ML12297A075

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1 North Anna 2012-301 Draft Administrative Documents
ML12297A075
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 10/23/2012
From:
NRC/RGN-II
To:
Virginia Electric & Power Co (VEPCO)
References
50-338/12-301, 50-339/12-301
Download: ML12297A075 (17)
v • d • e


Text

kIRiTrE,V E  :;9ff1ft6 i, ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: North Anna Power Station Date of Examination: September 2012 Initials Item Task Description

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

AØ R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.

T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. q* iE

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

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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 last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums 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 49 P2 in the appropriate exam sections. #1 f)iv E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

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c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

E R d. Check for duplication and overlap among exam sections.

L e. Check the entire exam for balance of coverage.

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

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a. Author /CML
b. Facility Reviewer (*)
c. NRC Chief Examiner (#) E4-is / ,27ui2. /
d. NRC Supervisor SE.LWO c g -

Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines wRirrEJ Exrn? 4,n,E 9/

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ES-401 PWR Examination Outline Form ES-401-2 Facility: NORTH ANNA POWER STATION Date of Exam: SEPTEMBER 2012 Tier II Group ROK/ACajpoyPornts SRO-Only_Points K)KKKKKAAAAG A2 G* Total jJ2 3 4 5 6 1 2 3 4

  • Total 1 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 1 2 2 N/A I 1. N/A 9 2 2 4 j.

Evoluons Tier Totals 4 5 5 4 5 4 27 5 5 10 1 312333232232 28 3 2 5

2. 1 Plant 2 J4J. 111111 110 10 0 2 1 3 Systems Tier Totals 4 44 34 33 4 2 38 5 3 8
3. Generic Knowledge and Abilities 1 2 3 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
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/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 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 I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D. 1 .b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
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 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO OO8AA1.02 Pressurizer Vapor Space Accident/3 4.1 3.9 HPI pump to control PZR level/pressure 009EK3.06 Small Break LOCA / 3 39 4 RCS inventory balance 011 EA2.08 Large Break LOCA / 3 34 39 Conditions necessary for recovery when accident reaches stable phase 022AK1.04 Loss of Rx Coolant Makeup / 2 2.9 3 i D Reason for changing from manual to automatic control of LI charging flow valve controller 025AA1 .04 Loss of RHR System / 4 2.8 2.6 Closed cooling water pumps 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 Controllers and positioners Malfunction / 3 029EK2.06 ATWS / 1 2.9 3.1 Breakers, relays, and disconnects.

038EK1 .02 Steam Gen. Tube Rupture / 3 3.2 3.5 Leak rate vs. pressure drop LI LI LI LI LI LI LI LI LI LI 040AG2.4.20 Steam Line Rupture - Excessive Heat 3.8 4.3 Knowledge of operational implications of EOP warnings, Transfer / 4 LI LI LI LI LI LI LI LI LI LI cautions and notes.

054AK3.04 Loss of Main Feedwater / 4 4.4 4.6 Actions contained in EOPs for loss of MFW LI LI LI LI LI LI LI LI LI LI 055EA2.03 Station Blackout / 6 3.9 4.7 Actions necessary to restore power LI LI LI LI LI LI LI LI LI LI Page 1 of 2 1/6/2012 8:55AM

ES-401, REV 9 TIGI 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 056AA2.73 Loss of Off-site Power /6 3.5 3.6 PZR heater on/off 057AG2. 1.31 Loss of Vital AC Inst. Bus /6 4.6 43 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

058AK3.01 Loss of DC Power / 6 3.4 3.7 Use of dc control power by D/Gs 077AK1 .01 Generator Voltage and Electric Grid 3.3 3.5 Definition of the terms: volts, watts, amps, VARS, power Disturbances / 6 factor WE04EA1 .1 LOCA Outside Containment / 3 4.0 4.0 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEO5EK2.2 -

Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary Secondary Heat Sink / 4 D coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

well EG2.4.6 Loss of Emergency Coolant Recirc. / 4 3.7 4.7 Knowledge symptom based EOP mitigation strategies.

