ML13339A754

Initial Exam 2013-301 Draft Administrative Documents

ML13339A754
Person / Time
Site:	Robinson
Issue date:	11/30/2013
From:	Michael Meeks Division of Reactor Safety II
To:
References
50-261/13-301
Download: ML13339A754 (27)

Text

WR!71E1J 6xAnl s;ni/z PLw c5iVL 1 ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: j4 j3, RINso,v Date of Examination:

Ji)ty Initials Item Task Description

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

?4 i4 R b. Assess whether the outline was systematically and randomly prepared in accordance with dV/

T I Section D.1 of ES-401 and whether all K!A categories are appropriately sampled. (4 T c. Assess whether the outline over-emphasizes any systems, evolUtions, or generic topics.

7 I/I

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. 927 474

2. a. Using Form ES-301 -5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S and major transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number u and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the lest two NRC examinations is within the lh,iits specified on the form T (3) no tasks are duplicated from the applicants audit test(s)

(4) the nuniber of new or modified tasks meets oreiceeds the miiim tins specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301 -1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered e in the appropriate exam sections. 1!! III

b. Assess whether the 10 CFR 55.41143 and 55.45 sampling is appropriate. W

c. Ensure that KFA importance ratings (except for plant-specific priorities) are at least 2.5. F?!

R d. Check for duplication and overlap among exam sections. A L e. Check the entire exam for balance of coverage. )91 7A

f. Assess whether the exam fits the appropriate job level (RO or SRO). m

a. Author flId1A6L

b. Facility Reviewer (*) 4?

c. NRC Chief Examiner (#) Sfid4OLAJ?. f7

d. NRC Supervisor ,41A,k. i4)i/cøZ / /s Note: # Independent NRC reviewer initial items in Column C; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines

- wj71E/V Ex4#i S4112,°1-E /i411 OIlILY

ES-401 PWR Examination Outline Form ES-401-2 Facility: H.B. ROBINSON Date of Exam: JULY 2013 ROK/ACapoyPoits_ SRO-Only Points Tier Group KKKKKKAAAAG A2 G* Total 1234561234

• Total 1.

Emergency &

1 3 3j 33 3 18 3 3 6 Abnormal 2 2 1 1 N/A 2 1 N/A 2 9 2 2 4 Evolutions Tier Totals 5 4 4 5 4 5 27 5 5 10 Pnt 2 IftO It ilL lii i02 Systems Tier Totals 3 4 2 4 3 3 4 4 3 4 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 7 Categories 2 2 3 3 ,jl 2 2 .2 Note: 1. Ensure that at least two toplcs 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 9ler 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. Systemsfevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and Sf0-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 arid 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.

8. on the following pages, enter the K/A numbers, a brief description of each topic, the topic importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G on the

• SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and Sf0-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 SF10 selections to K/As that are linked to 10 CFR 55.43.

ES4O1, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 008AK2.03 Pressurizer Vapor Space Accident /3 2.5 2.4 fl [2] Li Li Li Li Li LI [2] Controllers and positionors OO9EK1 .02 Small Break LOCA / 3 3.5 4.2 Li Li Li fl Use of steam tables 011 EG2.4.21 Large Break LOCA /3 4.0 4.6 fl Li Li Li Li fl Knowledge of the parameters and logic used to assess the status of safety functions 022AK3.07 Loss of Rx Coolant Makeup / 2 3 3.2 Li Li i ]J U [2] Isolating charging 025AK2.02 Loss of RHR System /4 3,2 3.2 fl [ [2] ]2] 2] 2] f2] fl Li [] LPI or Decay Heat RemovallRHR pumps 027AA1.02 Pressurizer Pressure Control System 3.1 3 Malfunction) 3 [} Li fl Li Li 2] } Li [] [] [] SCR-controlled heaters In manual mode 029EA64 ATWS / 1 3.9 3.8 Li LIE 2] Li [J ] Li 2] Li Li BIT inlet valve switches

