ML17191B424

Exam Administrative Items - Delay Release 2 Yrs

ML17191B424
Person / Time
Site:	Watts Bar
Issue date:	07/10/2017
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-390/16-301, 50-391/16-301, ES-201-1 50-390/OL-16, 50-391/OL-16
Download: ML17191B424 (46)

Text

ES-201 Examination Preparation Checklist Form ES-207-1 Facility: Watts Bar Date of Examination: July, 2076 Developed by: Written: Facility NRC ., II Operating Facility El NRC Target Task Description (Reference)

Date*

-180 1. Examination administration date confirmed (Cia; C.2.aand b)

-150 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)

-150 3. Facility contact briefed on security and other requirements (C.2.c)

-150 4. Corporate notification letter sent (C.2.d)

[-120] 5. Reference material due (C.1 .e; C.3.c; Attachment 3)

{-90] 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1, ES-401-1/2, ES-401N-1/2, ES-401-3, ES-401N-3, ES-401-4, and ES-401N-4, as applicable (C.l.e and t; C.3.d)

[-85] 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)

{-60} 8. Proposed examinations (including written, walk-through ]PMs, and scenarios, as applicable), supporting documentation (including Forms ES-301 -3, ES-301 -4, ES 301-5, ES-301-6, and ES-401-6, ES-401N-6, and any Form ES-201-2, ES-201-3, ES-301-l, or ES-301-2 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

-45 9. Written exam and operating test reviews completed. (C.3.f)

-30 10. Preliminary license applications (NRC Form 398s) due (Cli; C.2.g; ES-202)

-21 11. Examination approved by NRC supervisor for facility licensee review (C,2.h; C.3.f)

-21 12. Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g)

-14 13. Final license applications due and Form ES-201-4 prepared (Cli; C.2.i; ES-202)

-14 14. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 15. Facility licensee management queried regarding the licensees views on the examination. (C.2 j)

-7 16. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204)

-7 17. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)

-7 18. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by case basis in coordination with the facility licensee.

[Applies onlyj {Does not apply} to examinations prepared by the NRC.

ES-207 Examination Outline Quality Checklist Form ES-201-2 Facility: tJ 1T1S fl R .. 30 Date of Examination:

zi Item Initials Task Description a b c#

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

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

N

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. 2.

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

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, and major s transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number and U 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 at OJii A least one new or significantly modified scenario, that no scenarios are duplicated from the T 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 distributed W among the safety functions as specified on the form A (2) task repetition from the last two NRC examinations is within the limits specified on the form L (3) no tasks are duplicated from the applicants audit test(s)

K (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 T the form.

H R b. Verifythatthe administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form oJ)

U (2) at least one task is new or significantly modified C)

G (3) no more than one task is repeated from the last two NRC licensing examinations H

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.

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

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.

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

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

Printed Name/SignaU e Date

a. Author 1o44., \

b. Facility Reviewer () ,__.JA r C +-c3r.cci

c. NRC Chief Examiner (#) (6<J..J Ut ?7-

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

Not applicable for NRC-prepared examination outlines.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ___Watts Bar_______________________ Date of Examination: _July 2016___

Examination Level: RO SRO Operating Test Number: _2016-301_

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

Calculate Shutdown Margin K/A Conduct of Ops: 2.1.7 (4.4): Ability to Conduct of Operations R, N evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Calorimetric Calculation K/A Conduct of Ops: 2.1.7 (4.4): Ability to Conduct of Operations S/R, N evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Equipment Control Identify isolation boundary for 1A BAT pump R, N K/A Equipment Control 2.2.13 (4.1/4.3):

Knowledge of tagging and clearance procedures.

Perform a Stay Time Calculation using RCI-Radiation Control 100, Radiological Controls procedure. More R, N information attached in this document concerning this JPM.

K/A Radiation Control 2.3.4 (3.2/3.7):

Knowledge of radiation exposure limits under normal or emergency conditions.

N/A N/A Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• 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 Administrative Topics Outline Form ES-301-1 Facility: ___Watts Bar_______________________ Date of Examination: _July 2016___

Examination Level: RO SRO Operating Test Number: _2016-301_

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

Review 2-SI-0-2-MC for Mode Change R, N K/A Equipment Control 2.2.1 (4.5): Ability to Conduct of Operations perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

Calorimetric Calculation R, N Conduct of Operations K/A Conduct of Ops: 2.1.7 (4.7): Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Equipment Control Identify isolation boundary for 1A BAT pump R, N K/A Equipment Control 2.2.13 (4.1/4.3):

Knowledge of tagging and clearance procedures.

Perform a Stay Time Calculation using RCI-100, Radiological Controls procedure. More R, N information attached in this document Radiation Control concerning this JPM.

K/A Radiation Control 2.3.4 (3.2/3.7)

Knowledge of radiation exposure limits under normal or emergency conditions.

