ML14350A124

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Initial Exam 2014-301 Draft Administrative Documents
ML14350A124
Person / Time
Site: Brunswick  Duke energy icon.png
Issue date: 12/11/2014
From:
NRC/RGN-II
To:
Progress Energy Carolinas
Shared Package
ML14350A180 List:
References
50-324/14-301, 50-325/14-301 50-324/OL-14, 50-325/OL-14
Download: ML14350A124 (21)
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ES-401 1 Rev. 9 BWR Examination Outline Form Es-401-1 Facility Brunswick Date of Exam: 2014 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total 1 4 3 3 4 3 3 20 3 4 7
1. . -

Emergency& 1 2 1 1 1 1 7 1 2 3 2

Abnormal Plant N/A N/A Evolutions 5 5 4 5 4 4 27 4 6 10 Tier Totals 1 3 2 3 2 2 2 2 2 3 3 2 26 2 3 5

2. 1 1 1 1 1 1 1 2 1 1 1 12 0 1 2 3 2 . -

Plant Systems 4 3 4 3 3 3 3 4 4 4 3 38 3 5 8 Tier Totals -

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 1 2 2 2
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 ofthe 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 'V1 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 KIA 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

Es-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO 295001AK1.02 Partial or Complete Loss of Forced 3.3 3.5 ~ 0 0 0 0 0 0 0 0 0 0 Power/flow distribution .............................. .

Core Flow Circulation /1 & 4 295003AA2.05 Partial or Complete Loss of AC /6 3.9 4.2 0 0 0 0 0 0 0 ~ 0 0 0 Whether a partial or complete loss of A. C. power has occurred ............................................. .

295004AA 1.03 Partial or Total Loss of DC Pwr I 6 3.4 3.6 0 0 0 0 0 0 ~ 0 0 0 0 A.C. electrical distribution ........... .............. .

295005AK1.01 Main Turbine Generator Trip I 3 4.o 4.1 ~ 0 0 0 0 0 0 0 D 0 D Pressure effects on reactor power....................

295006AK1.02 SCRAM /1 3.4 3.7 ~ 0 D 0 0 0 0 0 0 0 0 Shutdown margin ........... ........................... .

$. Control Room Abandonment /7 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 Control room HVAC ...... .. ..... ........................

295018AA1.01 Partial or Total Loss of CCW /8 3.3 3.4 0 0 0 0 0 0 ~ 0 0 0 0 Backup systems .. ... ... .. .. .................... .. ......

295019G2.4.47 Partial or Total Loss of lnst. Air /8 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

295021AK1 .02 Loss of Shutdown Cooling /4 3.3 3.4 ~ 0 0 0 0 0 0 0 0 0 0 Thermal stratification ........ ................ .. .. ... .

295023AK2.06 Refueling Ace Cooling Mode I 8 3.4 3.8 0 ~ 0 0 0 0 0 0 0 0 0 Containment ventilation: Mark-111 ................... .

295024EA1.14 High Drywell Pressure /5 3.4 3.5 0 0 0 0 0 0 ~ 0 0 0 0 Drywell ventilation system .......................... ..

Page 1 of 2 11/08/2013 6:03AM

E5-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KG A1 A2 A3 A4 G TOPIC:

RO SAO 295025EK3.09 High Reactor Pressure /3 3.7 3.7 D D ~ D D 0 D D D D D Low-low set initiation: Plant-Specific .............. .

295026G2.1.28 Suppression Pool High Water Temp. I 4.1 4.1 D D D D D D D D D 0 ~ Knowledge of the purpose and function of major system 5 components and controls.

295028EK2.03 High Drywall Temperature /5 3.6 3.8 D ~ D D 0 D D D D D D Reactor water level indication ...................... ..

295030G2.2.38 Low Suppression Pool Wtr Lvl/5 3.6 4.5 D D D D D D D D 0 D ~ Knowledge of conditions and limitations in the facility license.