/.,..-

038EK3.08 Steam Gen. Tube Rupture / 3 4.1 4.2 Li LI ] (( [] [] [2] Li [] Li Criteria for securing RCP 040AA2.02 Steam Line Rupture Excessive Heat 4.6 4.7 Transfer) 4 Li Li El LI Li Li Li Li Li [] Conditions requiring a reactor trip 054AK1 .01 Loss of Main Feedwater / 4 4.1 4.3 Li Li Li El Li Li Li LI Li Li MFW line break depressurizes the S/G (similar to a steam line break) 055EG2.4.21 Station Blackout / 6 4.0 4.6 Li Li Li Li Li Li Li Li Li Li Knowledge of the parameters and logic used to assess the status of safety functions Page 1 of 2 1/30/2013 1:23 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 056AA1 .15 Loss of Off-site Power? 6 2.7 2.9 Service water booster pump h_D 057AA2.19 Loss of Vital AC Inst. Bus? 6 4 4.3 The plant automatic actions that will occur on the toss of a vital ac electrical instrument bus 058AK1.Ol LossofDCPower/6 2.8 3.1 E E E E fl Batterychargerequipmentandinstrumentation 077AK3.02 Generator Voltage and Electric Grid 3.6 3.9 Actions contained in abnormal operating procedures for Disturbances I 6 voltage and grid disturbances WEO4EK2.l LOCA Outside Containment? 3 3.5 3.9 Components and functions of control and safety systems, Including Instrumentation, signals, iriteriocks, failure modes and automatic and manual features.

weO5EG2.4.6 Inadequate Heat Transfer Loss of 3.7 4.7 Secondary Heat Sink / 4 J J fl LI LI LI LI LI Q Knowledge symptom based EOP mitigation strategies.

WE1 1 EA2.2 Loss of Emergency Coolant Recirc. / 4 3.4 4.2 LI LI LI LI LI LI LI 1I LI [1 C Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

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ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028AA2.03 Pressurizer Level Malfunction /2 2.8 3.3 0 EEl LI LI LI U U J Charging subsystem flow indicator and controller 032AA1 .01 Loss of Source Range NI 17 3.1 3.4 jJ J Manual restoration of power LI 033AG2.2.22 Loss of Intermediate Range NI / 7 4.0 4.7 IJ f C LI C U C LI LI LI Knowledge of limiting conditions for operations and safety limits.

060AK3.02 Accidental Gaseous Radwaste Rel. /9 3.3 3.5 Isolation of the auxiliary building ventilation LI LI U U Q 067AK1 .02 Plant Fire On-site/B 3.1 3.9 } fl LI LI LI LI El El LI LI LI Fire fighting 068AG23 Control Room Evac. / 8 3.1 4.2 Li LI LI LI LI LI LI LI El El Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 076AA1 .04 High Reactor Coolant Activity / 9 3.2 3.4 El LI LI Li U LI LI LI LI LI Failed fuel-monitoring equipment WEO8EK1 .2 RCS Overcooling PTS /4 3.4 4.0 jJ (J ELI U Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

WE1OEK2.2 Natural Circ. With Seam Void/4 3.6 3.9 j( LI U] U] [1 LI LI LI LI LI Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

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ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 1<4 1<5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003A1 .04 Reactor Coolant Pump 2.6 2.5 Li [1 Li El Li LI LI LI LI LI RCP oil reservoir levels 003K4.02 Reactor Coolant Pump 2,5 2.7 Li [] Li [] [] [] J Prevention of cold water accidents or transients 004K3.08 Chemical and Volume Control 3.6 3.8 Li Li (j LI LI LI Li Li Li Li RCP seal injection 0041<6.26 ChemIcal and Volume Control 3.8 4.1 LI LI LI j LI LI Li LI LI Methods of pressure control of solid plant (PZR relief and water inventory) 005A2.04 Residual Heat Removal 2.9 2.9 LI Li LI LI LI LI LI LI LI LI LI RHR valve malfunction 006A4.02 Emergency Core Cooling 4.0 3.8 LI Li Li LI LI LI ] LI LI ] Valves 006K5.10 Emergency Core Cooling 2.5 2.9 LI LI Li Li Li LI Li Li Li Li Theory of thermal stress 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 Li Li Li LI Li Li LI Li LI LI Method of forming a steam bubble in the PZR 008A2.07 Component Cooling Water 2.5 2.8 LI Li Li Li LI LI LI II Li LI LI Consequences of high or low CCW flow rate and tempera- ture; the flow rate at which the CCW standby pump will start 010K1.08 Pressurizer Pressure Control 3.2 I) Li Li Li LI LI Li Li Li El LI PZR LCS 012A3.04 Reactor Protection 2.8 2.9 Li Li LI Li Li LI [IL] Li Li Circuit breaker Page 1 of 3 1/30/2013 1:23PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki 1(2 K3 1(4 K5 K6 Al A2 AS A4 G TOPIC:

