ML16088A394

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301 Section 1
ML16088A394
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/22/2016
From:
NRC/RGN-II
To:
Virginia Electric & Power Co (VEPCO)
References
Download: ML16088A394 (24)
v • d • e


Text

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£x4M fA/v ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

5_jR Date of Examination:

TuL1 c.//

Initials Item Task Description

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

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. (17 T

T E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. (/9
d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. M i4 N
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

/ (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 in the appropriate exam sections. 2)7 it E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 7
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 7 R Check for duplication and overlap among exam sections. 41:4
d. 1 L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)

If

c. NRC Chief Examiner (#) 1I4 - .4ArRt
d. NRC Supervisor ,tAL4Ot4 i WlPLLMJ1/

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

Not applicable for NRC-prepared examination outlines

- WR/77EA) &4m

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

Tier Group JI RO K/A Category Points SRO-Only Points FKKKKKAAAAG[ A2 G* JTotal

  • jTotal 11234561234 L___
1. J i 3 3f3 33 3 18 3 3 6 Emergency &

Abnormal Plant

[

[

2 II N/A 1

N/A 9 2 2 4 Evolutions LTie1Tota1s 5 1 4 4 5 27 5 5 10 1 32 2 3332 3322 28 3 2 5

  • 2 11111110111 10 2 3 piant Systems Tier Totals 4 3 3 4 4 4 3 3 4 3 3 38 if 4 8
3. GenericKnowledgeandAbilities Categories

] 1 2 3 4 10 1 2 3 4 7 3 2 2 3 2 2 2 1

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 PTier 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 4 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. Systemslevolutions 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 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 I and 2 from the shaded systems and KIA 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 0.1 .b of ES-401 for the applicable KAs.
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 KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43..

ES-401, REV 9 TIGI 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 007EK1 .02 Reactor Trip Stabilization Recovery 3.4 3.8 H H H H H H H H H H Shutdown margin

/1 008AA1 .06 Pressurizer Vapor Space Accident / 3 3.6 3.6 Control of PZR level 009EK3.05 Small Break LOCA / 3 3.4 3.8 CCWS radiation alarm 011 EA2.l 0 Large Break LOCA /3 4.5 4.7 Verification of adequate core cooling 015AK3.0l RCP Malfunctions /4 2.5 3.1 LI Potential damage from high winding and/or bearing temperatures 022AK1 03 Loss of Rx Coolant Makeup / 2 3 3.4 H H Relationship between charging flow and PZR level 025AA1 .11 Loss of RHR System / 4 2.9 3 H H H H H H H H H H Reactor building sump level indicators 026AA2.01 Loss of Component Cooling Water / 8 2.9 3.5 H H H H H H H H H H Location of a leak in the CCWS 029EK2.06 ATWS / 1 2.9 3.1 H H H H H H H H H H Breakers, relays, and disconnects.

040AG2.2.3 Steam Line Rupture - Excessive Heat 3.8 3.9 LI H H H H H H H H H (multi-unit license) Knowledge of the design, procedural Transfer / 4 and operational differences between units.

054AK3.01 Loss of Main Feedwater / 4 4.1 4.4 H H H H H H H H H H Reactor and/or turbine trip, manua( and automatic Page 1 of 2 10/04/2013 9:30AM

ES-401, REV 9 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 056AA2.54 Loss of Off-site Power/6 2.9 3 Breaker position (remote and local)

ElElEl 062AA1.01 Loss ofNuclearSvcWater/4 3.1 3.1 Nuclear service water temperature indications ElElElEl 065AG2.l.32 LossoflnstrumentAir/8 3.8 4.0 Ability to explain and apply all system limits and El El El El El El ElElEI precautions.

077AK2.01 Generator Voltage and Electric Grid 3.1 3.2 Motors Disturbances I 6

[] El El El El El ElElElEl weO4EG2.4.3 LOCA Outside Containment / Ability to identify post-accident instrumentation.

El El El El El El El EJElE WE05EK2.2 Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary Secondary Heat Sink / 4 El El El El El El ElElElEl coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 1 EK1 .3 Loss of Emergency Coolant Recirc. / 4 3.6 4.0 Annunciators and conditions indicating signals, and El remedial actions associated with the (Loss of Emergency Coolant Recir).

Page 2 of 2 10/04/2013 9:30AM

ES-401, REV 9 TIG2 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 OO1AG2.1 .20 Continuous Rod Withdrawal I 1 4.6 4.6 H H H H H H H H H Ability to execute procedure steps.