295031 EA2.03 Reactor Low Water Level/ 2 4.2 4.2 D D D D D 0 D ~ D D D Reactor pressure .............................. .

295037EA1.01 SCRAM Condition Present and Power 4.6 4.6 ODDDDD~DDDD Reactor Protection System .............................

Above APRM Downscale or Unknown

/1 295038EK3.03 High Off-site Release Rate /9 3.7 3.9 DD~DDDOOODD Control room ventilation isolation: Plant-Specific ...

600000AA2.04 Plant Fire On Site I 8 2.8 3.1 DDDDDDO~ODD The fire's extent of potential operational damage to plant equipment 700000AK3.01 Generator Voltage and Electric Grid 3.9 4.2 DD~DDDODDDD Reactor and Turbine trip criteria Distrurbancecs Page 2 of 2 11/08/2013 6:03AM

ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 295008AA2.01 High Reactor Water Level/2 3.9 3.9 D D D D D D D ~ D D D Reactor water level. ..................................

295014AK1.06 Inadvertent Reactivity Addition /1 3.8 3.9 ~ D D D D D D D D D D Abnormal reactivity additions ........................ .

295015AK3.01 Incomplete SCRAM /1 3.4 3.7 D D ~ D 0 0 0 D 0 0 0 Bypassing rod insertion blocks ....................... .

295032EK2.04 High Secondary Containment Area 3.6 3.8 D ~ 0 D 0 0 0 D 0 0 0 PCIS/NSSSS .. ..... .................................... .

Temperature /5 295033G2.4.45 High Secondary Containment Area 4.1 4.3 0 D D D 0 D D D 0 D ~ Ability to prioritize and interpret the significance of each Radiation Levels I 9 annunciator or alarm.

295034EK2.03 Secondary Containment Ventilation 4.3 4.5 0 ~ 0 0 0 D D 0 0 D D SBGT/FRVS: Plant-Specific ............ ........ ........

High Radiation /9 295036EA1 .03 Secondary Containment High 2.8 3.o 0 D D 0 0 D ~ 0 0 0 0 Radwaste ..............................................

Sump/Area Water Level/5 Page 1 of 1 11/08/2013 6:03 AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 203000A1.05 RHRILPCI: Injection Mode 3.8 3.7 DDDDDD~DDDD Suppression pool level 203000A3.03 RHRILPCI : Injection Mode 3.7 3.6 DOOOOOOO~OO Pump discharge pressure 205000K4.05 Shutdown Cooling 3.6 3.7 DDD ~ ODODDDD Reactor cooldown rate 206000A2.08 HPCI 3.9 4.2 DDDDDDD~DDD tHigh suppression pool temperature: BWR-2,3,4 206000K2.04 HPCI 2.5 2.7 D~DDDDDDDDD Turbine control circuits: BWR-2,3,4 209001 K5.05 LPCS 2.5 2.5 DDDD~DDDDDD System venting 211000A4.02 SLC 4.2 4.2 DDDDDDDDD~D SBLC control switch 212000K2.01 RPS 3.2 3.3 D~DDDDDDDDD RPS motor-generator sets 215003K1.07 IRM 3.0 3.0 ~DDDDDDDDDD Reactor vessel 215004K3.02 Source Range Monitor 3.4 3.4 DD ~ DDDDDDDD Reactor manual control: Plant-Specific 215004K5.03 Source Range Monitor 2.8 2.8 DDDD~DDDDDD Changing detector position Page 1 of 3 11/08/2013 6:03AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401*1 KA NAME I SAFETY FUNCTION: lA K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO 215005A2.06 APRM I LPRM 3.4 3.5 0 0 0 0 0 0 0 ~ 0 0 0 Recirculation flow channels upscale 217000A4.07 RCIC 3.9 3.8 0 0 0 0 0 0 0 0 0 ~ 0 Reactor pressure 217000G2.4.4 RCIC 4.5 4.7 0 0 0 0 0 0 0 0 0 0 ~ Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