RO SRO T

0131(2.01 Engineered Safety Features Actuation 3.6 3.8 [] [] El El E] LI L] EEC] ESFASIsafeguards equipment control 022A3.0l Containment Cooling 4.1 4.3 El El [1 [1 El C] El LI El El Initia tion of safeguards mode of operation 026G2.2.42 Containment Spray 3.9 4.6 EL] ED El D ELIDE Ability to recognize system parameters that are entry-level conditions for Technical Specifications 039A4.04 Main and Reheat Steam 3.8 3,9 LIE] LIE] El El EEE El Emergency feedwater pump turbines 059A2.12 Main Feedwater 3.1 3.4 LIE ED El El EiElE El Failure of feedwater regulating valves 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 ED EEl El DEED El Pumps 062K3.03 AC Electrical Distribution 3.7 3,9 EEl El El EEL] El El DC system 063A1.01 DC Electrical Distribution 2.5 3.3 ED LIE El El JEEU E Battery capacity as it is affected by discharge rate 064G2.l .27 Emergency Diesel Generator 3,9 4 ElEl EEl El El DEED Knowledge of system purpose and or function.

0641(2.01 Emergency Diesel Generator 2.7 3.1 E LID El El El ED LI El Air compressor 073A4.0l Process Radiation Monitoring 3.9 3.9 LIE] ED El El ED [1 El Effluent release Page 2 of 3 1/30/2013 1:23PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 073K4.02 Process Radiation Monitoring UWL1LJL Letdown isolation on high-RCS activity 076A1.02 Service Water 2.6 2.6 cJ LE1[1[]L] Reactor and turbine building closed cooling water tern peratures.

076K2.08 Service Water 3.1 3.3 EiLLDL1LIE1LJ ESF-actuated MOVs 078G2.4.50 Instrument AIr 4.2 4.0 EIEI[..1 L1EflED Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

078K1.04 Instrument Air 2.6 2.9 LID LI Li LI LI LI LID Li Cooling water to compressor 103K4.04 Containment 2.5 3.2 fl LI DDEEDLiUD Personnel access hatch and emergency access hatch Page 3 of 3 1/30/2013 1:23PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002A2.04 Reactor Coolant 4.3 4.6 C] C] C] C] C] C] C) [] C] C] Cl Loss of heat sinks 011K6.03 Pressurizer Level Control 2.9 3.3 C] C] C] Ci C] Cl C] Relationship between PZR level and PZR heater control circuit 014G2.1.30 Rod Position Indication 4.4 4.0 C] c:i H El Ci C] C] C] C] C] Ability to locate and operate components, including local 01 7A1 .01 In-core Temperature Monitor 3.7 3.9 C] C] C] C] C] [] (J C] C] C] C] Core exit temperature 027K2.0l Containment iodine Removal 3.1 3.4 C] C] C] C]C] C] Li Li C] Fans 029A4.Ol Containment Purge 2.5 2.5 fl C] C] C] C] C] [] C] C] çj C] Containment purge flow rate 033K4.0l Spent Fuel Pool Cooling 2.9 3.2 C] C] C] [ [IC] Cl C] C] Maintenance of spent fuel level 035K5.0l Steam Generator 3.4 3.9 F] C] C] C] Effect of secondary parameters, pressure and C] [J F] [I C] []

temperature on reactivity 055A3.03 Condenser Air Removal 2.5 2.7 C] C] C] C] C] C] C] C] C] C] Automatic diversion of CARS exhaust 068K1 07 LiquId Radwaste 27 29 [] C] C] C] C] C] C] C] F] F] C] Sources of hquid wastes for LRS Page 1 of 1 1/30/2013 1:23 PM

ES-401 REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.14 Coriductof operations 3.1 3.1 LI LI LI LI LI LI LI LI LI LI {1 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.

G2.1 .40 Conduct of operations 2.8 3.9 LI LI LI LI LI H LI LI LI LI b Knowledge of refueling administrative requirements G2.2.12 Equipment Control 3.7 4.1 LI LI LI LI LI LI LI LI LI LI Knowledge of surveillance procedures.

G2.2.7 Equipment Control 2.9 3.6 LI [1 H LI LI LI LI LI LI LI Knowledge of the process for conducting special or Intrequent tests G2.3.14 Radiation Control 3.4 3.8 LI El LI LI LI LI LI LI LI LI Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.15 Radiation Control 2.9 3.1 LI LI [1 LI LI LI LI LI LI LI Knowledge of radiation monitoring systems G2.3.4 Radiation Control 3.2 3.7 LI LI LI LI LI LI LI LI LI LI Knowledge of radiation exposure limits under normal and emergency conditions G2.4.12 Emergency Procedures/Plans 4.0

• LI LI LI LI LI LI LI LI LI LI Knowledge of general operating crew responsibilities during emergency operations.