036AA1.04 Fuel Handling Accident/8 3.1 3.7 Fuel handling equipment during an incident 037AK3.06 Steam Generator Tube Leak) 3 3.6 4.1 H H H H H H H H H H Normal operating precautions to preclude or minimize SGTR 051AA2.02 Loss of Condenser Vacuuml4 3.9 4.1 Conditions requiring reactorand/orturbine trip 059AK1.0l Accidental Liquid RadWaste Rel. / 9 2.7 3.1 Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 074EG2.4.21 mad. Core Cooling /4 4.0 4.6 H H H H H H H H H H Knowledge of the parameters and logic used to assess the status of safety functions WEO3EK2.1 LOCA Cooldown Depress. /4 3.6 4.0 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE14EK2.l Loss of CTMT Integrity / 5 3.4 3.7 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEI 5EK1 .2 Containment Flooding /5 2.7 2.9 H H H H H H H H H H Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

Page 1 of 1 10/04/2013 9:30AM

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 003G2.4.50 Reactor Coolant Pump 4.2 4.0 Ability to verify system alarm setpoints and operate controls Li J identified in the alarm response manual.

004A2.26 Chemical and Volume Control 2.8 3.0 Low VCT pressure LI 0041(5.06 Chemical and Volume Control 3.0 3.3 Concept of boron worth or inverse boron worth Li [] Li fl (reactivity, pcmlppm) 005K5.09 Residual Heat Removal 3.2 3.4 Dilution and boration considerations 006K4.ll EmergencyCoreCooling 3.9 4.2 ResetofSlS Li LI 007A1 .02 Pressurizer Relief/Quench Tank 2.7 2.9 j Maintaining quench tank pressure J

007K5.02 Pressurizer Relief/Quench Tank 3.1 34 Method of forming a steam bubble in the PZR Li Li Li Li IJ Li Li Li Li Li Li 008K3.03 Component Cooling Water 4.1 4.2 RCP Li Li Li Li Li Li Li Li Li [1 O1OK1.06 PressurizerPressureControl 2.9 3.1 CVCS Li Li Li Li Li Li Li Li Li 0101(4.01 PressurizerPressureControl 2.7 2.9 Sprayvalvewarm-up Li Li Li Li Li Li Li Li Li Li 012K6.ll Reactor Protection 2.9 2.9 Trip setpoint calculators Li Li Li LI Li []

Page 1 of 3 10/04/2013 9:30AM

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

RO SRO 01 3K2.0l Engineered Safety Features Actuation 3.6 3.8 LI ESFAS/safeguards equipment control LI LI LI LI LI LI C] C] LI 013K6.0l Engineered Safety Features Actuation 2.7 3.1 C] C] C] Sensors and detectors C] C] C]

022A3.01 Containment Cooling 4.1 4.3 Initiation of safeguards mode of operation C] LI LI LI LI LI LI LI LI LI 026A4.05 Containment Spray 3.5 3.5 Containment spray reset switches LI LI LI LI LI LI LI LI LI LI 026K4.09 Containment Spray 3.7 4.1 Prevention of path for escape of radioactivity from LI LI LI LI LI LI LI LI LI LI containment to the outside (interlock on RWST isolation after swapover) 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS LI LI LI C] LI LI LI LI LI LI 059K3.03 Main Feedwater 3.5 3.7. S/GS LI LI ] LI LI LI LI LI LI LI LI 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps LI C] LI LI LI LI LI LI LI LI 062A1 .01 AC Electrical Distribution 3.4 3.8 Significance of DIG load limits LI LI LI LI LI LI ] LI LI LI LI 063G2.1 .31 DC Electrical Distribution 4.6 4.3 Ability to locate control room switches, controls and LI C] LI LI LI LI LI LI LI LI indications and to determine that they are correctly reflecting the desired plant lineup.

063K1.03 DC Electrical Distribution 2.9 3.5 Battery charger and battery LI LI LI LI LI LI LI LI LI C]

Page 2 of 3 10/04/2013 9:30 AM

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 064K1 .03 Emergency Diesel Generator 3.6 4.0 Diesel fuel oil supply system LI 073A2.02 Process Radiation Monitoring 2.7 3.2 Detector failure LI LI LI LI LI LI LI LI LI LI 076K2.08 Service Water 3.1 3.3 ESF-actuated MOVs LI LI LI LI LI LI LI LI LI LI 078A4.01 InstrumentAir 3.1 3.1 Pressure gauges LI LI LI LI LI LI LI LI LI ] LI 103A2.04 Containment 3.5 3.6 Containment evacuation (including recognition of the alarm)