21 BOOOA3.03 ADS 3.7 3.8 0 0 0 0 0 0 0 0 ~ 0 0 ADS valve acoustical monitor noise: Plant-Specific 223002G2.2.36 PCIS/Nuclear Steam Supply Shutoff 3.1 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 239002K1.05 SRVs 3.1 3.3 ~ 0 0 0 0 0 0 0 0 0 0 Plant air systems: Plant-Specific 239002K6.03 SRVs 2.7 2.9 0 0 0 0 0 ~ 0 0 0 0 0 A.C. power: Plant-Specific 259002K3.07 Reactor Water Level Control 3.4 3.4 0 0 ~ 0 0 0 0 0 0 0 0 Reactor water level indication 261000K1.11 SGTS 3.2 3.3 ~ 0 0 0 0 0 0 0 0 0 0 Primary containment pressure 262001A4.02 AC Electrical Distribution 3.4 3.4 0 0 0 0 0 0 0 0 0 ~ 0 Synchroscope, including understanding of running and incoming voltages 262002K6.03 UPS (AC/DC) 2.7 2.9 0 0 0 0 0 ~ 0 0 0 0 0 Static inverter Page 2 of 3 11/08/2013 6:03AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO 263000A 1.01 DC Electrical Distribution 2.5 2.8 0 0 0 0 0 0 ~ 0 0 0 0 Battery charging/discharging rate 264000K4.05 EDGs 3.2 3.5 0 0 0 ~ 0 0 0 0 0 0 0 Load shedding and sequencing 300000K3.01 Instrument Air 2.7 2.9 0 0 ~ 0 0 0 0 0 0 0 0 Containment air system 400000A3.01 Component Cooling Water 3.0 3.0 0 0 0 0 0 0 0 0 ~ 0 0 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the ccws Page 3of3 11/08/2013 6:03AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401*1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KG A1 A2 A3 A4 G TOPIC:

RO SAO 201002A1.04 RMCS 3.6 3.5 0 0 0 0 0 0 ~ 0 0 0 0 Overall reactor power 201003A2.09 Control Rod and Drive Mechanism 3.2 3.4 O O O 0 O 0 0 ~ 0 0 0 Low reactor pressure 201006K6.05 RWM 2.7 2.7 0 0 0 0 0 ~ 0 0 0 0 0 Steam flow input: P-Spec(Not-BWR6) 214000A4.01 RPIS 3.2 3.3 0 0 0 0 0 0 0 0 0 ~ 0 RCIS rod action control bypass switches 216000A2.02 Nuclear Boiler lnst. 2.9 3.0 0 0 0 0 0 0 0 ~ 0 0 0 Instrument line plugging 219000K2.01 RHRILPCI: Torus/Pool Cooling Mode 2.5 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Valves 230000A3.01 RHRILPCI: Torus/Pool Spray Mode 3.4 3.3 0 0 0 0 0 0 0 0 ~ 0 0 Valve operation 245000K1 .07 Main Turbine Gen./ Aux. 2.5 2.5 ~ 0 0 0 0 0 0 0 0 0 0 Plant air systems 256000K4.11 Reactor Condensate 2.9 3.0 O O O ~ O 0 0 0 0 0 0 Isolation of SJAE's on low flow: Plant-Specific 259001K5.03 Reactor Feedwater 2.8 2.8 0 O O O ~ 0 O O 0 0 0 Turbine operation: TORFP's-Only 271000K3.01 Offgas 3.5 3.5 O 0 ~ 0 0 0 0 0 0 0 0 Condenser vacuum Page 1 of 2 11/08/2013 6:03AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO 290001 G2.4.34 Secondary CTMT 4.2 4.1 D D D D D D D D D D ~ Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Page 2 of 2 11/08/2013 6:03AM

E5-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO G2.1.25 Conduct of operations 3.9 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

G2.1.27 Conduct of operations 3.9 4 0 D D D D D 0 0 D D ~ Knowledge of system purpose and or function .

G2.1.31 Conduct of operations 4.6 4.3 0 D D 0 0 D 0 0 D D ~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

G2.2.13 Equipment Control 4.1 4.3 0 0 D D D D D 0 0 0 ~ Knowledge of tagging and clearance procedures.