G2,4.26 Emergency Procedures/Plans 3.1 3.6 LI LI LI LI LI LI LI LI LI LI [} Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

G2.4.39 Emergency Procedures/Plans 3.9 3.8 LI H LI LI LI LI LI LI LI LI Knowledge of the ROs responsibilities in emergency plan implementation.

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ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OOBAG2.1 .7 Pressurizer Vapor Space Accident / 3 4.4 4.7 [J El El fl Li El El El fl [j Ability to evaluate plant performance and make operational judgments based on cperating characteristics, reactor behavior and instrument interpretation.

054AG2.4.35 Loss of Main Feedwater/ 4 3.8 4.0 Li El El El El El fl fl [] ( Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 055EA2.06 Station Blackout / 6 3.7 4.1 El El El El El El El El El Q Faults and lockouts that must be cleared prior to re energizing buses 058AG2. 1.19 Loss of DC Power! 6 3,9 3.8 El El El Li El El El El El El Ability to use plant computer to evaluate system or component status.

077AA2.02 Generator Voltage and Electric Grid 3.5 3.6 Disturbances / 6 El El El El Li El El El El El Voltage outside the generator capability curve WEO5EA2.2 Inadequate Heat Transfer Loss of 3.7 4.3 Li El El El El El El Adherence to appropriate procedures and operation Secondary Heat Sink /4 El El El within the limitations in the facilitys license and amendments.

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ES-401, REV 9 SRO Ti G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 AA2.05 Continuous Rod Withdrawal / 1 4.4 4.6 Uncontrolled rod withdrawal from available Indications 060AG2.2.37 Accidental Gaseous Radwaste Rel. /9 3.6 4.6 ]L1EEJJEE Ability to determine operability and/or availability of safety related equipment 061AA2.02 ARM System Alarms /7 2.9 3.2 fl nLJiuLWc1L1L1n Normal radiation intensity for each ARM system channel wel4EG2.2.38 Loss of CTMT IntegrIty / 5 3.6 4.5 fl flLJL11l Knowledge of conditions and limitations in the facility license.

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ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR 1(1 K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO 012G2.l .20 Reactor Protection 4.6 4.6 Q El [1 El El El Ability to execute procedure steps.

El ....89G2.420 11aln gnu Fehettm 3.8 4.3 fl El El El [] El El fl r Knowledge of operational implications of EOP warnings,

, 4i /_- i_- cautions and notes.

063A2.02 DC Electrical Distribution 2.3 3.1 fl El E] [1 Loss of ventilation during battery charging 076A2.0l Service Water 3.5 3.7 El El El E] L] El i] El El El Loss of SWS 103A2,01 Containment 2.0 2.6 fl El El El El El El li?] El El El Integrated leak rate test Page 1 of 1 1/30/2013 1:23 PM

ES-401, REV 9 SRO T2G2 PWR EXAMiNATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028A2.0l Hydrogen Recombiner and Purge 3.4 3.6 flEJIflflJ Hydrogen recombiner power setting, determined by using Control plant data book 068A2.04 Liquid Radwaste EflUDI1WThHTh Failure of automatic Isolation 071 G2.4.46 Waste Gas Disposal 4.2 4.2 [jffl JEHZ1[1 Ability to verify that the alarms are consistent with the plant conditions.

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ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1(1 K2 K3 K4 K5 KG Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .38 Conduct of operations 3.7 3.8 Li Li j Li Li fl Knowledge of the stations requirements for verbal communication when implamenting procedures G2.2.13 Equipment Control 4.1 4.3 Li Li Li Li n Li Li ci Li Knowledge of tagging and clearance procedures.

G2.2.1 B Equipment Control 2.6 3.8 LI Li El El El El El El El El Knowledge of the process for managing maintenance activities during shutdown operations.

G2.3.13 Radiation Control 3.4 3.8 fl Li Li Li Li Li El Li (j Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.5 Radiation Control 2.9 2.9 fl Li El Li F] Li Li Li El Li } Ability to use radiation monitoring systems G2.4.23 Emergency Procedures/Plans 3.4 4.4 Li [I LI LI Li Li Li Li LI Li Knowledge of the bases for prioritizing emergency procedure Implementation during emergency operations.

G2.4.30 Emergency Procedures/Plans 2.7 4.1 LiLi ElLi [ILi Li Li Li El Knowledge of events related to system operations/status that must be reported to internal orginizatlons or outside agencies.

