge of the physical connections 3.2( 49R Distribution and/or cause-effect relationships between RO)

D.C. ELECTRICAL DISTRIBUTION and Battery charger and battery: (CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.02 - RO)

S Ability to (a) predict the impacts of Grounds 3.2(

on the D.C. ELECTRICAL SR 15S O)

DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6) (A2.01 - SRO)

264000 EDGs R Knowledge of EMERGENCY 2.5 50R GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for speed droop control:

(CFR: 41.7) (K4.03) 300000 Instrument Air R Knowledge of the connections and / or 2.8 51R cause- effect relationships between INSTRUMENT AIR SYSTEM and the cooling water to compressor:

(CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.04 -

RO) 2.9 R Ability to monitor automatic operations of 52R the INSTRUMENT AIR SYSTEM including air temperature: (CFR: 41.7 / 45.7) (A3.02 -

RO) 400000 Component Cooling R Knowledge of tagging and clearance 4.1 53R Water procedures. (CFR: 41.10 / 45.13) (2.2.13) 2 3 K/A Category Point Totals: 3 2 2 3 2 3 2 R 2 2 R Group Point Total: 26/

5 2 3 S S

ES-401 5 Form ES-401-1 ES-401BWR Examination OutlineForm 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 201001 CRD Hydraulic R Ability to manually operate and/or 2.8 54R monitor the SDV isolation valve test switch in the control room:

CFR: 41.7 / 45.5 to 45.8) (A4.06) 201002 RMCS 201003 Control Rod and Drive R Knowledge of the physical connections 3.2 55R Mechanism and/or cause-effect relationships between CONTROL ROD AND DRIVE MECHANISM and the control rod drive hydraulic system:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

(K1.01) 201004 RSCS 201005 RCIS R Ability to interpret control room 4.2 56R indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12) (2.2.44) 201006 RWM 202001 Recirculation R Knowledge of the effect that a loss or 2.7 57R malfunction of the Control rod drive system (plant-specific) will have on the RECIRCULATION SYSTEM :

(CFR: 41.7 / 45.7) (K6.05) 202002 Recirculation Flow Control S 16S Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Recirculation pump speed mismatch between loops. (CFR 41.5 / 45.6)

(A2.04) 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe S 215002 RBM 216000 Nuclear Boiler Inst. R Ability to predict and/or monitor 3.4 58R changes in parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION controls including recorders and meters:

(CFR: 41.5 / 45.5) (A1.01)

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux. S Ability to (a) predict the impacts of the 3.1 17S Compressor trips (loss of air) (plant-specific) on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) (A2.08) 226001 RHR/LPCI: CTMT Spray Mode R Knowledge of RHR/LPCI: 2.5 59R CONTAINMENT SPRAY SYSTEM MODE design feature(s) and/or interlocks which provide for pump minimum flow protection: (CFR: 41.7)

(K4.05) 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup S Knowledge of new and spent fuel 3.4 18S movement procedures. (CFR: 41.10 /

43.7 / 45.13) (2.1.42) 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure R Knowledge of the operational 3.3 60R Regulator Implications of turbine inlet pressure vs.

reactor pressure as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM:

(CFR: 41.5 / 45.3) (K5.04) 245000 Main Turbine Gen. / Aux. R Knowledge of the physical connections 2.7 61R and/or cause-effect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the D. C . electrical distribution: (CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.09) 256000 Reactor Condensate R Ability to monitor automatic operations 3.0 62R of the REACTOR CONDENSATE SYSTEM including pump starts: (CFR: 41.7 / 45.7) (A3.02) 259001 Reactor Feedwater R Ability to (a) predict the impacts of 3.3 63R following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of Extraction Steam (CFR: 41.5 / 45.6) (A2.04) 268000 Radwaste 271000 Offgas

272000 Radiation Monitoring R Knowledge of RADIATION 2.7 64R MONITORING System design feature(s) and/or interlocks which provide for redundancy: (CFR: 41.7)

(K4.01) 286000 Fire Protection R Knowledge of the effect that a loss or 3.2 65R malfunction of the FIRE PROTECTION SYSTEM will have on personnel protection: (CFR: 41.7 / 45.4)

(K3.02) 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals: 1 1 1 2 1 1 1 1 1 1 1 Group Point Total: 12/3 R R 2

S 1 S

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Grand Gulf Date of Exam: 2009 Category K/A # Topic RO SRO-Only IR # IR #

2.1.13 Knowledge of facility requirements for controlling 2.5 66R vital/controlled access. (CFR: 41.10 / 43.5 / 45.9 / 45.10) 1.