G2.2.3 Equipment Control 3.8 3.9 0 D 0 0 D D D 0 D D ~ (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.2.41 Equipment Control 3.5 3.9 0 0 D D D D D 0 0 D ~ Ability to obtain and interpret station electrical and mechanical drawings G2.3.13 Radiation Control 3.4 3.8 0 D 0 0 0 0 0 0 0 0 ~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.21 Emergency Procedures/Plans 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the parameters and logic used to assess the status of safety functions G2.4.9 Emergency Procedures/Plans 3.8 4.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of AHA) mitigation strategies.

Page 1 of 1 11/08/2013 6:03AM

ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO 295001G2.1.27 Partial or Complete Loss of Forced 3.9 4 0000000000~ Knowledge of system purpose and or function.

Core Flow Circulation 11 & 4 295005G2.2.22 Main Turbine Generator Trip I 3 4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of limiting conditions for operations and safety limits.

295025G2.4.45 High Reactor Pressure I 3 4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to prioritize and interpret the significance of each annunciator or alarm .

295026EA2.01 Suppression Pool High Water Temp. I 4.1 4.2 O 0 0 0 0 0 0 ~ 0 0 0 Suppression pool water temperature ................ ... .

5 295030EA2.02 Low Suppression Pool Wtr Lvll5 3.9 3.9 0 0 0 0 0 0 0 ~ 0 0 0 Suppression pool temperature ..........................

295031G2.4.30 Reactor Low Water Levell2 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

295038EA2.03 High Off-site Release Rate 19 3.5 4.3 0 0 0 0 0 0 0 ~ 0 D D Radiation levels .......................... ..............

Page 1 of 1 1110812013 6:03AM

ES-401 I REV 9 SRO T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO 295015G2.4.20 Incomplete SCRAM /1 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of operational implications of EOP warnings, cautions and notes.

295022AA2.02 Loss of CAD Pumps /1 3.3 3.4 0 0 0 0 0 0 0 ~ 0 0 0 CAD system status ................. :.................. .

295033G2.2.44 High Secondary Containment Area 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability to interpret control room indications to verify the Radiation Levels I 9 status and operation of a system , and understand how operator actions and directives affect plant and system conditions Page 1 of 1 11/08/2013 6:03AM

ES-401, REV 9 SAO T2G1 BWR EXAMINATION OUTLINE FORM ES-401*1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

AO SAO 203000A2.16 AHRILPCI: Injection Mode 4.4 4.5 0 0 0 0 0 0 0 ~ 0 0 0 Loss of coolant accident 215003G2.4.30 lAM 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

215005G2.2.3 APAM I LPAM 3.8 3.9 0 0 0 0 0 0 0 0 0 0 ~ (multi-unit license) Knowledge of the design, procedural and operational differences between units.

261000G2.2.39 SGTS 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of less than one hour technical specification action statements for systems.

400000A2.01 Component Cooling Water 3.3 3.4 0 0 0 0 0 0 0 ~ 0 0 0 Loss of CCW pump Page 1 of 1 11/08/2013 6:03AM

ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR k1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:

RO SRO 201006G2.4.47 RWM 4.2 4.2 DD DDDDDDDD~ Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

290001 G2.4.45 Secondary CTMT 4.1 4.3 DD DDDDDDDD~ Ability to prioritize and interpret the significance of each annunciator or alarm.

290003A2.04 Control Room HVAC 3.1 3.3 DD DDDDD~DDD Initiation/failure of fire protection system Page 1 of 1 11/08/2013 6:03AM

Es-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SAO G2.1.39 Conduct of operations 3.6 4:3 D D D D D D D D D D ~ Knowledge of conservative decision making practices G2.2.3 Equipment Control 3.8 3.9 D D D D D D D D D D ~ (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.2.37 Equipment Control 3.6 4.6 D D D D D D D D D D ~ Ability to determine operability and/or availability of safety related equipment G2.3.14 Radiation Control 3.4 3.8 D D D D D D D D D D ~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 D D D D D D D D D D ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.4.27 Emergency Procedures/Plans 3.4 3.9 0 D D D 0 0 0 0 0 D ~ Knowledge of ' fire in the plant' procedures.