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: H B Robinson Date of Examination: 7/29/13 Examination Level: RO X SRO Operating Test Number: ILC-13 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations M, R Determine Power Distribution Flux Limits Conduct of Operations N, S Power Range Calorimetric During Power Operation Perform the monthly RVLIS Channel Check

. D, S lAW OST-054 Equipment Control s p Radiation Control M, R Calculate Low Dose Path Emergency N/A Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

ILC-13 NRC RO Admin JPM Summary 1LC-l3 NRC JPM Admin RO Al-I Determine Power Distribution Flux Limits G2. 1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR:41.5143.5145.12145.13)

The plant is at 70% RTP with a Xenon transient in progress. The program that calculates penalty points is inoperable. The candidate will be provided the 100% Target Value and the Target Band range along with seven sets of Power Data and individual Power Range Ni AFD readings over a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period. The candidate will be directed to manually calculate the Penalty Points in accordance with FMP-009, Power Distribution Control. Candidate will determine that a total of 105 penalty points have been accumulated over the course of the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> power ascension. (Modified Admin JPM)

ILC-13 NRC JPM Admin RO Al-2 Power Range Calorimetric During Power Operation G2.1.19 Ability to use plant computers to evaluate system or component status. (CFR 41.10 /45.12)

The plant is at 100% RTP and the candidate is directed to perform OST-OlO, Power Range Calorimetric During Power Operation Daily, and to adjust all Power Range Nis that indicate greater than +1- 0.5% of 100%. During the calorimetric the candidate will determine that NI-44 is outside of the prescribed band and adjust Nl-44 from 101% to 100%. (New Admin JPM)

ILC-13 NRC JPM Admin RO A2 Perform the monthly RVLIS Channel Check lAW OST-054.

G2.2.12 Knowledge of Surveillance Procedures The plant is at 100% RTP and the candidate is directed to perform OST-054, Section 8 1, RVLIS Channel Check During performance of the OST the candidate will identify that the deviation between RVLIS Channel I and Channel II exceed the allowed 1 deviation of 12% and will determine that the OST is UNSAT. (Bank Admin JPM)

ILC-13 NRC JPM Admin RO A3 Calculate Low Dose Path G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 I 43.4 / 45.10)

The candidate will be given a set of conditions and directed to determine the most efficient method of performing a job to receive the lowest dose for work in an RCA. The applicant will be given 2 possible paths to get to a work site and the option of using 1 or 2 workers. The candidates are also given the current annual dose of the two workers assigned to perform the work and have to determine if any dose limits will be exceeded.

This JPM will be performed by both RO and SRO candidates. (Modified Admin JPM)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: H B Robinson Date of Examination: 7/29/13 Examination Level: RO SRO X Operating Test Number: ILC-13 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations M, R Determine Power Distribution Flux Limits Conduct of Operations M, R Review a set of Hot Ops Log Review of Completed Surveillance Procedure / I i..

Equipment Control N R (OST-151-4, Comprehensive Flow Test For Safety Injection Pump A)

Radiation Control M, R Calculate Low Dose Path Perform an Emergency Action Level Emergency Classification and Recommended Protective Procedures/Plan R Actions 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)

ILC-I3 NRC SRO Admin JPM Summary ILC-13 NRC JPM Admin SRO Al-I Determine Power Distribution Flux Limits G2.1 .7 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)

The plant is at 70% RTP with a Xenon transient in progress. The program that calculates penalty points is inoperable. The candidate will be provided the 100% Target Value and the Target Band range along with seven sets of Power Data and individual Power Range NI AFD readings over a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period. The candidate will be directed to manually calculate the Penalty Points in accordance with FMP-009, Power Distribution Control. Candidate will also determine if any ITS Surveillance requirements and LCOs are applicable. Candidate will determine that the ITS 3.2.3, Condition C limit of 60 penalty points was exceeded at time 1430 and that ITS 3.2.3 Condition D was met at 1500 due to power not being reduced below 50% RTP within 30 minutes. Candidate also determines that SR 3.2.3.2 is required due to the AFD monitor being out of service.

(Modified Admin JPM)

ILC-13 NRC JPM Admin SRO Al-2 Review a set of Hot Ops Logs G2.1 .25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

G2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (CFR: 41.10 /45.12 /45.13)

The candidate will be given a set of Hot Ops Logs to review following the 1600 readings. The candidate will be directed to review the logs in accordance with 0MM-01-011, Logkeeping, and OPS-NGGC-1 000, Fleet Conduct of Operations. Candidate will identify that B SI Accumulators recorded level is high out of specification and request additional information. A cue will be given that will prompt the candidate that ITS SR 3.5.1.4 be performed to sample the accumulator for proper boron concentration.