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ES-401, REV 9 TIG2 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 OO1AA2.04 Continuous Rod Withdrawal / 1 4.2 4.3 Reactor power and its trend 028AK3.04 Pressurizer Level Malfunction /2 2.9 3 Change in PZR level with power change, even though RCS T-ave. constant, due to loop size difference 060AA1 .01 Accidental Gaseous Radwaste Rel. / 9 2.8 3 Area radiation monitors 067AA2.10 Plant Fire On-site / 8 2.9 3.6 Time limit of long-term-breathing air system for control room 068AK2.07 Control Room Evac. /8 3.3 3.4 ED/G 076AG2.2.3 High Reactor Coolant Activity / 9 3.8 3.9 (multi-unit license) Knowledge of the design, procedural and operational differences between units.

WEO8EK1 .3 RCS Overcooling PTS / 4 3.5 4.0 Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Operations).

WE1OEK2.2 Natural Circ. With Seam Void/4 3.6 3.9 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.

WE15EK3.1 Containment Flooding / 5 2.7 2.9 Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.

Page 1 of 1 1/6/2012 8:55AM

ES-401, REV 9 T2GI 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 003A4.06 Reactor Coolant Pump 2.9 2.9 RCP parameters 003K5.04 Reactor Coolant Pump 3.2 3.5 Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow and feed flow 004K2.07 Chemical and Volume Control 2.7 3.2 Heat tracing 004K5. 15 Chemical and Volume Control 3.3 3.5 Boron and control rod reactivity effects as they relate to MTC 005A2.03 Residual Heat Removal 2.9 3.1 RHR pump/motor malfunction 005K5.05 Residual Heat Removal 2.7 3.1 Plant response during solid plant: pressure change due to the relative incompressibility of water 006A3.03 EmergencyCoreCooling 4.1 4.1 ESFAS-operatedvalves 006A4.08 Emergency Core Cooling 4.2 4.3 LI LI LI LI LI ] LI ESF system, including reset 007A3.Ol Pressurizer Relief/Quench Tank 2.7 2.9 LI LI LI LI LI LI LI LI LI LI Components which discharge to the PRT 008G2.1 .27 Component Cooling Water 3.9 4 LI LI LI LI LI LI LI LI LI LI Knowledge of system purpose and or function.

010K2.02 PressurizerPressureControl 2.5 2.7 LI LI LI LI LI LI LI LI LI LI ControllerforPZRsprayvalve Page 1 of 3 1/6/2012 8:55AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 01 2A1 .01 Reactor Protection 2.9 3.4 Trip setpoint adjustment U

013K6.0l Engineered Safety Features Actuation 2.7 3.1 Sensors and detectors U U UJ U U 022G2.1.7 ContainmentCooling 4.4 4.7 Abilitytoevaluateplantperformanceandmakeoperational judgments based on operating characteristics, reactor behavior and instrument interpretation.

026K4.09 Containment Spray 3.7 4.1 Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover) 039A2.0l Main and Reheat Steam 3.1 3.2 Flow paths of steam during a LOCA 059K1.02 Main Feedwater 3.4 3.4 AFW system U U 061K6.01 Auxiliary/Emergency Feedwater 2.5 2.8 Controllers and positioners U U U U U U U U U U 062K1.02 AC Electrical Distribution 4.1 4.4 ED/G U U U U U U U U U U 063A4.01 DC Electrical Distribution 2.8 3.1 Major breakers and control power fuses U U U U U U U U U U 064A1 .03 Emergency Diesel Generator 3.2 3.3 Operating voltages, currents and temperatures U U U U U U U U U H 064K4.01 Emergency Diesel Generator 3.8 4.1 Trips while loading the ED/G (frequency, voltage, speed)

H H H H H U H H H H Page2of3 1/6/2012 8:55AM

ES -401, REV 9 T2GI 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 073K3.01 Process Radiation Monitoring 3.6 4.2 Radioactive effluent releases 073K4.01 Process Radiation Monitoring 4.0 4.3 Release termination when radiation exceeds setpoint Li DL1E1DL1 076A1 .02 Service Water 2.6 2.6 Reactor and turbine building closed cooling water LLLLH1L1 temperatures.