G2.4.45 Emergency Procedures/Plans 4.1 4.3 D D D D 0 0 0 D 0 0 ~ Ability to prioritize and interpret the significance of each annunciator or alarm .

Page 1 of 1 11/08/2013 6:03AM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Brunswick Date of Examination: October 2014 Examination Level: ROB SRO B Operating Test Number: FINAL Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Calculate GAFS and T.S. Assessment R, M (COO01) 2.1.23 Ability to perform specific system and integrated (RO, then SRO) plant procedures during all modes of operation.

Conduct of Operations Verifying SLC Operating Parameters R M (COO-02) 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument (RO) interpretation.

Conduct of Operations Evaluate Plant Chemistry Limits During Condenser R D Tube Leak (COO-03) 2.1 .34 Knowledge of primary and secondary plant SRO chemistry limits.

Equipment Control Evaluate a CRD Clearance R, D (RO and SRO) 2.2.13 Knowledge of tagging and clearance procedures.

Radiation Control Determine Total Dose for ALARA R D (RO and SRO) 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions Emergency Procedures/Plan Classify an Emergency per PEP-2.1 R, N (SRO Only) 2.4.29 Knowledge of the emergency plan.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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)

Conduct of Operations (COO-O1) (RO, then SRO)

Calculate GAFs and Tech Spec Assessment R, M K/A 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation.

This is a modified JPM that requires the Exam inee to calculate Gain Adjustment Factors (GAF5) per OPT-Ol .8C, and then the SRO determines the Tech Spec implications based on the calculations. Numbers were modified to provide different values for calculated GAFs and different GAFs that were out of spec.

Conduct of Operations (COO-02) (RO)

Verifying SLC Operating Parameters K/A 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

This is a modified JPM that requires the RO to verifying SLC Tank operating parameters. This is part of the RO DSR. Parameters were changed to provide satisfactory results.

Conduct of Operations (COO-03) (SRO)

Evaluate Plant Chemistry Limits during Condenser Tube Leak R, M 2.1.34 Knowledge of primary and secondary plant chemistry limits.

This is a bank JPM that was used on the 2008 NRC Exam. It requires the Examinee to evaluate plant chemistry limit lAW OAOP-26.0, High Reactor Coolant Or Condensate Conductivity and then determine the determine applicable actions required by OAI-81, Water Chemistry Guidelines, related to plant operations.

Equipment Control (RO and SRO)

Evaluate a Clearance Boundary 2A CRD Pump R, D K/A 2.2.13 Knowledge of tagging and clearance procedures.

This is a bank JPM that was used on the 2008 NRC exam. Given a boundary request form and a written clearance, the Examinee must evaluate the clearance for safety and accuracy.

Radiation Control (RO and SRO)

Determine Total Dose for ALARA R, M K/A 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

The is a bank JPM that was used on the previous NRC Exam (2012). It required the Examinee to determine the travel path which gives the lowest dose, ALARA.

Emergency ProcedureslPlan (SRO only)

Classify and Emergency lAW OPEP-2.1 R, N K/A 2.4.40 Knowledge of SRO responsibilities in Emergency Plan implementation.

This is a new JPM that requires the SRO Examinee to classify and emergency.

Although classification JPMs have been use in previous exams, the classification requirements for this JPM are new.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Brunswick Date of Examination: OCT 2014 Exam Level: RO SRO-I SRO-U Operating Test No.: DRAFT Control Room Systems@ (8 for RO); (7 for SRO-l)

System I JPM Title Type Code* Safety Function

a. Start second Recirc Pump S, P, A 1
b. Start HPCI with Exhaust Diaphragm failure S, D, L, A 2
c. Emergency Equalize around MSIVs S, P 3
d. SDC restoration with RHR overload S, D, A, L, EN 4
e. (RO only) Terminate PC venting S, D 5
f. Bus E3 Normal feeder to DG3, with DG Ground S, D, A 6
g. Place RPS to Alternate S,D 7
h. Perform PASS lineup S, N 9 In-Plant Systems@ (3 for ROISRO-l)

