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

E S-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

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total 1

3 3

3 4

3 4

20 3

4 7

2 1

1 11 1

2 1

7 2

1 3

1.

Emergency &

Abnormal Plant Evolutions Tier Totals 4

4 44 N/A 5

5 N/A 5

27 5

5 10 1

3 2

2 3

2 3

2 2

2 2

3 26 2

3 5

2 1

1 1

2 1

1 1

1 1

1 1

12 2

1 3

2.

Plant Systems Tier Totals 4

3 3

5 3

4 3

3 3

3 4

38 4

4 8

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 3

3 2

2 10 3

2 1

1 7

Note: 1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the 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.

E S-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

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 R

S Ability to operate and/or monitor the Neutron monitoring system as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.7 / 45.6) (AA1.06 - RO)

Ability to determine and/or interpret the jet pump operability as it applies to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.10 / 43.5 / 45.13)

(AA2.05 - SRO) 3.

3 3.

4 1R 1S 295003 Partial or Complete Loss of AC / 6 R

Knowledge of the operational implications of Load shedding as it applies to PARTIAL OR COMPLETE LOSS OF A.C. POWER (CFR: 41.8 to 41.10) (AK1.02) 3.

1 2R 295004 Partial or Total Loss of DC Pwr / 6 R

Ability to determine and/or interpret the extent of partial or complete loss of D.C. power as it applies to PARTIAL OR COMPLETE LOSS OF D.C.

POWER (CFR: 41.10 / 43.5 / 45.13) (AA2.02) 3.

5 3R 295005 Main Turbine Generator Trip / 3 R

Knowledge of the operational implications of Pressure effects on reactor level as it applies to MAIN TURBINE GENERATOR TRIP (CFR:

41.8 to 41.10) (AK1.03) 3.

5 4R 295006 SCRAM / 1 R

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13)

(2.1.7) 4.

4 5R 295016 Control Room Abandonment / 7 R

S Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 / 45.2) (2.2.22

- RO)

Knowledge of abnormal condition procedures.

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

0 4.

2 6R 2S 295018 Partial or Total Loss of CCW / 8 R

Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and system loads (CFR: 41.7 / 45.8) (AK2.01) 3.

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

Ability to manage the control room crew during plant transients. (CFR: 41.10 / 43.5 / 45.12 / 45.13)

(2.1.6) 3.

8 8R 295021 Loss of Shutdown Cooling / 4 R

Ability to operate and/or monitor Alternate heat removal methods as they apply to LOSS OF SHUTDOWN COOLING (CFR: 41.7 / 45.6) (AA1.04) 3.

7 9R 295023 Refueling Acc / 8 R

Knowledge of the reasons for responses of interlocks associated with fuel handling equipment as they apply to REFUELING ACCIDENTS (CFR:

41.5 / 45.6) (AK3.02) (RO) 3.

4 10R

295024 High Drywell Pressure / 5 R

Ability to operate and/or monitor the emergency generators as they apply to HIGH DRYWELL PRESSURE (CFR: 41.7 / 45.6) (EA1.06) 3.

7 11R 295025 High Reactor Pressure / 3 R

S Knowledge of the interrelations between HIGH REACTOR PRESSURE and the reactor/turbine pressure regulating system (Plant Specific) (CFR:

41.7 / 45.8) (EK2.08 - RO)

Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12) (2.1.20 - SRO) 3.

7 (R

O) 4.

6 (S

R O) 12R 3S 295026 Suppression Pool High Water Temp.

/ 5 S

R Ability to determine and/or interpret reactor pressure as it applies to SUPPRESSION POOL HIGH WATER TEMPERATURE:

(CFR: 41.10 / 43.5 / 45.13) (EA2.03 - SRO)

Knowledge of conservative decision making practices. (CFR: 41.10 / 43.5 / 45.12) (2.1.39 -

RO) 4.

0 (S

R O) 3.

6 (R

O) 4S 13R 295027 High Containment Temperature / 5 R

Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the containment spray (plant-specific): (CFR: 41.7 / 45.8) (EK2.01) 3.

2 14R 295028 High Drywell Temperature / 5 R

S Ability to determine and/or interpret the Drywell pressure as it applies to HIGH DRYWELL TEMPERATURE :

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

Knowledge of EOP mitigation strategies. (CFR:

41.10 / 43.5 / 45.13) (2.4.6 - SRO) 4.

1 (R

O) 4.