Conduct 2.1.17 Ability to make accurate, clear, and concise verbal reports. 3.9 67R of Operations (CFR: 41.10 / 45.12 / 45.13) 2.1.39 Knowledge of conservative decision making practices. 3.6 68R (CFR: 41.10 / 43.5 / 45.12) 2.1.5 Ability to use procedures related to shift staffing, such as 3.9 19S (S) minimum crew complement, overtime limitations, etc.

(CFR: 41.10 / 43.5 / 45.12) 2.1.23 Ability to perform specific system and integrated plant 4.4 20S (S) procedures during all modes of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 2.1.30 Ability to locate and operate components, including local 4.0 21S (S) controls. (CFR: 41.7 / 45.7)

Subtotal 3 3 2.2.18 Knowledge of the process for managing maintenance 2.6 69R activities during shutdown operations, such as risk assessments, work prioritization, etc. (CFR: 41.10 / 43.5 /

2. 45.13)

Equipment Control 2.2.37 Ability to determine operability and/or availability of safety 3.6 70R related equipment. (CFR: 41.7 / 43.5 / 45.12) 2.2.44 Ability to interpret control room indications to verify the 4.2 71R status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12) 2.2.25 Knowledge of the bases in Technical Specifications for 4.2 22S (S) limiting conditions for operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2) 2.2.42 Ability to recognize system parameters that are entry-level 4.6 23S (S) conditions for Technical Specifications. (CFR: 41.7 / 41.10 /

43.2 / 43.3 / 45.3)

Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 72R emergency conditions. (CFR: 41.12 / 43.4 / 45.10)

3. 2.3.14 Knowledge of radiation or contamination hazards that may 3.4 73R Radiation arise during normal, abnormal, or emergency conditions or Control activities. (CFR: 41.12 / 43.4 / 45.10) 2.3.11 Ability to control radiation releases. (CFR: 41.11 / 43.4 / 4.3 24S (S) 45.10)

Subtotal 2 1 2.4.13 Knowledge of crew roles and responsibilities during EOP 4.0 74R usage. (CFR: 41.10 / 45.12)

4.

2.4.21 Knowledge of the parameters and logic used to assess the 4.0 75R Emergency status of safety functions, such as reactivity control, core Procedures /

cooling and heat removal, reactor coolant system integrity, Plan containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5 / 45.12) 2.4.37 Knowledge of the lines of authority during implementation 4.1 25S (S) of the emergency plan.

(CFR: 41.10 / 45.13)

Subtotal 2 1 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/1 206000 HPCI This exam is being written for the BWR-6 design. This question is only applicable to the BWR-2, -3, and -4 designs.

2/1 207000 Isolation This exam is being written for the BWR-6 design. This (Emergency) question is only applicable to the BWR-2 and -3 designs.

Condenser 2/1 261000 SGTS This exam is being written for a BWR-6 design, which includes Mark-III containment. The line item selected (A1.06) is specific for Mark-I containment.

1/1 295024 High The original random selection of EA1.16 involves Drywell Pressure containment/drywell vacuum breakers, and this plant does not include these. Drywell vacuum relief is provided for in the CGCS, but physical passive vacuum breakers are not included.

1/1 295028 High This exam is being written for a BWR-6 design, which Drywell includes Mark-III containment. The line item selected Temperature (EA2.06) is specific for Mark-I containment.

2/2 230000 This exam is being written for a BWR-6 design, which RHR/LPCI: includes Mark-III containment. The system selected is Torus/Pool Spray specific for Mark-I containment.