REP Classification and State Notification on River High Level R, D Bank 3-OT-J1C-0-1AS-R2 Emergency Plan K/A Emergency Procedures/ Plan 2.4.38 (2.4/4.4) Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• 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 (REV_031516)

Facility: McGuire Date of Examination: 4/2016 Exam Level (circle one): RO (only) / SRO(I) / SRO Operating Test No.: N16-1 (U)

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Type Code* Safety System / JPM Title Function A. EPE 029 Anticipated Transient Without Scram (ATWS) [EPE 029 EA2.10 (3.1/3.4)] S, D, A 1 Emergency Borate the Reactor Coolant System Using the PD Pump B. 061 Auxiliary/Emergency Feedwater (AFW) System [061 A2.07 (3.4/3.5)] S, M, A, EN 4S CA Suction Source Realignment 004 Chemical Volume & Control System [004 A4.06 (3.6/3.1)]

C.

Establish Excess Letdown following a loss of Normal Letdown in S, N, A, L 2 Mode 4 D. 010 Pressurizer Pressure Control System [010A4.02(3.6/3.4)]

S, D, A 3 Remove Pressurizer Heaters from Service E. EPE E09 Natural Circulation Operations [EPE E09 EA1.1 (3.5/3.5)]

S, D, A, L 4P Depressurize NCS During Natural Circulation Cooldown F. 027 Containment Iodine Removal System [027 A4.01 (3.3/3.3)]

S, D, EN 5 Perform the 1A Annulus Ventilation Operability Test G. 062 AC Electrical Distribution System [062 A2.05 (2.9/3.3)]

S, D 6 Restore Power to 6900V Buses H. 075 Circulating Water System [075 A2.02 (2.5/2.7)]

S, D 8 Isolate the Circulating Water System During Turbine Building Flooding In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

I. EPE 055 Station Blackout [055 EA2.03 (3.9/4.7)]

P, D, R, E 6 Transfer of 1EMXA4 To SSF During A Loss Of All AC on Unit 1 J. 068 Control Room Evacuation [068 AAQ1.23 (4.3/4.4)]

D, E 8 Locally Trip Unit 2 Main Turbine and Both Unit 2 FWPT's NUREG-1021, Revision 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_031516)

K. APE 024 Emergency Boration [024AA1.04(3.6/3.7)]

D, R, E 1 Emergency Borate the NCS Locally Using 2NV-269

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 (5) /4-6 (5) / 2-3 (3)

(C)ontrol room (D)irect from bank 9 (9) / 8 (8) / 4 (3)

(E)mergency or abnormal in-plant 1 (3) / 1 (3) / 1 (2)

(EN)gineered Safety Feature 1 (2) / 1 (2)/ 1 (1) (Control Room System)

(L)ow-Power / Shutdown 1 (2) / 1 (2) / 1 (1)

(N)ew or (M)odified from bank including 1(A) 2 (2) / 2 (2) / 1 (2)

(P)revious 2 exams 3 (1) / 3 (1)/ 2 (1) (Randomly Selected)

(R)CA 1 (2)/ 1 (2) / 1 (2)

(S)imulator JPM Summary JPM A This is a Bank JPM. The operator will be told that Unit 1 was at 100% power with A NV pump tagged for maintenance, when a failure of an automatic reactor trip occurred causing entry into EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/ATWS. The operator will be directed to emergency borate the NC System per Step 5 of EP/1/A/5000/FR-S.1. During the course of the procedure implementation the operator will discover that the 1B NV Pump has tripped (Alternate Path). The operator will be expected to attempt to start the 1B NV Pump, and when it fails to start, start the PD Pump, and then commence emergency boration with the 1B Boric Acid Transfer Pumps running and 30 gpm or greater emergency boration flow indicated.

JPM B This is a modified Bank JPM. The operator will be told that Unit 1 has just tripped from 100% power, due to seismic activity, that the crew is now implementing EP/1/A/5000/ES-0.1 (Reactor Trip Response), and that the CA Storage Tank has developed a leak, and level has lowered to 1.5 feet. The operator will be directed to perform EP/1/A/5000/G-1, Generic Enclosure 20 (CA Suction Source Realignment), while the crew continues with ES-0.1. The operator will be expected to realign the suction of the CA Pumps from the non-safety related to the safety-related source (RN). During the course of this action, the operator will recognize that RN Supply to the 1B MDCA Pump cannot be established (Alternate Path), and stop the pump.

JPM C This is a new JPM. The operator will be told that Unit 1 is performing a plant shutdown and cooldown to Mode 5, that the plant is currently at 345°F and 600 psig, that the crew has entered AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection, due to a loss of Normal Letdown, and that it is not expected that the crew will be able to re-establish Normal Letdown without corrective maintenance. The operator will be directed to establish Excess Letdown per AP/1/A/5500/12 starting with Step 52, and maintain Pressurizer level between 85-96%. While establishing Excess Letdown the operator will discover that Excess Letdown cannot be placed in service due to a failure (Alternate NUREG-1021, Revision 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_031516)

Path). The operator will be expected to attempt to place Excess Letdown in service in accordance with Step 52 of AP/1/A/55/12; and then after recognizing that Excess Letdown cannot be placed in service, establish letdown to the PRT using the Rx Head Vessel Vents in accordance with Step 53 of AP/1/A/5500/12 and maintain Pressurizer level between 85-96%.