076K3.0l Service Water 3.4 3.6 Closed cooling water 078K1.05 lnstrumentAir 3.4 3.5 MSIV air 103K3.02 Containment 3.8 4.2 Loss of containment integrity under normal operations Page 3 of 3 1/6/2012 8:55AM

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 002A4.08 Reactor Coolant 3.4 3.7 Safety parameter display systems 011A2.08 Pressurizer Level Control 2.6 2.8 Loss of level compensation 0141(1.02 Rod Position Indication 3.0 3.3 NIS 017K6.0l In-core Temperature Monitor 2.7 3.0 Sensors and detectors 027K2.01 Containment Iodine Removal 3.1 3.4 Fans L LI LI LI 029A3.0l Containment Purge 3.8 4.0 CPS isolation 035A1.02 Steam Generator 3.5 3.8 SIG pressure LI 045K5.17 Main Turbine Generator 2.5 2.7 Relationship between moderator temperature coefficient and boron concentration in RCS as T/G load increases 0551(3.01 Condenser Air Removal 2.5 2.7 j Main condenser LI LI LI LI LI LI LI LI LI LI 0681(4.01 Liquid Radwaste 3.4 4.1 Safety and environmental precautions for handling hot, LI LI LI LI LI LI LI LI LI LI acidic and radioactive liquids Page 1 of 1 1/6/2012 8:55AM

ES-401, REV 9 T3 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:

RD SRO G2.l .26 Conduct of operations 3.4 3.6 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

G2.l.40 Conduct of operations 2.8 3.9 Knowledge of refueling administrative requirements G2.2.12 Equipment Control 3.7 4.1 D Knowledge of surveillance procedures.

G2.2.43 Equipment Control 3.0 3.3 Knowledge of the process used to track inoperable alarms G2.3.13 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 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 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.23 Emergency Procedures/Plans 3.4 4.4 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

G2.4.29 Emergency Procedures/Plans 3.1 4.4 Knowledge of the emergency plan.

G2.4.43 Emergency Procedures/Plans 3.2 3.8 Knowledge of emergency communications systems and techniques.

Page 1 of 1 1/6/2012 8:55AM

ES-401, REV 9 SRO TIGI 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 008AG2.4.6 Pressurizer Vapor Space Accident / 3 L1L1L1E1.L Knowledge symptom based EOP mitigation strategies.

025AA2.02 Loss of RHR System / 4 3.4 3.8 Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere 056AG2.2.40 Loss of Off-site Power /6 Ability to apply technical specifications for a system.

065AA2.02 Loss of Instrument Air / 8 2.4 2.6 Relationship of flow readings to system operation weO4EG2.4.18 LOCA Outside Containment /3 3.3 4.0 Knowledge of the specific bases for EQ Ps.

WEO5EA2.l -

Inadequate Heat Transfer Loss of 3.4 4.4 Facility conditions and selection of appropriate procedures Secondary Heat Sink / 4 during abnormal and emergency operations.

Page 1 of 1 1/6/2012 8:55AM

ES-401, REV 9 SRO TIG2 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 OO1AA2.04 Continuous Rod Withdrawal / 1 4.2 4.3 Reactor power and its trend 060AG2.l.19 Accidental Gaseous Radwaste Rel. / 9 3.9 3.8 Ability to use plant computer to evaluate system or component status.

061AA2.05 ARM System Alarms / 7 3.5 4.2 Need for area evacuation; check against existing limits 069AG2.l.31 Loss of CTMT Integrity/5 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Page 1 of 1 1/6/2012 8:55AM

ES-401, REV 9 SRO T2GI 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 SRQ 012A2.Ol Reactor Protection 3.1 3.6 Faulty bistable operation 039A2.03 Main and Reheat Steam 3.4 3.7 Indications and alarms for main steam and area radiation monitors (during SGTR) 062A2.15 AC Electrical Distribution 2.8 3.2 Consequence of paralleling out-of-phase/mismatch in volts 063G2.4.9 DC Electrical Distribution 3.8 4.2 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

103G2.4.31 Containment 4.2 4.1 D DDE ED D ED E1 Knowledge of annunciators alarms, indications or response procedures Page 1 of 1 1/6/2012 8:55AM

ES-401, REV 9 SRO 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 028G2.l.25 Hydrogen Recombiner and Purge 3.9 4.2 Ability to interpret reference materials such as graphs, Control monographs and tables which contain performance data.

071A2.Ol Waste Gas Disposal 2.3 2.8 Use of WGDS to prevent entry of oxygen into holdup tanks during liquid transfers 079A2.Ol Station Air 2.9 3.2 Cross-connection with lAS Page 1 of 1 1/6/2012 8:55 AM

ES-401, REV 9 SRO 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.15 Conduct of operations 2.7 3.4 Knowledge of administrative requirements for temporary El management directives such as standing orders, night orders, Operations memos, etc.