Candidate will also identify that A Boric Acid Storage Tank is low out of specification and determine that adequate volume exists between A and B BASTs to meet the requirements of TRM 3.6. Lastly the candidate will identify that the Primary Water Storage Tank is low out of specification per the logs. The candidate will review the station curve book and determine that adequate volume is available to meet the requirements of TRM 3.6. (Modified Admin JPM)

ILC-13 NRC JPM Admin SRO A2 Review of Completed Surveillance Procedure (OST-151-4, Comprehensive Flow Test For Safety Injection Pump A)

G2.2.12 Knowledge of surveillance procedures. (CFR: 41.10 /45.13)

The candidate will be directed to perform a review of a completed OST-151-4 prior to 1J Shift Managers approval. The candidate will identify a missing initial from a step and failure to circle SAT for performance of a section of the procedure Candidate will identify that the differential pressure recorded on the data table is different that the differential pressure calculated from the field data Candidate will identify that one of pump vibration readings was incorrectly labeled as in the Acceptable range when it 0 should have been marked as in the Alert range. Candidate will note that position verification of a tested valve was marked as UNSAT due to not receiving the proper ERFIS indication. Candidate will review the associated note in the comments section and determine that the valve has been erroneously declared OOS due to the failed ERFIS reading. (New Admin JPM)

ILC-13 NRC JPM Admin SRO A3 Calculate Low Dose Path G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 /43.4 /45.10)

The candidate will be given a set of conditions and directed to determine the most efficient method of performing a job to receive the lowest dose for work in an RCA. The applicant will be given 2 possible paths to get to a work site and the option of using 1 or 2 workers. The candidates are also given the current annual dose of the two workers assigned to perform the work and have to determine if any dose limits will be exceeded.

This JPM will be performed by both RO and SRO candidates. (Modified Admin JPM)

ILC-13 NRC JPM Admin SRO A4 Perform an Emergency Action Level Classification and Recommended Protective Actions.

G2.4.41 Knowledge of the emergency action level thresholds and classifications.

(CFR: 41.10 /43.5 /45.11)

G2 4 44 Knowledge of emergency plan protective action recommendations (CFR 4110/435/453/4512)

The candidate will be given the necessary plant conditions to classify that an emergency event has occurred This classification is time critical and is required to be determined within 15 minutes of the onset of the event Once the classification is communicated to the examiner, the candidate will directed to determine the Protective Action Recommendations based on the event and meteorological data (New Admin JPM)

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: H B Robinson Date of Examination: 7/29/13 Exam Level: RO X SRO-I X SRO-U Operating Test No.: ILC-13 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. 004 CVCS / Establishing RCS Cold Shutdown Boron L N S 1 Concentration

b. 010 PZR PCS / Place LTOP in Service L, N, S 3 A, EN, L, M,

c. 002 RCS I Establish RCS Bleed and Feed

d. 039 MRSS I Reactor Trip Response Excessive RCS A, D, L, S 4S Cooldown

e. 103 Containment I Verify Phase B Containment Isolation A, EN, L, M, and CV Spray Alignment P, S

f. 062 AC Elect. / Operation with High Switchyard Voltage A, N, S 6

g. 008 CCW I Respond to a Loss of CCW D, S 8

h. 006 ECCS I Fill a Safety Injection Accumulator lAW OP-202 D EN 2 (ROOnly)

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

i. 004 CVCS / Auxiliary Building Operator Actions lAW DSP- A E L M R 2 002,Att.3 , ,

j. 061 AFW I Aligning SW Backup to SDAFW Pump Suction A, D, E, L, R 4S lAW DSP-007, Attachment 7

k. 064 EDG I Align Backup Fuel Oil to the B EDG lAW EPP- D, E, L, R 6 28, Att. 5

@ All RD and SRD-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 RD I SRO-l I SRO-U

(A)ltern ate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrombank <_9181<_4 (E)mergency or abnormal in-plant I I I I 1 (EN)gineered safety feature - I - I 1 (control room system)

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

(R)CA >_lIlI>_l (S)imulator JPM A: Establishing RCS Cold Shutdown Boron Concentration.