Mode 2/1 263000 DC For the selected item for an RO question (K1.03), it will be Electrical difficult to develop valid discriminatory answers.

Distribution 3 G 2.1.30 A valid SRO question could not be developed for this KA.

(Ability to locate and operate components, including local controls.) Another KA was randomly selected.

2/2 215001 A2.01 This KA was rejected due to it not being applicable to a Mark III containment. Another KA was randomly selected.

1/1 295028 G-2.4.18 This KA was rejected due to the fact that this was selected for a SRO question, and EOP bases knowledge is applicable to RO questions. Another generic Emergency Procedures/Plan KA was selected for the Safety Function.

1/1 295023 AA2.03 A valid SRO question could not be developed for this KA.

Another safety function was selected, and a KA was randomly selected.

2/1 215004 G-2.4.50 This KA was rejected due to it being focused on actions found in the alarm cards making it an RO question. Another

KA was randomly selected.

2/2 268000 A2.01 This KA was rejected due to not being able to write a valid RO question. Another KA was randomly selected.

1/1 600000 G2.4.3 This KA was rejected due to not being able to write a valid SRO question and another KA was selected.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 2 March 2009 Examination Level (circle one) RO / SRO Operating Test Number:

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

Perform Daily Operations Log Surveillance for N SLC Operability.

Conduct of Operations GJPM-OPS-ADM04 K/A 2.1.25: 2.8 N/A Conduct of Operations Prepare a Tagout Tags Sheet for a Protective Tag N out Clearance.

Equipment Control GJPM-OPS-ADM01 K/A 2.2.13: 3.6 Identify Entry/Exit Requirements for accessing a M High Radiation Area / Contamination Area.

Radiation Control GJPM-OPS-RP01 K/A 2.3.1: 2.6; 2.3.4: 2.5 Loss of Shutdown Cooling - Determine time to N 200°F Emergency Procedures/Plan GJPM-OPS-ADM03 K/A 2.4.11 3.4 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 (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)

(S) imulator Revision 0 11/13/2006

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 2 March 2009 Examination Level (circle one) RO / SRO Operating Test Number:

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

Perform SRO review of the Daily Jet Pump N Surveillance.

Conduct of Operations GJPM-SRO-ADM01 K/A 2.1.33: 4.0 Review the Plant Chemistry Report and determine M any required actions Conduct of Operations GJPM-SRO-ADM03 K/A 2.1.25: 3.1; 2.1.34: 2.9 Perform Tag Reviewer review of Protective Tag N out Clearance.

Equipment Control GJPM-OPS-ADM02 K/A 2.2.13: 3.8 Review Liquid Radwaste Discharge Permit.

M Radiation Control GJPM-SRO-ADM02 K/A 2.3.6: 3.1 Given plant conditions, determine entry into the M Site Emergency Plan and complete the initial Emergency notification form. ATWS Procedures/Plan GJPM-OPS-EAL25 K/A 2.4.41: 4.1; 2.4.38: 4.0; 2.4.40: 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 all 5 are required.

  • Type Codes & Criteria: (C) ontrol Room (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)

(S) imulator Revision 0 11/13/2006

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination: 2 March 2009 Exam Level (circle one) RO / SRO-I / SRO-U Operating Test Number:

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Safety Code* Function

a. 202001 Recirculation System - Startup idle Recirculation Pump w/ S; N; A; 1 High Vibration requiring manual pump trip. L
b. 209002 High Pressure Core Spray System - Operate HPCS in CST- S; D; A 2 to-CST mode w/failure of HPCS minimum flow valve ESF
c. 264000 Emergency Generators - Parallel of Emergency Generator S; N 6 (with load) to the grid ESF
d. 400000 Component Cooling Water System - Rotate CCW pumps S; B; A 8 w/CCW pump trip
e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for S; N; A 3 RPV pressure control w/failure of RCIC turbine speed controller
f. 219000 RHR/LPCI: Suppression Pool Cooling Mode - Secure RHR S; N; A 5 from Containment Spray mode to Suppression Pool Cooling mode ESF w/trip of ECCS pump requiring manual RHR alignment to LPCI mode
g. 201005 Rod Control and Information System - Bypass a Control Rod C; D 7 in the RACS
h. 239003 Main Steam Isolation Valve Leakage Control System - Start C; N; A 9 the Outboard MSIV LCS w/ blower failure requiring start of the ESF Inboard MSIV LCS In-Plant Systems@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)
i. 211000 Standby Liquid Control System - Perform SLC Pump A R; N 1 Monthly Surveillance
j. 262002 Uninterruptible Power Supply (A.C./D.C.) - Start up Static D 6 Inverter 1Y81
k. 286000 Fire Protection System - Align Fire Water for injection to the R; E; L; 8 reactor via LPCS and RHR C per EP Attachment 26 D

@ 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 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 Revision 2 2/22/2007

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination: 2 March 2009 Exam Level (circle one) RO / SRO-I / SRO-U Operating Test Number:

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Safety Code* Function

a. 202001 Recirculation System - Startup idle Recirculation Pump w/ S; N; A; 1 High Vibration requiring manual pump trip. L
b. 209002 High Pressure Core Spray System - Operate HPCS in CST- S; D; A 2 to-CST mode w/failure of HPCS minimum flow valve ESF
c. 264000 Emergency Generators - Parallel of Emergency Generator S; N 6 (with load) to the grid ESF
d. 400000 Component Cooling Water System - Rotate CCW pumps S; B; A 8 w/CCW pump trip
e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for S; N; A 3 RPV pressure control w/failure of RCIC turbine speed controller
f. 219000 RHR/LPCI: Suppression Pool Cooling Mode - Secure RHR S; N; A 5 from Containment Spray mode to Suppression Pool Cooling mode ESF w/trip of ECCS pump requiring manual RHR alignment to LPCI mode
g. 201005 Rod Control and Information System - Bypass a Control Rod C; D 7 in the RACS
h. N/A In-Plant Systems@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)
i. 211000 Standby Liquid Control System - Perform SLC Pump A R; N 1 Monthly Surveillance
j. 262002 Uninterruptible Power Supply (A.C./D.C.) - Start up Static D 6 Inverter 1Y81
k. 286000 Fire Protection System - Align Fire Water for injection to the R; E; L; 8 reactor via LPCS and RHR C per EP Attachment 26 D

@ 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 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 Revision 2 2/22/2007

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination: 2 March 2009 Exam Level (circle one) RO / SRO-I / SRO-U Operating Test Number:

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Safety Code* Function

a. N/A
b. N/A
c. N/A
d. N/A
e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for S; N; A 3 RPV pressure control w/failure of RCIC turbine speed controller
f. 219000 RHR/LPCI: Suppression Pool Cooling Mode - Secure RHR S; N; A 5 from Containment Spray mode to Suppression Pool Cooling mode ESF w/trip of ECCS pump requiring manual RHR alignment to LPCI mode
g. N/A
h. N/A In-Plant Systems@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)
i. 211000 Standby Liquid Control System - Perform SLC Pump A R; N 1 Monthly Surveillance
j. 262002 Uninterruptible Power Supply (A.C./D.C.) - Start up Static D 6 Inverter 1Y81
k. 286000 Fire Protection System - Align Fire Water for injection to the R; E; L; 8 reactor via LPCS and RHR C per EP Attachment 26 D

@ 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 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 Revision 2 2/22/2007

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 1 Op-Test No.: 030209 Examiners: _________________________ Operators:__________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Rotate EHC pumps.
2. Recognize and respond to indications of a Seal Steam Pressure Controller failure.
3. Respond to RPS MG Set B trip.
4. Recognize and respond to Reactor Recirc Flow Control Valve A failing open.
5. Respond to bus 16AB lockout.
6. Respond to an ATWS.
7. Respond to a SSW C Pump trip.

Initial Conditions: Reactor Power is at 73 %.