JPM D This is a Bank JPM. The operator will be told that plant power has just been raised to 100% per OP/1/A/6100/003 (Controlling Procedure for Unit Operation). The operator will be directed to remove Pzr Heater Groups A, B and D from service per Enclosure 4.6 (Operation of Pzr Heaters) of OP/1/A/6100/003. The operator will be expected to remove the A, B and D Pzr Heater Groups from service in accordance with the Enclosure. After the Pzr Pressure Master has been placed in MANUAL and its output has been adjusted, the Pzr Variable Heaters (Group C) will fail (Alternate Path). The operator will be required to respond to MCB Annunciator 1AD6/D6 (PZR HTR CONTROLLER TROUBLE), and manually control pressure using the other heater groups. The operator will be expected to place at least one Pzr Heater Group in service in accordance with Step 3.3.1 (or equivalent) of Enclosure 4.6.

JPM E This is a Bank JPM. The operator will be told that Unit 1 has tripped from 100% power due to a Loss of Off-Site Power, that the crew is currently implementing EP/1/A/5000/ES-0.2 (Natural Circulation Cooldown), and is currently at Step 15; and that Normal Letdown is in service. The operator will be directed to perform Step 15 of ES-0.2, depressurizing the NC system to 1905 PSIG using aux spray per Generic Enclosures, Enclosure 3 (Establishing NV Aux Spray). The operator will be expected to place Auxiliary Spray in service and lower Pzr Pressure to 2030 psig; and after diagnosing a loss of Normal Letdown (Alternate Path) immediately remove Aux Spray from service.

JPM F This is a Bank JPM. The operator will be told that Unit 1 is operating at 100% power, that Unit 1 VE System is aligned for Engineered Safeguards Operation, and that PT/1/A/4450/003 A (Annulus Ventilation System Train 'A' Operability Test) is on the Operations schedule for today. The operator will be directed to perform PT/1/A/4450/003 A (Annulus Ventilation System Train 'A' Operability Test). The operator will be expected to place the 1A VE Fan in Recirculation Mode with the cross connect from B Train closed.

The 1A VE Fan will be shut down after flow verification and returned to normal alignment.

JPM G This is a Bank JPM. The operator will be told that a total loss of Offsite Power has occurred to the Unit 1 Switchyard, that Unit 1 tripped from 100% power, and that the Electrical Grid has remained energized throughout the event. The operator will also be told that Unit 1 has implemented AP/1/A/5500/07 (Loss of Electrical Power), Case I (Loss of Normal Power to 1ETA and 1ETB), that power has been restored to the Unit 1 Switchyard, and that the crew is preparing to restore power to the 6900VAC Buses, and is complete through Step 43.p. The operator will be directed to restore power to the 6900V buses starting with Step 43.q of AP/1/A/5500/07 (Loss of Electrical Power), Case I (Loss of Normal Power to 1ETA and 1ETB) using the Normal Supply breakers. The operator will be expected to re-energize all four 6900V Buses per AP/1/A/5500/07 Steps 43.q-r.3.

JPM H This is a Bank JPM. The operator will be told that there is massive flooding in the Turbine Building and that the crew has implemented AP/0/A/5500/44 (Plant Flooding), Enclosure 1 (Unit 1 Turbine Bldg Flooding). The operator will be directed to isolate the RC System by continuing with Enclosure 1 of AP/0/A/5500/44, step 5.d, while the crew continues with EP/1/A/5000/E-0 (Reactor Trip and/or Safety Injection). The operator will be expected to NUREG-1021, Revision 10

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_031516) take actions to isolate the Unit 1 RC System in accordance with Enclosure 1 of AP/0/A/5500/44. This task was chosen because Internal Flooding events are a large PRA contributor (15% CDF). This is a Time Critical JPM.

JPM I This is a Bank JPM. The operator will be told that a Station Blackout has occurred at Unit 1, that the crew is currently in EP/1/A/5000/ECA-0.0 (Loss of All AC Power), and that the CRS has dispatched an operator to the SSF to complete Enclosure 2 (Unit 1 SSF ECA-0.0 Actions). The operator will be directed to perform Enclosure 3 (Unit 1 ETA and ETB Rooms - ECA-0.0 Actions). The operator will be expected to transfer 1EXMA-4 to its alternate power supply within 3 minutes from dispatch (Start of the JPM), and identify that the 1ETA2 Lockout Relay has tripped. This was previously used on the 2015 NRC Exam, randomly selected for use on the 2016 Exam.

JPM J This is a Bank JPM. The operator will be told that a loss of control room has occurred, that AP/2/A/5500/17 (Loss Of Control Room) has been implemented and is complete through step 10.b, that the operator has been dispatched to standby at the Unit 2 Main Turbine, and that communications have been established between them and the SRO at the Unit 2 Aux. Shutdown panel. The operator will be directed to perform the local actions of Step 10.c.1-3 of AP/1/A/550/17 Loss of Control Room). The operator will be expected to trip the Unit 2 Main Turbine locally, and trip any of the available "trip" mechanisms on both FWPT's such that 2SP-1 and 2SP-2 are closed.