7 (S

R O) 15R 5S 295030 Low Suppression Pool Wtr Lvl / 5 R

Ability to determine and/or interpret the Suppression pool temperature as it applies to LOW SUPPRESSION POOL WATER LEVEL :

(CFR: 41.10 / 43.5 / 45.13) (EA2.02) 3.

9 16R 295031 Reactor Low Water Level / 2 R

S Ability to operate and/or monitor low pressure core spray as it applies to REACTOR LOW WATER LEVEL : (CFR: 41.7 / 45.6) (EA1.03 -

RO)

Ability to determine and/or interpret adequate core cooling as it applies to REACTOR LOW WATER LEVEL : (CFR: 41.10 / 43.5 / 45.13) (EA2.04 -

SRO) 4.

4 4.

8 (S

R O) 17R 6S 295037 SCRAM Condition Present and Power Above APRM Downscale R

Knowledge of the operational implications of the reactor pressure effects on reactor power as it 4.

1 18R

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 depressurization as it applies to HIGH OFF-SITE RELEASE RATE: (CFR: 41.5 / 45.6) (EK3.04) 3.

6 19R 600000 Plant Fire On Site / 8 R

S Knowledge of the reasons for actions contained in the abnormal procedure for plant fire on site as it applies to PLANT FIRE ON SITE:

(AK3.04 - RO)

Ability to identify post-accident instrumentation.

(CFR: 41.6 / 45.4) (2.4.3 - SRO) (REJECTED)

Knowledge of the emergency plan. (CFR: 43.5)

(2.4.29 - SRO) 2.

8 (R

O) 4.

4 (S

R O) 20R 7S K/A Category Totals:

3 3

3 4

3 R

3 S

4 R

4 S

Group Point Total:

20/7

E S-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

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295002 Loss of Main Condenser Vac / 3 R

Ability to identify and interpret diverse indications to validate the response of another indication.

(CFR: 41.7 / 43.5 / 45.4) (2.1.45) 4.

3 21R 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 level as it applies to LOW REACTOR WATER LEVEL :(CFR: 41.10 / 43.5 / 45.13) (AA2.01) 4.

2 22R 295010 High Drywell Pressure / 5 R

Knowledge of the operational implications of temperature increases as it applies to HIGH DRYWELL PRESSURE : (CFR: 41.8 to 41.10)

(AK1.03) 3.

2 23R 295011 High Containment Temp / 5 R

Knowledge of the reasons for the increased containment cooling (Mark-III) response as it applies to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): (CFR: 41.5 /

45.6) (AK3.01) 3.

6 24R 295012 High Drywell Temperature / 5 S

Ability to determine and/or interpret the drywell temperature as it applies to HIGH DRYWELL TEMPERATURE : (CFR: 41.10 / 43.5 / 45.13)

(AA2.01) 3.

9 8S 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-SITE RELEASE RATE and the standby gas treatment/FRVS: (CFR: 41.7 / 45.8) (AK2.12) 3.

4 25R 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 R

Knowledge of the operational implications of the Reactivity control concepts as they apply to LOSS OF CRD PUMPS: (CFR: 41.8 to 41.10) (AK1.02) 3.

6 26R 295029 High Suppression Pool Wtr Lvl / 5 S

Ability to determine and/or interpret reactor pressure as it applies to HIGH SUPPRESSION POOL WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13)

(EA2.02) 3.

6 9S 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 S

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.12 / 43.4 / 45.9) (2.3.15) 3.

1 10S 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 monitoring system availability as it applies to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: (CFR: 41.10 / 43.5 / 45.13)

(EA2.01) 3.

1 27R K/A Category Point Totals:

1 1

1 1

2 R

2 S

1 R

1 S

Group Point Total:

7/3

E S-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

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 203000 RHR/LPCI: Injection Mode R

Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. (CFR: 41.10 / 45.1 / 45.12) (2.1.29) 4.1 28R 205000 Shutdown Cooling R

S Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on reactor water level (plant-specific): (CFR: 41.7 / 45.4) (K3.02 -

RO)

Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10 /

43.6 / 45.7) (2.1.36 - SRO) 3.2(

RO) 4.1(

SR O) 29R 11S 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS R

Knowledge of the process for conducting special or infrequent tests. (CFR: 41.10 /

43.3 / 45.13) (2.2.7) 2.9 30R 209002 HPCS R

Knowledge of the effect that a loss or 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) 2.5 31R 211000 SLC R

Knowledge of the effect that a loss or 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) 3.0 32R 212000 RPS R

Knowledge of electrical power supplies to the RPS motor-generator sets:

(CFR: 41.7) (K2.01) 3.2 33R 215003 IRM R

Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the rod withdrawal blocks:

(CFR: 41.7) (K4.01) 3.7 34R 215004 Source Range Monitor R

Knowledge of the effect that a loss or malfunction of the RPS will have on the SOURCE RANGE MONITOR (SRH)

SYSTEM : (CFR: 41.7 / 45.7) (K6.01 - RO) 3.2(

RO) 35R

S Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 / 43.5 / 45.3)

(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) 4.0 (SR O) 12S 215005 APRM / LPRM R

Knowledge of the operational implications of 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) 2.5 36R 217000 RCIC R

R Knowledge of electrical power supplies to the gland seal compressor (vacuum pump):

(CFR: 41.7) (K2.04)

Knowledge of the effect that a loss or 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) 2.6 3.5 37R 38R 218000 ADS R

R Knowledge of the physical connections 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)

Ability to (a) predict the impacts of the Loss 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) 3.7 3.4 39R 40R 223002 PCIS/Nuclear Steam Supply Shutoff R

S Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including valve closures: (CFR: 41.5 / 45.5) (A1.02 - RO)

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

(2.2.39 - SRO) 3.7(

RO) 4.5(

SR O) 41R 13S 239002 SRVs R

Ability to (a) predict the impacts of the 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) 4.1 42R

259002 Reactor Water Level Control R

Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including runout flow control (plant-specific): (CFR: 41.7 / 45.7)

(A3.01) 3.0 43R 261000 SGTS R

S Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including system flow:

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

Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on 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) 2.9 (RO

)

3.2(

SR O) 44R 14S 262001 AC Electrical Distribution R

R Knowledge of the operational implications of 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)

Ability to manually operate and/or monitor in the control room: voltage, current, power, and frequency on A.C. buses (CFR: 41.7 / 45.5 to 45.8) (A4.05) 3.1 3.3 45R 46R 262002 UPS (AC/DC)

R R

Knowledge of UNINTERRUPTABLE 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)

Ability to manually operate and/or monitor in the control room: transfer from alternative source to preferred source (CFR: 41.7 / 45.5 to 45.8) (A4.01) 3.1 2.8 47R 48R 263000 DC Electrical Distribution R

S Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and Battery charger and battery: (CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.02 - RO)

Ability to (a) predict the impacts of Grounds on the D.C. ELECTRICAL 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) 3.2(

RO) 3.2(

SR O) 49R 15S

264000 EDGs R

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

(CFR: 41.7) (K4.03) 2.5 50R 300000 Instrument Air R

R Knowledge of the connections and / or 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)

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

RO) 2.8 2.9 51R 52R 400000 Component Cooling Water R

Knowledge of tagging and clearance procedures. (CFR: 41.10 / 45.13) (2.2.13) 4.1 53R K/A Category Point Totals:

3 2

2 3

2 3

2 2

R 2

S 2

2 3

R 3

S Group Point Total:

26/

5

E S-401 5

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 201001 CRD Hydraulic R

Ability to manually operate and/or monitor the SDV isolation valve test switch in the control room:

CFR: 41.7 / 45.5 to 45.8) (A4.06) 2.8 54R 201002 RMCS 201003 Control Rod and Drive Mechanism R

Knowledge of the physical connections 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) 3.2 55R 201004 RSCS 201005 RCIS R

Ability to interpret control room 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) 4.2 56R 201006 RWM 202001 Recirculation R

Knowledge of the effect that a loss or malfunction of the Control rod drive system (plant-specific) will have on the RECIRCULATION SYSTEM :

(CFR: 41.7 / 45.7) (K6.05) 2.7 57R 202002 Recirculation Flow Control S

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) 16S 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe S

215002 RBM 216000 Nuclear Boiler Inst.

R Ability to predict and/or monitor changes in parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION controls including recorders and meters:

(CFR: 41.5 / 45.5) (A1.01) 3.4 58R

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

S Ability to (a) predict the impacts of the 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) 3.1 17S 226001 RHR/LPCI: CTMT Spray Mode R

Knowledge of RHR/LPCI:

CONTAINMENT SPRAY SYSTEM MODE design feature(s) and/or interlocks which provide for pump minimum flow protection: (CFR: 41.7)

(K4.05) 2.5 59R 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup S

Knowledge of new and spent fuel movement procedures. (CFR: 41.10 /

43.7 / 45.13) (2.1.42) 3.4 18S 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator R

Knowledge of the operational Implications of turbine inlet pressure vs.