INOPERABLE Equipment None Turnover:

The plant is at 73% power during startup. Power ascension is temporarily suspended to place EHC pump C in service and remove EHC pump A from operation in accordance with SOI 04-1-01-N32-1. No out of service equipment and EOOS is green. Division 1 work week is in effect.

REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 1 of 20

Appendix D Scenario Outline Form ES-D-1 Scenario 1 Event Malf. No. Event Event No. Type* Description 1 N(BOP)

Rotate EHC pumps - start C and secure A (SOI 04-1 N32-1 section 5.1) 2 ms255 C(ACRO)

Recognize and respond to indications of a Seal Steam Pressure Controller failure. (ARI 1H13-P680-10A-E7) 3 c71077b C(ACRO)

Respond to RPS MG Set B trip (05-1-02-III-2) 4 di_1b33k603ac C(ACRO)

Recognize and respond to Recirc FCV A Controller Failure (FCV Opens) 5 r21139f C(BOP)

Respond to ESF bus 16AB lockout (ONEP 05-1-02-I-4) 6 c11164 @ 10 M (ALL)

Respond to an ATWS (EP-2A) 7 p41149 C(BOP)

Respond to SSW C Pump trip

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks

- Upon recognition of ATWS conditions, perform actions to insert control rods by scramming and/or driving.

- When conditions are met in EP-2A, terminate and prevent injection to exercise power/level control, and re-establish injection to control RPV level in accordance with EP-2A.

REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 2 of 20

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Facility: GRAND GULF NUCLEAR STATION Scenario No.: 2 Op-Test No.: 030209 Examiners: ________________________ Operators:__________________________

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

1. Raise reactor power from 81% to 88% using Recirc FCVs.
2. Recognize and respond to a low failure of APRM B Flow Reference Signal resulting in an APRM B Upscale.
3. Recognize and respond to Reactor Feed Pump B Controller failure -

increasing speed.

4. Respond to an SRV failing open.
5. Recognize and respond to failure of HPCS suction to automatically align to Suppression Pool on high Suppression Pool level.
6. Respond to bus 12HE lockout.
7. Respond to trip of Service Transformer 11.
8. Respond to a RCIC steam line break in the RCIC room with failure/inability to isolate.

Initial Conditions: Reactor Power is at 81 %.

INOPERABLE Equipment None Turnover:

The plant is at 81% power following a temporary downpower for a control rod pattern adjustment. Power ascension is to continue to 88% where it will be held due to fuel preconditioning limitations. The current envelope is at 90% power. There is no out of service equipment. EOOS is green. A Division 1 work week is in effect.

REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 1 of 23

Appendix D Scenario Outline Form ES-D-1 Scenario 2 Event Malf. No. Event Event No. Type* Description 1 R(ACRO)

Raise reactor power from 81% to 88% using Recirc FCVs (03-1-01-2) 2 aprmbus C(ACRO)

APRM B Flow Reference Signal Failure Low - APRM Upscale (ARI 04-1-021H13-P680-5A-B10) 3 fw121b C(ACRO)

Reactor Feed Pump B Controller failure - increasing speed (05-1-02-V-7) 4 di_1b21606d C(BOP)

Respond to an SRV B21-F041D failing open (EP-3) 5 Att 4 C(BOP)

Respond to failure of HPCS suction to automatically align to Suppression Pool on high Suppression Pool level (ARI 1H13-P601-16A-C5) 6 r21138b C(ACRO)

Respond to bus 12HE lockout (ONEP 05-1-02-I-4) 7 r21133a M (ALL)

Respond to trip of Service Transformer 11 (ONEP 05-1-02-I-4, EP-2) 8 e51050 M (ALL) e51187a Respond to a RCIC steam line break in the RCIC room e51187b with failure/inability to isolate (EP-4)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Critical Tasks

- When Maximum Safe temperature is reached in RCIC Room and auxiliary building Steam Tunnel, enters the Emergency Depressurization leg of EP-2 and opens at least 7 SRVs.

- During Emergency Depressurization, maintains reactor water level above -

192 Compensated Fuel Zone using Condensate system.

REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 2 of 23

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