JPM K This is a Bank JPM. The operator will be told that Unit 2 was at 100% power when a Boron dilution event occurred, that AP/2/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution) was entered, and that while attempting to open 2NV-265B (Boric Acid To NV Pumps), the RO discovered that 2NV-265B was de-energized. The operator will be directed to emergency borate the NC System by performing Step 12.d RNO of AP/2/A/5500/38. The operator will be expected to attempt to open 2NV-265B, and when this fails open 2NV-269 within ten (10) minutes of dispatch. This is a Time Critical JPM.

NUREG-1021, Revision 10

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: A _ 2.%i b 3b Date of Examination: J I ( 20 ° Operating Test Number: 2 ti SC)

1. General Criteria Initials a b c#

a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).

ç rJJit O

b. There is no day-to-day repetition between this and other operating tests to be administered k ,

during this examination.

c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1 .a.)

U. Overlap with the written examination and between different parts of the operating test is within acceptable limits.

e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.

2. Walk-Through Criteria -- - --

a. Each JPM includes the following, as applicable:

• initial conditions

• initiating cues

• references and tools, including associated procedures

• reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee

• operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.

3. Simulator Criteria --

The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.

Printed Name / Sign Date

a. Author Piwltn(t. Io4 (i\bjt

b. Facility Reviewerç) NP.C - --

c. NRC Chief Examiner (Ii) 7f]oi

d. NRC Supervisor ])O.-S)_S.. z c ci -

NOTE:

• The facility signature is not applicable for NRC-developed tests.

1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: tfrTiS Date of Exam:J\j 2OUz Scenario Numbers: I / 2! /+ Operating Test No.:2tilI lnWals QUALITATIVE ATTRIBUTES a b* cIt

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, , i I f4 but it does not cue the operators into expected events.

2. The scenarios consist mostly of related events. I

3. Each event description consists of

• the point in the scenario when it is to be initiated

• the malfunction(s) or conditions that are entered to initiate the event

• the symptoms/cues that will be visible to the crew

• the expected operator actions (by shift position)

. the event termination point (if applicable)

4. The events are valid with regard to physics and thermodynamics. -

5. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete (yfl evaluation results commensurate with the scenario objectives. .cl -

6. It time compression techniques are used, the scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints.

I Cues are given.

7. The simulator modeling is not altered.

8. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

9. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301.

10. All individual operator competencies can be evaluated, as verified using Form ES-301 -6 (submit the form along with the simulator scenarios).

1 1. The scenario set provides the opportunity for each applicant to be evaluated in each of the applicable rating factors. (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- --

1. Malfunctions after EOP entry (1-2) 2/2/2/ 1

2. Abnormal events (2-4) 4 / 3/4 /4 -

3. Major transients (12) 1 /2/2/2 -

4. EOPs entered/requiring substantive actions (12) 2/3/2/3 -

5. EOP contingencies requiring substantive actions (0-2) 0/ 1 /1 /0

6. EOP based Critical tasks (23) 2/2/2/2 NOTE:

• The facility signature is not applicable for NRC-developed tests.

1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Watts Bar Date of Exam: July 2016 Operating Test No.:2016-301 A E Scenarios P V P E 1 2 3 4 T M L N O I CREW CREW POSITION CREW POSITION CREW POSITION N I T POSITION T C I A

A T S A B S A B S A B S A B M L U N Y R T O R T O R T O R T O T P O C P O C P O C P O C P M(*)

E R I U RO RX 1 1 4 4 3 3 1 1 1 1 0 NOR 1 4 1 1 2 2 1 1 1 SRO-I I/C 2,3,4 2,3,4 7 1,2,3 2,3,5 1 2,3 2 3,4,5 3,4,5 3,4,6 5 4 4 2 SRO-U ,6,7 ,6 ,5 MAJ 5 5 5 6 6 6 5 5 5 6 6 6 2 2 1 TS 3,4 1,3 3 3 0 2 2 RO 1,3 RX 4 1 1 1 0 NOR 1 2 2 1 1 1 SRO-I I/C 7 2,3,5 5 5 4 4 2 SRO-U MAJ 5 6 6 3 2 2 1 TS 0 0 2 2 RO 2,4 RX 1 1 1 1 0 NOR 4 1 1 1 1 SRO-I I/C 2,3,4 1 5 4 4 2 SRO-U ,6 MAJ 5 6 2 2 2 1 TS 3,4 0 0 2 2 RO 5 RX 4 1 1 1 0 NOR 2 1 1 1 1 SRO-I I/C 2,3,5 5 4 4 4 2 SRO-U MAJ 6 6 2 2 2 1 TS 0 0 2 2 RO 6 RX 1 1 1 1 0 NOR 4 1 1 1 1 SRO-I I/C 2,3,4 1 5 4 4 2 SRO-U ,6 MAJ 5 6 2 2 2 1 TS 0 0 2 2 RO 7 RX 1 1 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 7 3,4,6 4 4 4 2 SRO-U MAJ 5 6 2 2 2 1 TS 0 0 2 2