LI LI LI LI LI LI LI LI LI LI 103A3.01 Containment 3.9 4.2 Containment isolation LI LI LI LI LI LI LI LI LI LI Page 3 of 3 10/04/2013 9:30 AM

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 015A4.02 Nuclear Instrumentation 3.9 39 NIS indicators El 016K1.08 Non-nuclearlnstrumentation 3 PZRPCS El El El El El El El El El El 027K2.O1 Containment Iodine Removal 3.1 3.4 Fans 028K5.03 Hydrogen Recombiner and Purge 2.9 3.6 Sources of hydrogen within containment Control 033K3.02 Spent Fuel Pool Cooling 2.8 3.2 Area and ventilation radiation monitoring systems El 034K6.02 Fuel Handling Equipment 2.6 3.3 Radiation monitoring systems 071A3.Ol Waste Gas Disposal 2.6 2.7 HRPS El El El El El El El El El El 072G2.l.28 Area Radiation Monitoring 4.1 4.1 Knowledge of the purpose and function of major system El El El El El El El El El El components and controls.

079K4.O1 Station Air 2.9 3.2 Cross-connect with lAS El El El El El El El El El El 086A1 .01 Fire Protection 2.9 3.3 Fire header pressure El El El El El El El El El El Page 1 of 1 10/04/2013 9:30 AM

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:

RO SRO G2.l.29 Conduct of operations 4.1 4.0 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.l.40 Conduct of operations 2.8 3.9 Knowledge of refueling administrative requirements G2.1 .5 Conduct of operations 2.9 3.9 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

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

G2.2.2 Equipment Control 4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements J

during normal or abnormal conditions G2.4.1 Emergency Procedures/Plans 4.6 4.8 Knowledge of EOP entry conditions and immediate action steps.

G2.4.32 Emergency Procedures/Plans 3.6 4.0 Knowledge of operator response to loss of all annunciators.

G2.4.4 Emergency Procedures/Plans 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30 AM

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

RO SRO 009EA2.39 Small Break LOCA I 3 Adequate core cooling 022AA2.0l Loss of Rx Coolant Makeup /2 3.2 3.8 Whether charging line leak exists 027AA2.lO Pressurizer Pressure Control System 3.3 3.6 jrj PZR heater energized/de-energized condition Malfunction / 3 057AG2.1 .28 Loss of Vital AC Inst. Bus 16 4.1 4.1 Knowledge of the purpose and function of major system components and controls.

well EG2.l .32 Loss of Emergency Coolant Recirc. / 4 3.8 4.0 Ability to explain and apply all system limits and precautions.

wel2EG2.4.4 Steam Line Rupture Excessive Heat 4.5 4.7 Ability to recognize abnormal indications for system Transfer I 4 operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 1(3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 024AG2.l.23 Emergency Boration / 1 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

033AG2.2.44 Loss of Intermediate Range NI / 7 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions WEO1 EA2.l Rediagnosis / 3 3.2 4 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE16EA2.2 High Containment Radiation / 9 3.0 3.3 Adherence to appropriate procedures and operation LI LI LI LI LI LI LI LI LI LI within the limitations in the facilitys license and amendments.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO 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 004G2.2.22 Chemical and Volume Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

013A2.03 Engineered Safety Features Actuation 4.4 4.7 Rapid depressurization 059A2.0l Main Feedwater 3.4 3.6 Feedwater actuation of AFW system 061G2.4.49 Auxiliary/Emergency Feedwater 4.6 4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

078A2.01 Instrument Air 2.4 2.9 Air dryer and filter malfunctions Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T2G2 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 017G2.4.47 In-core Temperature Monitor 4.2 4.2 Ability to diagnose and recognize trends in an accurate J

and timely manner utilizing the appropriate control room reference material.

056A2.04 Condensate 2.6 2.8 Loss of condensate pumps 075G2.2.44 Circulating Water 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Page 1 of 1 10/04/2013 9:30AM

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.25 Conduct of operations 3.9 4.2 Ability to interpret reference materials such as graphs,

[

monographs and tables which contain performance data.

G2.l .32 Conduct of operations 3.8 4.0 Ability to explain and apply all system limits and precautions.

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

D L D L fl G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance D LI LI LI LI LI LI activities during shutdown operations.

G2.3.ll Radiation Control 3.8 4.3 Ability to control radiation releases G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.