K/A 004 A4.18 Ability to manually operate and/or monitor in the control room:

Emergency borate valve (CFR 41.7, 45.5 to 45.8)

(004 CVCS) Candidate will assume the watch with the plant in Mode 3 following a Rapid Plant Shutdown due to a 20 gpm leak on A S/G. The candidate will be directed to add 700 gallons of boric acid to the RCS in accordance with AOP-035, Att. 3, Establishing RCS Cold Shutdown Boron Concentration. This procedure will have the candidate use MOV-350, BA TO CHARGING PMP SUCT, as the boration flowpath. Candidate will have to utilize Boric Acid Flowrate information and calculate how long the addition must be in service to add the desired amount of boric acid MOV-350 will be closed after the desired amount of boric acid has been added based on calculated time. (New CR JPM)

JPM B: Place LTOP in Service K/A 010 A4.03 Ability to manually operate and/or monitor in the control room: PORV and Block Valves (CFR: 41.7 / 45.5 to 45.8)

(010 PZR PCS) Candidate will assume the watch as Operator at Controls with a cooldown to Cold Shutdown in progress. With RCS temperature between 350° F and 360° F the candidate will adjust PC-444J, PZR PRESS MASTER CONTROLLER, OR PZR Spray Valves in manual to lower RCS pressure to between 350 and 375 psig.

Candidate will the proceed through a series of plant condition verification steps and then ultimately place both PZR PORVs Overpressure Selector Switches to the LOW PRESSURE position. This evolution will be performed in accordance with GP-007, Plant Cooldown from Hot Shutdown to Cold Shutdown, Step 8.3.10. (New CR JPM)

JPM C: Establish RCS Bleed and Feed K/A 002 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of heat sinks. (CFR: 41.5 I 43.5 I 45.3 / 45.5)

(002 RCS) The plant has experienced a loss of all feedwater along with failure of the reactor to be tripped from the control room. Upon exiting FRP-S.1, the crew has identified a RED terminus on the Heat Sink CSF and transitioned to FRP-H.1, Response to Loss of Secondary Heat Sink. The candidate will be directed to respond to the loss of secondary heat sink in accordance with FRP-H.1. The candidate will determine that RCS Bleed and Feed criteria have been met and take the necessary actions. During the implementation of RCS Bleed and Feed the candidate will determine that PZR PORV PCV-455C has failed at mid-position. The candidate will take alternative actions to open all RCS and PZR Vent Valves in an attempt to provide an adequate bleed path. (CR-075 Bank JPM Modified for Alternate Path)

JPM D: Reactor Trip Response Excessive RCS Cooldown K/A 007 EAI .03 / EAI .10 Ability to operate and monitor the following as they apply to a reactor trip: RCS pressure and temperature I S/G Pressure (CFR: 41.7 / 45.5 /45.6)

(039 MRSS) The plant was manually tripped due to a loss of both Main Feed Pumps.

The CRS has directed the candidate to stabilize the plant lAW EOP-ES-0.1. Candidate will identify that RCS Temperature is continuing to lower with all S/G PORVs and Steam Dumps closed and takes action to close the MSIVs. (Alternate Path) Based on a continuous action step the candidate will identify that RCS temperature is now rising and takes action to control RCS temperature by manually controlling the S/G PORV5 and stabilizes RCS temperature at approximately 547°F. (CR-084 Bank JPM)

JPM E: Verify Phase B Containment Isolation and CV Spray Alignment K/A 026 A4.01 Ability to manually operate and/or monitor in the control room: CSS Controls (CFR: 41.7 /45.5 to 45.8)

K/A 103 A3.01 Ability to monitor automatic operation of the containment system, including: Containment Isolation (CFR: 41 .7 / 45.5)

(103 Containment) The plant has tripped due to a Large Break LOCA. EOP-E-0 has been implemented up to Step 9. a. CV pressure HAS REMAINED LESS THAN 10 PISG. The candidate has been directed to perform the RNO actions for this step due to CV being greater than 10 psig. Candidate will determine that none of the CV Spray Pump Discharge Valves (Sl-880s) are open and take manual actions to open them from the RTGB controls. The candidate will then determine that none of the Phase B valves are in the proper position and take manual action to close all the valves and then secure the RCPs. (CR-098 Bank JPM Modified for Alternate Paths)

JPM F: Operation with High Switchyard Voltage K/A 062 A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the AC distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequences of exceeding voltage limitations (CFR: 41.5 / 43.5 / 45.3 /

45.13)

(062 AC Dist.) The plant is in Mode I and Grid voltage has risen to the point that E-2 voltage is greater than 505 Volts. AOP-031, Operation with High Switchyard Voltage, has been performed up to step 21. The candidate will continue in AOP-031 and start loads on E-2 in an attempt to lower voltage and ultimately transfer 4Kv Bus 4 to the Start-Up Transformer. During the transfer, breaker 52/20 will fail to Auto-Open and require the candidate to perform an alternate path by manually opening breaker 52/20.