RO RX 1 4 1 3 1 1 0 NOR 1 1 1 SRO-I I/C 2,3,4 1,2,3 3,4,6 12 4 4 2 SRO-U ,6,7 ,5 MAJ 5 6 6 3 2 2 1 TS 3,4 1,3 4 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

ES-301 Competencies Checklist Form ES-301-6 RO RO SRO-I SRO-I SRO-U SRO-U Competencies SCENARIO SCENARIO 1 2 3 4 1 2 3 4 Interpret/Diagnose 2,3,4,5,6, 1,2,3,4 2,3,4,5 1,3,4,5, 2,3,4,5, 1,2,3,4 2,3,4,5 1,3,4,5,6 Events and Conditions 7 6 6,7 Comply With and 1,2,3,4,5, 1,2,3,4,5, 12,3,4,5 1,2,3,4, 1,2,3,4, 1,2,3,4, 12,3,4, 1,2,3,4,5, Use Procedures (1) 6,7 6 5,6 5,6,7 5,6 5 6 Operate Control 1,2,3,4,5, 1,2,3,4,5 1,2,3,4, 1,2,3,4, 1,2,3,4, 1,2,3,4, 1,2,3,4 1,2,3,4,5, Boards (2) 6,7 5 5,6 5,6,7 5 ,5 6 Communicate 1,2,3,4,5, 1,2,3,4,5, 1,2,3,4, 1,2,3,4, 1,2,3,4, 1,2,3,4, 1,2,3,4 1,2,3,4,5, and Interact 6,7 6 5 5,6 5,6,7 5,6 ,5 6 Demonstrate 1,2,3,4,5, 1,2,3,4,5, 1,2,3,4, 1,2,3,4, Supervisory Ability (3) 6,7 6 5 5,6 Comply With and 3,4 2,3 3 3,4 Use Tech. Specs. (3)

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

ES-401 PWR Examination Outline Form ES-401-2 Facility: Watts Bar Date of Exam: July, 2016 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 2 2 1 N/A 1 2 N/A 1 9 2 2 4 Plant Evolutions Tier Totals 5 5 4 4 5 4 27 5 5 10 1 3 2 2 2 3 2 3 3 2 3 3 28 3 2 5 2.

Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 - 1 2 3 Systems Tier Totals 4 2 3 3 4 3 4 4 3 4 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 3 3 1 3 2 2 1 2 7 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 with justification; 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 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. 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 a category 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.

G* Generic K/As

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G* K/A Topic(s) IR #

1 2 3 1 000007 (BW/E02&E10; CE/E02) Reactor Trip - X 007EK1.04; Knowledge of the operational implications of 3.6 1 Stabilization - Recovery / 1 the following concepts as they apply to the reactor trip:

Decrease in reactor power following reactor trip (prompt drop and subsequent decay).

000008 Pressurizer Vapor Space Accident / 3 X 008AK3.03; Knowledge of the reasons for the following 4.1 2 responses as they apply to the Pressurizer Vapor Space Accident: Actions contained in EOP for PZR vapor space accident/ LOCA.

000009 Small Break LOCA / 3 X 009EA2.07; Ability to determine or interpret the following 2.7 3 as they apply to a small break LOCA: CCWS surge tank vent isolation valve indication.

000011 Large Break LOCA / 3 X 011AG2.2.37; Ability to determine operability and/or 4.6 76 availability of safety related equipment.

000015/17 RCP Malfunctions / 4 X 015AG2.2.12; Knowledge of surveillance procedures. 4.1 77 000022 Loss of Rx Coolant Makeup / 2 X 022AG2.4.1; Knowledge of EOP entry conditions and 4.6 4 immediate action steps.

000025 Loss of RHR System / 4 X 025AK3.03; Knowledge of the reasons for the following 3.9 5 responses as they apply to the Loss of Residual Heat Removal System: Immediate actions contained in EOP for Loss of RHRS.

000026 Loss of Component Cooling Water / 8 X 026AG2.4.6; Knowledge of EOP mitigation strategies. 4.7 78 000027 Pressurizer Pressure Control System X 027AK2.03; Knowledge of the interrelations between the 2.6 6 Malfunction / 3 Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners.

000029 ATWS / 1 X 029EK2.06; Knowledge of the interrelations between the 2.9 7 following and ATWS: Breakers, relays, and disconnects.

000038 Steam Gen. Tube Rupture / 3 X 038EG2.4.45; Ability to prioritize and interpret the 4.1 8 significance of each annunciator or alarm.

000040 (BW/E05; CE/E05; W/E12) Steam Line X WE12EA1.2; Ability to operate and / or monitor the 3.6 9 Rupture - Excessive Heat Transfer / 4 following as they apply to the (Uncontrolled Depressurization of all Steam Generators): Operating behavior characteristics of the facility.

000054 (CE/E06) Loss of Main Feedwater / 4 X 054AA2.08; Ability to determine and interpret the 2.9 10 following as they apply to the Loss of Main Feedwater (MFW): Steam flow-feed trend recorder.

000055 Station Blackout / 6 X 055EK1.02; Knowledge of the operational implications of 4.1 11 the following concepts as they apply to the Station Blackout: Natural circulation cooling.