Page 1 of 1 10/04/2013 9:30AM

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Surry ______________________ Date of Examination: _7/21/14______

Exam Level: SRO-I Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8 h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROI Actual Criteria Met (A)lternate path 4-6 5 YES (D)irect from bank 8 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 2 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Surry________________________ Date of Examination: _7/21/14______

Exam Level: SRO-U Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5 d.

e.

f.

g.

h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel j.
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROUI Actual Criteria Met (A)lternate path 2-3 3 YES (D)irect from bank 4 3 YES (E)mergency or abnormal in-plant 1 2 YES (EN)gineered safety feature 1 1 YES (L)ow -Power / Shutdow n 1 2 YES (N)ew or (M)odified from bank including 1(A) 1 2 YES (P)revious 2 exams (randomly selected) 2 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry_______________________ Date of Examination: _7/21/14_____

Examination Level: SRO Operating Test Number: _SR14301__

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

Quadrant Power Tilt Ratio Conduct of Operations R/D K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations S/D K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8

/ SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control R/D K/A: 2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Authorize Emergency Exposure Radiation Control R/D K/A: 2.3.4. Knowledge of radiation exposure limits under normal or emergency conditions. RO: 3.2 / SRO 3.7 Classify and Determine PAR for General Emergency Emergency Procedures/Plan R/N K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications. 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: ___Surry _____________________ Date of Examination: _7/21/14______

Exam Level: RO Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8
h. Respond to a #3 EDG Start Failure N/A/S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U RO Actual Criteria Met (A)lternate path 4-6 6 YES (D)irect from bank 9 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 3 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Surry_________________________ Date of Examination: __7/21/14_____

Examination Level: RO Operating Test Number: _SR14-301_

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

Quadrant Power Tilt Ratio Conduct of Operations R/D K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Conduct of Operations Perform a review of OPT-FW-006 Equipment Control R/D K/A: 2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Calculate Radiation Exposure when Placing Unit 1 Radiation Control Residual Heat Removal System in Service R/D K/A: 2.3.4 Know ledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Obtain Required Information IAW EPIP-2.01 Emergency Procedures/Plan S/N 2.4.39 Know ledge of RO responsibilities in emergency plan implementation. RO: 3.9 / SRO: 3.8.

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: ___Surry _____________________ Date of Examination: _7/21/14______

Exam Level: RO Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8
h. Respond to a #3 EDG Start Failure N/A/S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U RO Actual Criteria Met (A)lternate path 4-6 6 YES (D)irect from bank 9 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 3 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry_______________________ Date of Examination: _7/21/14_____

Examination Level: SRO Operating Test Number: _SR14301__

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

Quadrant Power Tilt Ratio Conduct of Operations R/D K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations S/D K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8

/ SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control R/D K/A: 2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Authorize Emergency Exposure Radiation Control R/D K/A: 2.3.4. Knowledge of radiation exposure limits under normal or emergency conditions. RO: 3.2 / SRO 3.7 Classify and Determine PAR for General Emergency Emergency Procedures/Plan R/N K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications. 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: __Surry ______________________ Date of Examination: _7/21/14______

Exam Level: SRO-I Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8 h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROI Actual Criteria Met (A)lternate path 4-6 5 YES (D)irect from bank 8 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 2 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Surry________________________ Date of Examination: _7/21/14______

Exam Level: SRO-U Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5 d.

e.

f.

g.

h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel j.
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROUI Actual Criteria Met (A)lternate path 2-3 3 YES (D)irect from bank 4 3 YES (E)mergency or abnormal in-plant 1 2 YES (EN)gineered safety feature 1 1 YES (L)ow -Power / Shutdow n 1 2 YES (N)ew or (M)odified from bank including 1(A) 1 2 YES (P)revious 2 exams (randomly selected) 2 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

£x4M fA/v ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

5_jR Date of Examination:

TuL1 c.//

Initials Item Task Description

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

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. (17 T

T E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. (/9
d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. M i4 N
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

/ (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 in the appropriate exam sections. 2)7 it E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 7
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 7 R Check for duplication and overlap among exam sections. 41:4
d. 1 L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)

If

c. NRC Chief Examiner (#) 1I4 - .4ArRt
d. NRC Supervisor ,tAL4Ot4 i WlPLLMJ1/

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

Not applicable for NRC-prepared examination outlines

- WR/77EA) &4m

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

Tier Group JI RO K/A Category Points SRO-Only Points FKKKKKAAAAG[ A2 G* JTotal

  • jTotal 11234561234 L___
1. J i 3 3f3 33 3 18 3 3 6 Emergency &

Abnormal Plant

[

[

2 II N/A 1

N/A 9 2 2 4 Evolutions LTie1Tota1s 5 1 4 4 5 27 5 5 10 1 32 2 3332 3322 28 3 2 5

  • 2 11111110111 10 2 3 piant Systems Tier Totals 4 3 3 4 4 4 3 3 4 3 3 38 if 4 8
3. GenericKnowledgeandAbilities Categories