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

(CFR: 41.5 / 45.3) (K5.04) 3.3 60R 245000 Main Turbine Gen. / Aux.

R Knowledge of the physical connections 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) 2.7 61R 256000 Reactor Condensate R

Ability to monitor automatic operations of the REACTOR CONDENSATE SYSTEM including pump starts: (CFR: 41.7 / 45.7) (A3.02) 3.0 62R 259001 Reactor Feedwater R

Ability to (a) predict the impacts of 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) 3.3 63R 268000 Radwaste 271000 Offgas

272000 Radiation Monitoring R

Knowledge of RADIATION MONITORING System design feature(s) and/or interlocks which provide for redundancy: (CFR: 41.7)

(K4.01) 2.7 64R 286000 Fire Protection R

Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on personnel protection: (CFR: 41.7 / 45.4)

(K3.02) 3.2 65R 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

R 2

S 1

1 1

R 1

S Group Point Total:

12/3

E S-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Grand Gulf Date of Exam: 2009 RO SRO-Only Category K/A #

Topic IR IR 2.1.13 Knowledge of facility requirements for controlling vital/controlled access. (CFR: 41.10 / 43.5 / 45.9 / 45.10) 2.5 66R 2.1.17 Ability to make accurate, clear, and concise verbal reports.

(CFR: 41.10 / 45.12 / 45.13) 3.9 67R 2.1.39 Knowledge of conservative decision making practices.

(CFR: 41.10 / 43.5 / 45.12) 3.6 68R 2.1.5 (S)

Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

(CFR: 41.10 / 43.5 / 45.12) 3.9 19S 2.1.23 (S)

Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.4 20S 2.1.30 (S)

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

1.

Conduct of Operations Subtotal 3

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

45.13) 2.6 69R 2.2.37 Ability to determine operability and/or availability of safety related equipment. (CFR: 41.7 / 43.5 / 45.12) 3.6 70R 2.2.44 Ability to interpret control room 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) 4.2 71R 2.2.25 (S)

Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2) 4.2 22S 2.2.42 (S)

Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (CFR: 41.7 / 41.10 /

43.2 / 43.3 / 45.3) 4.6 23S

2.

Equipment Control Subtotal 3

2 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 3.2 72R 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10) 3.4 73R 2.3.11 (S)

Ability to control radiation releases. (CFR: 41.11 / 43.4 /

45.10) 4.3 24S

3.

Radiation Control Subtotal 2

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

2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5 / 45.12) 4.0 75R 2.4.37 (S)

Knowledge of the lines of authority during implementation of the emergency plan.

(CFR: 41.10 / 45.13) 4.1 25S

4.

Emergency Procedures /

Plan Subtotal 2

1 Tier 3 Point Total 10 7

E S-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection 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 (Emergency)

Condenser This exam is being written for the BWR-6 design. This question is only applicable to the BWR-2 and -3 designs.

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 Drywell Pressure The original random selection of EA1.16 involves 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 Drywell Temperature This exam is being written for a BWR-6 design, which includes Mark-III containment. The line item selected (EA2.06) is specific for Mark-I containment.

2/2 230000 RHR/LPCI:

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

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

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.

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 (see Note)

Type Code*

Describe activity to be performed Conduct of Operations N

Perform Daily Operations Log Surveillance for SLC Operability.

GJPM-OPS-ADM04 K/A 2.1.25: 2.8 Conduct of Operations N/A Equipment Control N

Prepare a Tagout Tags Sheet for a Protective Tag out Clearance.

GJPM-OPS-ADM01 K/A 2.2.13: 3.6 Radiation Control M

Identify Entry/Exit Requirements for accessing a High Radiation Area / Contamination Area.

GJPM-OPS-RP01 K/A 2.3.1: 2.6; 2.3.4: 2.5 Emergency Procedures/Plan N

Loss of Shutdown Cooling - Determine time to 200°F 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

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 (see Note)

Type Code*

Describe activity to be performed Conduct of Operations N

Perform SRO review of the Daily Jet Pump Surveillance.

GJPM-SRO-ADM01 K/A 2.1.33: 4.0 Conduct of Operations M

Review the Plant Chemistry Report and determine any required actions GJPM-SRO-ADM03 K/A 2.1.25: 3.1; 2.1.34: 2.9 Equipment Control N

Perform Tag Reviewer review of Protective Tag out Clearance.

GJPM-OPS-ADM02 K/A 2.2.13: 3.8 Radiation Control M

Review Liquid Radwaste Discharge Permit.