000056 Loss of Off-site Power / 6 X 056AK1.03; Knowledge of the operational implications of 3.1 12 the following concepts as they apply to Loss of Offsite Power: Definition of subcooling: use of steam tables to determine it.

000057 Loss of Vital AC Inst. Bus / 6 X 057AA1.05; Ability to operate and / or monitor the 3.2 13 following as they apply to the Loss of Vital AC Instrument Bus: Backup instrument indications.

000058 Loss of DC Power / 6 X 058AA2.03; Ability to determine and interpret the 3.5 14 following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems.

000062 Loss of Nuclear Svc Water / 4 X 062AG2.2.38; Knowledge of conditions and limitations in 3.6 15 the facility license.

000065 Loss of Instrument Air / 8 X 065AA2.03; Ability to determine and interpret the 2.9 79 following as they apply to the Loss of Instrument Air:

Location and isolation of leaks.

WE04EK3.2; Knowledge of the reasons for the following W/E04 LOCA Outside Containment / 3 X responses as they apply to the (LOCA Outside 3.4 16 Containment): Normal, abnormal and emergency operating procedures associated with (LOCA Outside Containment).

WE11EA1.3; Ability to operate and / or monitor the W/E11 Loss of Emergency Coolant Recirc. / 4 X following as they apply to the (Loss of Emergency 3.7 17 Coolant Recirculation): Desired operating results during abnormal and emergency situations.

WE05EK2.1; Knowledge of the interrelations between BW/E04; W/E05 Inadequate Heat Transfer - X the (Loss of Secondary Heat Sink) and the following: 3.7 18 Loss of Secondary Heat Sink / 4 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

X WE05EA2.1; Ability to determine and interpret the 4.4 80 following as they apply to the (Loss of Secondary Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

077AA2.09; Ability to determine and interpret the 000077 Generator Voltage and Electric Grid X following as they apply to Generator Voltage and Electric 4.3 81 Disturbances / 6 Grid Disturbances: Operational status of emergency diesel generators.

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G* K/A Topic(s) IR #

1 2 3 1 000001 Continuous Rod Withdrawal / 1 X 001AK1.08; Knowledge of the operational 2.9 19 implications of the following concepts as they apply to Continuous Rod Withdrawal: Control rod motion on S/G pressure.

000003 Dropped Control Rod / 1 X 003AA2.04: Ability to determine and interpret 3.6 82 the following as they apply to the Dropped Control Rod: Rod motion stops due to dropped rod.

000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 X 028AA2.03; Ability to determine and interpret 2.8 20 the following as they apply to the Pressurizer Level Control Malfunctions: Charging subsystem flow indicator and controller.

000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 X 036AG2.4.50; Ability to verify system alarm 4.0 83 setpoints and operate controls identified in the alarm response manual.

000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 X 060AK3.02; Knowledge of the reasons for the 3.3 21 following responses as they apply to the Accidental Gaseous Radwaste: Isolation of the auxiliary building ventilation.

000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 X 067AK1.01; Knowledge of the operational 2.9 22 implications of the following concepts as they apply to Plant Fire on Site: Fire classifications, by type.

000068 (BW/A06) Control Room Evac. / 8 X 068AG2.4.50; Ability to verify system alarm 4.2 23 setpoints and operate controls identified in the alarm response manual.

000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 X 076AA1.04; Ability to operate and / or monitor 3.2 24 the following as they apply to the High Reactor Coolant Activity: Failed fuel-monitoring equipment.

W/EO1 & E02 Rediagnosis & SI Termination / 3 X WE01EG2.4.21; Knowledge of the parameters 4.6 84 and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

W/E13 Steam Generator Over-pressure / 4 X WE13EA2.1; Ability to determine and interpret 3.4 85 the following as they apply to the (Steam Generator Overpressure): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

W/E15 Containment Flooding / 5 X WE15EA2.2; Ability to determine and interpret 2.9 25 the following as they apply to the (Containment Flooding): Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments.

W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 WE10EK2.2; Knowledge of the interrelations BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X between the (Natural Circulation with Steam 3.6 26 Void in Vessel with/without RVLIS) and the following: 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.

BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 X WE08EK2.1; Knowledge of the interrelations 3.4 27 between the (Pressurized Thermal Shock) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 2 2 1 1 2/2 1/2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 003 Reactor Coolant Pump X 003A2.02; Ability to (a) predict the impacts 3.7 28 of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

X Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP.

003K5.01; Knowledge of the operational 3.3 29 implications of the following concepts as they apply to the RCPS: The relationship between the RCPS flow rate and the nuclear reactor core operating parameters (quadrant power tilt, imbalance, DNB rate, local power density, difference in loop T-hot pressure).

004 Chemical and Volume Control X 004G2.2.39; Knowledge of less than or 3.9 30 equal to one hour Technical Specification action statements for systems.

005 Residual Heat Removal X 005K2.03; Knowledge of bus power 2.7 31 supplies to the following: RCS pressure boundary motor-operated valves.

X 005K5.03; Knowledge of the operational 2.9 32 implications of the following concepts as they apply the RHRS: Reactivity effects of RHR fill water.