I. SEP-09 with RB Accessible R, D, E 2

j. Secure Condensate Pump IAWAOP-32 (Bkr Failure) R, A, E, D 7
k. Place IA Dryer in Sweep Mode R, N, E 8

@ All RO and SRO-l 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-l I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrombank 91814 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - I - I 1 (control room system)

(L)ow-Power/Shutdown 1 I 1 I1 (N)ew or (M)odified from bank including 1(A) 2 I 2/ 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

a. Recovery from Recirc System Runback 202001 A4.01 Ability to operate and/or monitor in the control room:

Recirculation Pumps This is a previous exam (2012) simulator alternate path JPM that will have the examinees preparing to start the second recirc pump.

When the pump is started and the discharge valve is being throttle d

open the only running pump will trip requiring a reactor manual scram. This JPM was randomly selected from the 2012 exam.

b. Start HPCI with Exhaust Diaphragm failure 206000 A3.09 Ability to monitor automatic operation of HPCI including response to system isolation This is a banked JPM that will require the examinee to start HPCI for injection per the Hard Card and restore RPV water level. As an alternate path the exhaust diaphragm breaks and HCI does not auto isolate requiring manual isolation of HPCI.
c. Emergency Equalize around MSIVs 239001 A4.01 Ability to manually operate and or monitor in the Control Room:

MSIVs This is a banked simulator JPM that will require the examinee to perform the control operator actions associated with emergency equalization around the MSIVs. This JPM was randomly selected from the 2010-2 exam.

d. SDC restoration with RHR valve overload 295021 AA1 .04 Ability to manually operate Alternate Heat Removal Methods This is a low power banked simulator JPM that will require the examinee to perform Alternate Shutdown Cooling lAW OAOP-15.0.

As an alternate path the RHR pump has on overload condition.

e. (RO only) Terminate PC venting 295024 EA1 .19 Ability to operate/monitor Containment Atmosphere Control System as it applies to High Drywell Pressure This is a banked simulator JPM that will require the examinee to terminate Primary Containment Venting, using SEP-01, Section 4.
f. Bus E3 Normal feeder to DG3, with DG Ground 264000 A4.04 Ability to manually operate and/or monitor in the control room Manual start, loading, and stopping of emergency generator.

This is a banked simulator JPM that will require the examinee to place E3 on the DG. This is an alternate path JPM in that an annunciator will alert the operator to remove the load from the DG.

g. Place RPS to Alternate 212000 A2.02 Ability to predict the impacts of RPS bus power supply failure on RPS System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations.

This is a banked simulator JPM that will require the examinee to transfer RPS alternate power to alternate.

h. Perform PASS lineup 295038 EA1 .05 Ability to manually operate and/or monitor in the control room: Post Accident Sampling System (PASS).

This is a new simulator JPM that will require the examinee to lineup the Post Accident Sampling System for taking a sample.

i. SEP-09 with RB Accessible 295009 AA1 .02 Ability to operate or monitor the CRD System as it applies to low reactor water level.

This is a banked in-plant JPM that will require the examinee to simulate performing SEP-09, CRD System flow maximization using two pumps and the reactor building accessible. This JPM is performed in the RCA.

j. Secure Condensate Pump lAW AOP-32 (Bkr Failure) 295016 AA1 .06 Ability to operate and/or monitor the following as it they apply to Control Room Abandonment-Reactor Water Level.

This is a banked in-plant JPM that will require the examinee to simulate the actions associated with AOP-32. This JPM is alternate path in that the condensate pump does not trip requiring additional actions to trip the pump. This JPM is performed in the RCA.

k. Place IA Dryer in Sweep Mode 300000 A2.01 Ability to predict the impacts of Air Dryer and filter malfunctions on the Instrument Air System and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations.

This is a new in-plant JPM that will require the examinee to simulate setting the Service Air Dryer maximum sweep value to zero lAW OAOP-20.0. This JPM is performed in the RCA.

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