GJPM-SRO-ADM02 K/A 2.3.6: 3.1 Emergency Procedures/Plan M

Given plant conditions, determine entry into the Site Emergency Plan and complete the initial notification form. ATWS 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 Code*

Safety Function

a. 202001 Recirculation System - Startup idle Recirculation Pump w/

High Vibration requiring manual pump trip.

S; N; A; L

1

b. 209002 High Pressure Core Spray System - Operate HPCS in CST-to-CST mode w/failure of HPCS minimum flow valve S; D; A 2

ESF

c. 264000 Emergency Generators - Parallel of Emergency Generator (with load) to the grid S; N 6

ESF

d. 400000 Component Cooling Water System - Rotate CCW pumps w/CCW pump trip S; B; A 8
e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for RPV pressure control w/failure of RCIC turbine speed controller S; N; A 3
f. 219000 RHR/LPCI: Suppression Pool Cooling Mode - Secure RHR from Containment Spray mode to Suppression Pool Cooling mode w/trip of ECCS pump requiring manual RHR alignment to LPCI mode S; N; A 5

ESF

g. 201005 Rod Control and Information System - Bypass a Control Rod in the RACS C; D 7
h. 239003 Main Steam Isolation Valve Leakage Control System - Start the Outboard MSIV LCS w/ blower failure requiring start of the Inboard MSIV LCS C; N; A 9

ESF In-Plant Systems@ (3 for RO; 3 for SRO-I; 3or2 for SRO-U)

i. 211000 Standby Liquid Control System - Perform SLC Pump A Monthly Surveillance R; N 1
j. 262002 Uninterruptible Power Supply (A.C./D.C.) - Start up Static Inverter 1Y81 D

6

k. 286000 Fire Protection System - Align Fire Water for injection to the reactor via LPCS and RHR C per EP Attachment 26 R; E; L; D

8

@ 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 (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 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 Code*

Safety Function

a. 202001 Recirculation System - Startup idle Recirculation Pump w/

High Vibration requiring manual pump trip.

S; N; A; L

1

b. 209002 High Pressure Core Spray System - Operate HPCS in CST-to-CST mode w/failure of HPCS minimum flow valve S; D; A 2

ESF

c. 264000 Emergency Generators - Parallel of Emergency Generator (with load) to the grid S; N 6

ESF

d. 400000 Component Cooling Water System - Rotate CCW pumps w/CCW pump trip S; B; A 8
e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for RPV pressure control w/failure of RCIC turbine speed controller S; N; A 3
f. 219000 RHR/LPCI: Suppression Pool Cooling Mode - Secure RHR from Containment Spray mode to Suppression Pool Cooling mode w/trip of ECCS pump requiring manual RHR alignment to LPCI mode S; N; A 5

ESF

g. 201005 Rod Control and Information System - Bypass a Control Rod in the RACS C; D 7
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 Monthly Surveillance R; N 1
j. 262002 Uninterruptible Power Supply (A.C./D.C.) - Start up Static Inverter 1Y81 D

6

k. 286000 Fire Protection System - Align Fire Water for injection to the reactor via LPCS and RHR C per EP Attachment 26 R; E; L; D

8

@ 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 (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 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 Code*

Safety Function

a. N/A
b. N/A
c. N/A
d. N/A
e. 217000 Reactor Core Isolation Cooling System - Operate RCIC for RPV pressure control w/failure of RCIC turbine speed controller S; N; A 3
f. 219000 RHR/LPCI: Suppression Pool Cooling Mode - Secure RHR from Containment Spray mode to Suppression Pool Cooling mode w/trip of ECCS pump requiring manual RHR alignment to LPCI mode S; N; A 5

ESF

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 Monthly Surveillance R; N 1
j. 262002 Uninterruptible Power Supply (A.C./D.C.) - Start up Static Inverter 1Y81 D

6

k. 286000 Fire Protection System - Align Fire Water for injection to the reactor via LPCS and RHR C per EP Attachment 26 R; E; L; D

8

@ 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 (C)ontrol Room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 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 REVISION 2-18-9 SCENARIO 1 NUREG 1021 REVISION 9 PAGE 2 of 20 Event No.

Malf. No.

Event Type*

Event 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.

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 REVISION 2-18-9 SCENARIO 2 NUREG 1021 REVISION 9 PAGE 2 of 23 Event No.

Malf. No.

Event Type*

Event 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 e51187a e51187b M (ALL)

Respond to a RCIC steam line break in the RCIC room 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.

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