006 Emergency Core Cooling X 006A1.07; Ability to predict and/or monitor 3.3 33 changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including:

Pressure, high and low.

X 006A3.08; Ability to monitor automatic 4.2 34 operation of the ECCS, including:

Automatic transfer of ECCS flowpaths.

007 Pressurizer Relief/Quench Tank X 007K3.01Knowledge of the effect that a 3.3 35 loss or malfunction of the PRTS will have on the following: Containment.

008 Component Cooling Water X 008A1.01; Ability to predict and/or monitor 2.8 36 changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:

CCW flow rate.

010 Pressurizer Pressure Control X 010K2.01; Knowledge of bus power 3.0 37 supplies to the following: PZR heaters.

012 Reactor Protection X 012K5.02; Knowledge of the operational 3.1 38 implications of the following concepts as they apply to the RPS: Power density.

X 012A2.02; Ability to (a) predict the impacts 3.9 86 of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of instrument power.

013 Engineered Safety Features X 013K6.01; Knowledge of the effect of a 2.7 39 Actuation loss/malfunction on the following will have on the ESFAS: Sensors and detectors.

X 013A2.06; Ability to (a) predict the impacts 4.0 87 of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent ESFAS actuation.

022 Containment Cooling X 022K3.02; Knowledge of the effect that a 2.9 40 loss or malfunction of the CCS will have on the following: Containment instrumentation readings.

025 Ice Condenser X 025A2.03; Ability to (a) predict the impacts 3.0 41 of the following malfunctions or operations on the ice condenser system; correct, control, or mitigate the consequences of those malfunctions or operations: Opening of ice condenser doors.

X 025G2.1.27; Knowledge of system 4.0 88 function and/or purpose.

026 Containment Spray X 026K4.01; Knowledge of CSS design 4.2 42 feature(s) and/or interlock(s) which provide for the following: Source of water for CSS, including recirculation phase after LOCA.

039 Main and Reheat Steam X 039A3.02; Ability to monitor automatic 3.1 43 operation of the MRSS, including: Isolation of the MRSS.

059 Main Feedwater X 059A1.07; Ability to predict and/or monitor 2.5 44 changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including:

Feed Pump speed, including normal control speed for ICS.

061 Auxiliary/Emergency Feedwater X 061K6.02; Knowledge of the effect of a 2.6 45 loss or malfunction of the following will have on the AFW components: Pumps.

X 061A2.08; Ability to (a) predict the impacts 2.9 89 of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Flow rates expected from various combinations of AFW pump discharge valves.

062 AC Electrical Distribution X 062G2.4.46; Ability to verify that the 4.2 46 alarms are consistent with the plant conditions.

063 DC Electrical Distribution X 063A4.01; Ability to manually operate 2.8 47 and/or monitor in the control room: Major breakers and control power fuses.

X 063G2.2.37; Ability to determine 4.6 90 operability and/or availability of safety related equipment.

064 Emergency Diesel Generator X 064A4.03; Ability to manually operate 3.2 48 and/or monitor in the control room:

Synchroscope.

X 4.1 49 064G2.4.45; Ability to prioritize and interpret the significance of each annunciator or alarm.

073 Process Radiation Monitoring X 073K1.01; Knowledge of the physical 3.6 50 connections and/or cause-effect relationships between the PRM system and the following systems: Those systems served by PRMs.

076 Service Water X 076A2.01; Ability to (a) predict the impacts 3.5 51 of the following malfunctions/operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of X those malfs./operations: Loss of SWS.

076K1.20; Knowledge of the physical 3.4 52 connections and/or cause- effect relationships between the SWS and the following systems: AFW.

078 Instrument Air X 078A4.01; Ability to manually operate 3.1 53 and/or monitor in the control room:

Pressure gauges.

X 078K4.02; Knowledge of IAS design 3.2 54 feature(s) and/or interlock(s) which provide for the following: Cross-over to other air systems.

103 Containment X 103K1.02; Knowledge of the physical 3.6 55 connections and/or cause-effect relationships between the containment system and the following systems: Cont.

isolation/containment integrity.

K/A Category Point Totals: 3 2 2 2 3 2 3 3/3 2 3 3/2 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 001 Control Rod Drive 002 Reactor Coolant X 002K5.15; Knowledge of the operational 4.2 56 implications of the following concepts as they apply to the RCS: Reasons for maintaining subcooling margin during natural circulation.

011 Pressurizer Level Control X 011K3.01; Knowledge of the effect that a loss 3.2 57 or malfunction of the PZR LCS will have on the following: CVCS.

014 Rod Position Indication X 014A4.01; Ability to manually operate and/or 3.3 58 monitor in the control room: Rod selection control.

015 Nuclear Instrumentation X 015G2.2.25: Knowledge of the bases in 4.2 91 Technical Specifications for limiting conditions for operations and safety limits.

016 Non-Nuclear Instrumentation X 016G2.1.7; Ability to evaluate plant 4.7 92 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

017 In-Core Temperature Monitor X 017K1.01; Knowledge of the physical 3.2 59 connections and/or cause-effect relationships between the ITM system and the following systems: Plant computer.