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

G2.2.7 Equipment Control 2.9 3.6 LI El El El El El El El LI El Knowledge of the process for conducting special or infrequent tests G2.3.15 Radiation Control 2.9 3.1 Knowledge of radiation monitoring systems El LI LI LI LI LI LI LI LI LI G2.3.5 Radiation Control 2.9 2.9 LI LI LI LI LI LI El LI LI LI Ability to use radiation monitoring systems G2.4.25 Emergency Procedures/Plans 3.3 3.7 LI El LI LI LI LI LI LI LI LI Knowledge of fire protection procedures.

G2.4.30 Emergency Procedures/Plans 2.7 4.1 LI LI LI El LI LI LI LI LI LI Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Page 1 of 1 1)6/2012 8:55AM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: North Anna Power Station Date of Examination: 9/1012012 Examination Level: Combined (See Below) Operating Test Number:

1 Administrative Topic (see Note)

Conduct of Operations j

Type Codes M, R J Describe activity to be performed Determine Shutdown Margin (1-PT-i 0.1).

G2.1 .25 (ALL) (RO 3.9 I SRO 4.2)

Conduct of Operations M, R Calculate Reactor Coolant System Leak Rate (Hand G2.1.20 Calculation) (1-PT-52.2).

(ALL) (RO 4.6 1 SRO 4.6)

Equipment Control M, R Perform Alternate Core Cooling Assessment G2.237 (1-GOP-13.O & 1-GOP-13,1)

(ALL) (RO 3.6 I SRO 4.6)

Radiation Control M, R Select RWP Task; determine dressout & dosimetry G2.3.7 requirements, and calculate stay time.

(ALL) (RO 3.5 I SRO 3.6)

Emergency Plan M, R Classify an emergency event (EPIP-1 .01)

G2.4.41 (SRO ONLY) (RO 2.9! SRO 4.6)

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)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: North Anna Power Station Date of Examination: 9/1012012 Exam Level: RO SRO-l SRO-U Q Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System I .JPM Title (KA) Type Code*

Function a) Initiate Bleed & Feed in Response to Loss of Secondary Heat Sink (1-FR-Hi) A, EN, L, M, S 4 (Pri)

E05 EAI.1, (4.1 I 4.0) I (ALL) b) Align Service Water to Cool Charging Pumps with Gravity Flow (0-AP-12) L, N, S 4 (Sec) 076 A2.01,_(3.5/_3.7)!_(ALL) c) Perform Attachments 4 and 5 of I -E-0, Reactor Trip or Safety Injection A, EN, L, M, S 2 013-A4.01, (4.5/4.8)_(ALL) d) Defeat a failed loop iTITave channel in accordance with 1-MOP-55.74 M, S 7 016A4.01, (2.9/2.8)_(ALL) e) Terminate spurious SI in accordance with 1-AP-0.1 A, EN, L, N, S 3 006- A2.13 (3.9/4.2) (ALL) f) Place Containment Purge in Service D, L, S 8 029 A4.01 (2.5 I 2.5)_(ALL) g) Perform an RCS Dilution A, M, S 1 004 (3.9 / 3.7)_(RO_ONLY) h) Start and load an Emergency Diesel Generator A, D, S 6 062 A4.07 (3.1 13.1) (ALL) in-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)

I) Locally reset trip switches on breakers in accordance with 1-AP-20, Attachment 2 E, N 6 062 K2.01, (3.3! 3.4) (ALL) j) Align Auxiliary Feedwater to Supply the HCV Header 0, E, P 4 (sec) 061 A2.04 (3.4 I 3.8) (ALL) k) Emergency Borate the RCS Locally D, E, R 024 AA2.05 (3.3 I 3.9) (ALL)

@ All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-LJ systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO I SRO-l I SRO-U (A)Iternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank < 9 1 < 8 1 4 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature

- I - / 1 (control room system)

(L)ow-Power I Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1 (A)

> 2 1 2 I 1 (P)revious 2 exams (similar topic) 3 I . 3 I 2 (randomly selected)

(R)CA i ,i /1 (S)imulator Note: There are NO SRO-U candidates for this exam.

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