] 1 2 3 4 10 1 2 3 4 7 3 2 2 3 2 2 2 1

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 PTier 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 4 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. Systemslevolutions 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 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 I and 2 from the shaded systems and KIA 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 0.1 .b of ES-401 for the applicable KAs.
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 KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43..

ES-401, REV 9 TIGI 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 007EK1 .02 Reactor Trip Stabilization Recovery 3.4 3.8 H H H H H H H H H H Shutdown margin

/1 008AA1 .06 Pressurizer Vapor Space Accident / 3 3.6 3.6 Control of PZR level 009EK3.05 Small Break LOCA / 3 3.4 3.8 CCWS radiation alarm 011 EA2.l 0 Large Break LOCA /3 4.5 4.7 Verification of adequate core cooling 015AK3.0l RCP Malfunctions /4 2.5 3.1 LI Potential damage from high winding and/or bearing temperatures 022AK1 03 Loss of Rx Coolant Makeup / 2 3 3.4 H H Relationship between charging flow and PZR level 025AA1 .11 Loss of RHR System / 4 2.9 3 H H H H H H H H H H Reactor building sump level indicators 026AA2.01 Loss of Component Cooling Water / 8 2.9 3.5 H H H H H H H H H H Location of a leak in the CCWS 029EK2.06 ATWS / 1 2.9 3.1 H H H H H H H H H H Breakers, relays, and disconnects.

040AG2.2.3 Steam Line Rupture - Excessive Heat 3.8 3.9 LI H H H H H H H H H (multi-unit license) Knowledge of the design, procedural Transfer / 4 and operational differences between units.

054AK3.01 Loss of Main Feedwater / 4 4.1 4.4 H H H H H H H H H H Reactor and/or turbine trip, manua( and automatic Page 1 of 2 10/04/2013 9:30AM

ES-401, REV 9 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 056AA2.54 Loss of Off-site Power/6 2.9 3 Breaker position (remote and local)

ElElEl 062AA1.01 Loss ofNuclearSvcWater/4 3.1 3.1 Nuclear service water temperature indications ElElElEl 065AG2.l.32 LossoflnstrumentAir/8 3.8 4.0 Ability to explain and apply all system limits and El El El El El El ElElEI precautions.

077AK2.01 Generator Voltage and Electric Grid 3.1 3.2 Motors Disturbances I 6

[] El El El El El ElElElEl weO4EG2.4.3 LOCA Outside Containment / Ability to identify post-accident instrumentation.

El El El El El El El EJElE WE05EK2.2 Inadequate Heat Transfer Loss of 3.9 4.2 Facilitys heat removal systems, including primary Secondary Heat Sink / 4 El El El El El El ElElElEl coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 1 EK1 .3 Loss of Emergency Coolant Recirc. / 4 3.6 4.0 Annunciators and conditions indicating signals, and El remedial actions associated with the (Loss of Emergency Coolant Recir).

Page 2 of 2 10/04/2013 9:30AM

ES-401, REV 9 TIG2 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 OO1AG2.1 .20 Continuous Rod Withdrawal I 1 4.6 4.6 H H H H H H H H H Ability to execute procedure steps.

036AA1.04 Fuel Handling Accident/8 3.1 3.7 Fuel handling equipment during an incident 037AK3.06 Steam Generator Tube Leak) 3 3.6 4.1 H H H H H H H H H H Normal operating precautions to preclude or minimize SGTR 051AA2.02 Loss of Condenser Vacuuml4 3.9 4.1 Conditions requiring reactorand/orturbine trip 059AK1.0l Accidental Liquid RadWaste Rel. / 9 2.7 3.1 Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 074EG2.4.21 mad. Core Cooling /4 4.0 4.6 H H H H H H H H H H Knowledge of the parameters and logic used to assess the status of safety functions WEO3EK2.1 LOCA Cooldown Depress. /4 3.6 4.0 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE14EK2.l Loss of CTMT Integrity / 5 3.4 3.7 H H H H H H H H H H Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WEI 5EK1 .2 Containment Flooding /5 2.7 2.9 H H H H H H H H H H Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

Page 1 of 1 10/04/2013 9:30AM

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 003G2.4.50 Reactor Coolant Pump 4.2 4.0 Ability to verify system alarm setpoints and operate controls Li J identified in the alarm response manual.