(New CR JPM)

JPM G: Respond to a Loss of CCW lAW AOP-014 K/A 008 A3.01 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: RCP (CFR: 41.5 / 45.5)

(007 PRT) Candidate will assume the watch with the plant at 100% RTP and told to respond to plant alarms. The candidate will receive a CCW Surge Tank HI/LO Level alarm and determine that the CCW Surge Tank is lowering rapidly. Candidate will take actions lAW AOP-014, CCW System Malfunction, and trip the reactor and trip all RCP5.

Candidate will then lockout all CCW Pumps to prevent Auto-Start on Low System Pressure and ultimately determine that the leak is in the CV and Isolate CCW to the RCPs. (CR-066 Bank JPM)

JPM H: Fill a Safety Injection Accumulator lAW OP-202 (RO Only)

K/A 006 Al .13 Ability to predict and / or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including:

Accumulator pressure (level, boron concentration) (CFR 41.5 / 45.5)

(006 ECCS): Fill a Safety Injection Accumulator lAW OP-202. The candidate assumes the watch with a SI Accumulator Low level alarm with direction to fill the Accumulator lAW OP-202, SAFETY INJECTION AND CONTAINMENT VESSEL SPRAY SYSTEM, Section 8.2.1, to reset the low level alarm. The applicant will align ECCS valves and start a Safety Injection Pump to raise level above 69%, while maintaining pressure within band. (CR-019 Bank JPM) (RO ONLY)

JPM I: Auxiliary Building Operator Actions lAW DSP-002, Aft. 3 K/A 004 G2.1 .30 Ability to locate and operate components, including local controls with respect to CVCS. (CFR: 41.7 / 45.7)

(004 CVCS) The plant has been tripped and control room evacuated due to a fire on the RTGB. DSP-002, Hot Shutdown Using the Dedicated /Alternate Shutdown System, is being implemented. The candidate has been assigned to perform DSP-002, , Auxiliary Building Operator Actions, and directed to inform the SM when a Charging Pump is running at minimum speed and adequate seal injection flow is being supplied to the RCPs. The candidate will enter the Charging Pump Room and take local control of A Charging Pump, properly align a discharge and suction path, and then manually start A Charging Pump and adjust Charging Pump Speed. The candidate then manually throttles open the RCP Seal Water Flow Control Valves to raise seal injection flow to within the expected band. This JPM requires RCA entry. (IP 145 Bank JPM Modified)

JPM J: Aligning SW Backup to SDAFW Pump Suction lAW DSP-007, Att. 7 K/A 061 K4.01 Knowledge of AFW design feature(s) and/or interlock(s) which provide for the following: Water sources and priority of use. (CFR: 41.7)

(061 AFW) The plant has been shutdown and is preparing to cool down lAW DSP-007, Cold Shutdown Using the Dedicated /Alternate Shutdown System. The CRS has directed the candidate perform DSP-007, Att. 7 to align Service Water to the suction of the SDAFW pump. When Service Water is aligned the candidate is to start the SDAFW pump by manually opening the steam supply from C S/G (V1-8C). The candidate will determine that V1-8C is stuck in the closed position and have to open an alternate steam supply valve. This JPM has actions both inside and outside of the RCA. (IP-165 Bank JPM)

JPM K: Align Backup Fuel Oil to the B EDG lAW EDG lAW EPP-28, Att. 5 K/A 064 Ki .03 Knowledge of the physical connections and / or cause-effect relationships between the ED/G system and the following systems: Diesel fuel oil supply system (CFR: 41.2 to 41.9 / 45.7 to 45.8)

(064 EDG) The plant has been shut down due to hostile action that has resulted in a loss of off-site power and a loss of Ultimate Heat Sink. EPP-028, Loss of Ultimate Heat Sink, has been implemented and B EDG is the only EDG operating. The candidate is directed to perform EPP-28, Attachment 5, Backup Fuel Oil Alignment. The candidate will enter the B EDG Room and perform manual valve operations to add fuel oil from the Alternate Fuel Oil Storage Tank and raise the EDG Fuel Oil Day Tank from % full to

% full. This JPM requires RCA entry. (IP-151 Bank JPM)