004A2.26 Chemical and Volume Control 2.8 3.0 Low VCT pressure LI 0041(5.06 Chemical and Volume Control 3.0 3.3 Concept of boron worth or inverse boron worth Li [] Li fl (reactivity, pcmlppm) 005K5.09 Residual Heat Removal 3.2 3.4 Dilution and boration considerations 006K4.ll EmergencyCoreCooling 3.9 4.2 ResetofSlS Li LI 007A1 .02 Pressurizer Relief/Quench Tank 2.7 2.9 j Maintaining quench tank pressure J

007K5.02 Pressurizer Relief/Quench Tank 3.1 34 Method of forming a steam bubble in the PZR Li Li Li Li IJ Li Li Li Li Li Li 008K3.03 Component Cooling Water 4.1 4.2 RCP Li Li Li Li Li Li Li Li Li [1 O1OK1.06 PressurizerPressureControl 2.9 3.1 CVCS Li Li Li Li Li Li Li Li Li 0101(4.01 PressurizerPressureControl 2.7 2.9 Sprayvalvewarm-up Li Li Li Li Li Li Li Li Li Li 012K6.ll Reactor Protection 2.9 2.9 Trip setpoint calculators Li Li Li LI Li []

Page 1 of 3 10/04/2013 9:30AM

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

RO SRO 01 3K2.0l Engineered Safety Features Actuation 3.6 3.8 LI ESFAS/safeguards equipment control LI LI LI LI LI LI C] C] LI 013K6.0l Engineered Safety Features Actuation 2.7 3.1 C] C] C] Sensors and detectors C] C] C]

022A3.01 Containment Cooling 4.1 4.3 Initiation of safeguards mode of operation C] LI LI LI LI LI LI LI LI LI 026A4.05 Containment Spray 3.5 3.5 Containment spray reset switches LI LI LI LI LI LI LI LI LI LI 026K4.09 Containment Spray 3.7 4.1 Prevention of path for escape of radioactivity from LI LI LI LI LI LI LI LI LI LI containment to the outside (interlock on RWST isolation after swapover) 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS LI LI LI C] LI LI LI LI LI LI 059K3.03 Main Feedwater 3.5 3.7. S/GS LI LI ] LI LI LI LI LI LI LI LI 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps LI C] LI LI LI LI LI LI LI LI 062A1 .01 AC Electrical Distribution 3.4 3.8 Significance of DIG load limits LI LI LI LI LI LI ] LI LI LI LI 063G2.1 .31 DC Electrical Distribution 4.6 4.3 Ability to locate control room switches, controls and LI C] LI LI LI LI LI LI LI LI indications and to determine that they are correctly reflecting the desired plant lineup.

063K1.03 DC Electrical Distribution 2.9 3.5 Battery charger and battery LI LI LI LI LI LI LI LI LI C]

Page 2 of 3 10/04/2013 9:30 AM

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 064K1 .03 Emergency Diesel Generator 3.6 4.0 Diesel fuel oil supply system LI 073A2.02 Process Radiation Monitoring 2.7 3.2 Detector failure LI LI LI LI LI LI LI LI LI LI 076K2.08 Service Water 3.1 3.3 ESF-actuated MOVs LI LI LI LI LI LI LI LI LI LI 078A4.01 InstrumentAir 3.1 3.1 Pressure gauges LI LI LI LI LI LI LI LI LI ] LI 103A2.04 Containment 3.5 3.6 Containment evacuation (including recognition of the alarm)

LI LI LI LI LI LI LI LI LI LI 103A3.01 Containment 3.9 4.2 Containment isolation LI LI LI LI LI LI LI LI LI LI Page 3 of 3 10/04/2013 9:30 AM

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 015A4.02 Nuclear Instrumentation 3.9 39 NIS indicators El 016K1.08 Non-nuclearlnstrumentation 3 PZRPCS El El El El El El El El El El 027K2.O1 Containment Iodine Removal 3.1 3.4 Fans 028K5.03 Hydrogen Recombiner and Purge 2.9 3.6 Sources of hydrogen within containment Control 033K3.02 Spent Fuel Pool Cooling 2.8 3.2 Area and ventilation radiation monitoring systems El 034K6.02 Fuel Handling Equipment 2.6 3.3 Radiation monitoring systems 071A3.Ol Waste Gas Disposal 2.6 2.7 HRPS El El El El El El El El El El 072G2.l.28 Area Radiation Monitoring 4.1 4.1 Knowledge of the purpose and function of major system El El El El El El El El El El components and controls.

079K4.O1 Station Air 2.9 3.2 Cross-connect with lAS El El El El El El El El El El 086A1 .01 Fire Protection 2.9 3.3 Fire header pressure El El El El El El El El El El Page 1 of 1 10/04/2013 9:30 AM

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:

RO SRO G2.l.29 Conduct of operations 4.1 4.0 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.l.40 Conduct of operations 2.8 3.9 Knowledge of refueling administrative requirements G2.1 .5 Conduct of operations 2.9 3.9 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

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

G2.2.2 Equipment Control 4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements J

during normal or abnormal conditions G2.4.1 Emergency Procedures/Plans 4.6 4.8 Knowledge of EOP entry conditions and immediate action steps.

G2.4.32 Emergency Procedures/Plans 3.6 4.0 Knowledge of operator response to loss of all annunciators.

G2.4.4 Emergency Procedures/Plans 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30 AM

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

RO SRO 009EA2.39 Small Break LOCA I 3 Adequate core cooling 022AA2.0l Loss of Rx Coolant Makeup /2 3.2 3.8 Whether charging line leak exists 027AA2.lO Pressurizer Pressure Control System 3.3 3.6 jrj PZR heater energized/de-energized condition Malfunction / 3 057AG2.1 .28 Loss of Vital AC Inst. Bus 16 4.1 4.1 Knowledge of the purpose and function of major system components and controls.

well EG2.l .32 Loss of Emergency Coolant Recirc. / 4 3.8 4.0 Ability to explain and apply all system limits and precautions.

wel2EG2.4.4 Steam Line Rupture Excessive Heat 4.5 4.7 Ability to recognize abnormal indications for system Transfer I 4 operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 1(3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 024AG2.l.23 Emergency Boration / 1 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

033AG2.2.44 Loss of Intermediate Range NI / 7 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions WEO1 EA2.l Rediagnosis / 3 3.2 4 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE16EA2.2 High Containment Radiation / 9 3.0 3.3 Adherence to appropriate procedures and operation LI LI LI LI LI LI LI LI LI LI within the limitations in the facilitys license and amendments.

Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO 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 004G2.2.22 Chemical and Volume Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

013A2.03 Engineered Safety Features Actuation 4.4 4.7 Rapid depressurization 059A2.0l Main Feedwater 3.4 3.6 Feedwater actuation of AFW system 061G2.4.49 Auxiliary/Emergency Feedwater 4.6 4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

078A2.01 Instrument Air 2.4 2.9 Air dryer and filter malfunctions Page 1 of 1 10/04/2013 9:30AM

ES-401, REV 9 SRO T2G2 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 017G2.4.47 In-core Temperature Monitor 4.2 4.2 Ability to diagnose and recognize trends in an accurate J

and timely manner utilizing the appropriate control room reference material.

056A2.04 Condensate 2.6 2.8 Loss of condensate pumps 075G2.2.44 Circulating Water 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Page 1 of 1 10/04/2013 9:30AM

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.25 Conduct of operations 3.9 4.2 Ability to interpret reference materials such as graphs,

[

monographs and tables which contain performance data.

G2.l .32 Conduct of operations 3.8 4.0 Ability to explain and apply all system limits and precautions.

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

D L D L fl G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance D LI LI LI LI LI LI activities during shutdown operations.

G2.3.ll Radiation Control 3.8 4.3 Ability to control radiation releases G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.

Page 1 of 1 10/04/2013 9:30AM

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __Surry ______________________ Date of Examination: _7/21/14______

Exam Level: SRO-I Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8 h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROI Actual Criteria Met (A)lternate path 4-6 5 YES (D)irect from bank 8 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 2 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Surry________________________ Date of Examination: _7/21/14______

Exam Level: SRO-U Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5 d.

e.

f.

g.

h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel j.
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROUI Actual Criteria Met (A)lternate path 2-3 3 YES (D)irect from bank 4 3 YES (E)mergency or abnormal in-plant 1 2 YES (EN)gineered safety feature 1 1 YES (L)ow -Power / Shutdow n 1 2 YES (N)ew or (M)odified from bank including 1(A) 1 2 YES (P)revious 2 exams (randomly selected) 2 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry_______________________ Date of Examination: _7/21/14_____

Examination Level: SRO Operating Test Number: _SR14301__

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

Quadrant Power Tilt Ratio Conduct of Operations R/D K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations S/D K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8

/ SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control R/D K/A: 2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Authorize Emergency Exposure Radiation Control R/D K/A: 2.3.4. Knowledge of radiation exposure limits under normal or emergency conditions. RO: 3.2 / SRO 3.7 Classify and Determine PAR for General Emergency Emergency Procedures/Plan R/N K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications. 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: ___Surry _____________________ Date of Examination: _7/21/14______

Exam Level: RO Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8
h. Respond to a #3 EDG Start Failure N/A/S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U RO Actual Criteria Met (A)lternate path 4-6 6 YES (D)irect from bank 9 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 3 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Surry_________________________ Date of Examination: __7/21/14_____

Examination Level: RO Operating Test Number: _SR14-301_

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

Quadrant Power Tilt Ratio Conduct of Operations R/D K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Conduct of Operations Perform a review of OPT-FW-006 Equipment Control R/D K/A: 2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Calculate Radiation Exposure when Placing Unit 1 Radiation Control Residual Heat Removal System in Service R/D K/A: 2.3.4 Know ledge of radiation exposure limits under normal or emergency conditions. RO: 2.5 / SRO: 3.1 Obtain Required Information IAW EPIP-2.01 Emergency Procedures/Plan S/N 2.4.39 Know ledge of RO responsibilities in emergency plan implementation. RO: 3.9 / SRO: 3.8.

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: ___Surry _____________________ Date of Examination: _7/21/14______

Exam Level: RO Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8
h. Respond to a #3 EDG Start Failure N/A/S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U RO Actual Criteria Met (A)lternate path 4-6 6 YES (D)irect from bank 9 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 3 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Surry_______________________ Date of Examination: _7/21/14_____

Examination Level: SRO Operating Test Number: _SR14301__

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

Quadrant Power Tilt Ratio Conduct of Operations R/D K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. RO: 4.4/SRO: 4.7 Authorize Fuel Movement Conduct of Operations S/D K/A: G2.1.40 Knowledge of refueling administrative procedures RO: 2.8

/ SRO: 3.9 Perform a review of OPT-FW-006 Equipment Control R/D K/A: 2.2.12 Knowledge of surveillance procedures. RO: 3.7 / SRO: 4.1 Authorize Emergency Exposure Radiation Control R/D K/A: 2.3.4. Knowledge of radiation exposure limits under normal or emergency conditions. RO: 3.2 / SRO 3.7 Classify and Determine PAR for General Emergency Emergency Procedures/Plan R/N K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications. 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: __Surry ______________________ Date of Examination: _7/21/14______

Exam Level: SRO-I Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5
d. Re-establish Normal Letdown Following SI D/S/A/L 3
e. Cross-Connect Auxiliary Feedwater from Unit 1 to Unit 2 D/S 4S
f. Remove a Failed SR NI From Service D/S/L 7
g. Respond to a Low Level Transient D/S 8 h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel
j. Isolate Service Water to MER #3 D/A/LE 3
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROI Actual Criteria Met (A)lternate path 4-6 5 YES (D)irect from bank 8 8 YES (E)mergency or abnormal in-plant 1 3 YES (EN)gineered safety feature (L)ow -Power / Shutdow n 1 6 YES (N)ew or (M)odified from bank including 1(A) 2 2 YES (P)revious 2 exams (randomly selected) 3 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _Surry________________________ Date of Examination: _7/21/14______

Exam Level: SRO-U Operating Test No.: _SR14301______

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

System / JPM Title Type Code* Safety Function

a. Respond to Control Rod Withdrawal M/S/A 1
b. Respond to a Failed Low PRZR Level Channel M/S 2
c. Configure Containment Spray IAW ECA-1.1 D/S/A/EN/L 5 d.

e.

f.

g.

h.

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

i. Locally Transfer Individual Components to the Aux Shutdown D/L/E 8 Panel j.
k. Locally Swap U-2 AFW to Fire Water D/A/L/E 4S

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

  • Type Codes Criteria for RO / SRO-I / SRO-U SROUI Actual Criteria Met (A)lternate path 2-3 3 YES (D)irect from bank 4 3 YES (E)mergency or abnormal in-plant 1 2 YES (EN)gineered safety feature 1 1 YES (L)ow -Power / Shutdow n 1 2 YES (N)ew or (M)odified from bank including 1(A) 1 2 YES (P)revious 2 exams (randomly selected) 2 0 YES (R)CA 1 1 YES (S)imulator / (C)ontrol room
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