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge X 029A1.02; Ability to predict and/or monitor 3.4 60 changes in parameters to prevent exceeding design limits associated with operating the Containment Purge System controls including:

Radiation levels.

033 Spent Fuel Pool Cooling X 033A2.02; Ability to (a) predict the impacts of 2.7 61 the following malfunctions or operations on the Spent Fuel Pool Cooling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SFPCS.

034 Fuel Handling Equipment 035 Steam Generator X 035G2.4.8; Knowledge of how abnormal 3.8 62 operating procedures are used in conjunction with EOPs.

041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator X 045K4.44; Knowledge of MT/G system design 2.5 63 feature(s) and/or interlock(s) which provide for the following: Impulse pressure mode control of steam dumps.

055 Condenser Air Removal X 055A3.03; Ability to monitor automatic 2.5 64 operation of the CARS, including: Automatic diversion of CARS exhaust.

056 Condensate 068 Liquid Radwaste X 068K6.10; Knowledge of the effect of a loss or 2.5 65 malfunction on the following will have on the Liquid Radwaste System : Radiation monitors 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection X 086A2.01: Ability to (a) predict the impacts of 3.1 93 the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Manual shutdown of the FPS.

K/A Category Point Totals: 1 0 1 1 1 1 1 1/1 1 1 1/2 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

Knowledge of shift or short-term relief turnover practices.

2.1.3 3.7 66 Knowledge of criteria or conditions that require plant-wide 2.1.14 3.1 67 announcements, such as pump starts, reactor trips, mode changes, etc.

1. 2.1.40 Knowledge of refueling administrative requirements. 2.8 68 Conduct of 2.1.25 Ability to interpret reference materials, such as graphs, 4.2 94 Operations curves, tables, etc.

2.1.35 Knowledge of the fuel-handling responsibilities of SROs. 3.9 95 2.1.

Subtotal 3 2 (multi-unit license) Ability to explain the variations in 2.2.4 3.6 69 control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

2.2.12 Knowledge of surveillance procedures. 3.7 70 Ability to recognize system parameters that are entry-

2. 2.2.42 3.9 71 level conditions for Technical Specifications.

Equipment Control 2.2.21 Knowledge of pre- and post-maintenance operability 4.1 96 requirements.

Ability to interpret control room indications to verify the 2.2.44 4.4 97 status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Subtotal 3 2 Knowledge of radiation or contamination hazards that 2.3.14 3.4 72 may arise during normal, abnormal, or emergency

3. conditions or activities.

Radiation Knowledge of radiation monitoring systems, such as fixed 2.3.15 3.1 98 Control radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Subtotal 1 1 Knowledge of Emergency Plan.

2.4.29 3.1 73 Ability to verify system alarm setpoints and operate 2.4.50 4.2 74 controls identified in the alarm response manual.

Knowledge of local auxiliary operator tasks during an 2.4.35 3.8 75 emergency and the resultant operational effects.

4. Knowledge of how abnormal operating procedures are Emergency 2.4.8 4.5 99 used in conjunction with EOPs.

Procedures / Knowledge of events related to system operation/status Plan 2.4.30 2.7 100 that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

2.4.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 3 2.4.26 WBN does not have the Ops Dept participate in Fire Brigade activities.

Randomly selected 2.4.29 as a replacement.

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility:W h45 p. _ Date of Exam:

• t( .o I Exam Level: RO SRC 20i 3c( Initial Item Description a b* c.#

1 Questions and answers are technically accurate and applicable to the facility. (j) sJ /A

2. a. NRC K/As are referenced for all questions.

b. Facility learning objectives are referenced as available.

3. SAC questions are appropriate in accordance with Section D.2.d of ES-401 J) 4 The sampling process was random and systematic (If more than 4 RO or 2 SAC questions were repeated from the last two NRC licensing_exams, consult the NRA/NRC CL program_office).

5. Question duplication from the licensee screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate The audit exam was systematically and randomly developed: or t r the audit exam was completed before the license exam was started: or X the examinations were developed independently: or the licensee certifies that there is no duplication: or other (explain)

6. Bank use meets limits (no more than 75 percent from the Bank Modified New bank, at least 10 percent new, and the rest new or modified):

enter the actual AC / SRC-only question distribution(s) at 22 I3 10 I4 43! 18

7. Between 50 and 60 percent of the questions on the AC Memo C/A exam are written at the comprehension! analysis level: the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels: enter the actual AC 31/9 44/16 1 SAC question distribution(s) at right.

8. References/handouts provided do not give away answers or aid in the elimination of distractors.

9. Question content conforms to specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned: deviations are justified. 1)

10. Question psychometric quality and format meet the guidelines in ES Appendix B.

1 1. The exam contains the required number of one-point, multiple choice items: the total is correct and agrees with the value on the cover sheet.

Printed Name! Signature Date

a. Author jib

b. Facility Aeviewer()

c. NRC Chiet Examiner(#) -

/at

d. NRC Regional Supervisor .

---(- . - .

1 JS,kLtç Note: The facility reviewers initials or signature are not applicable for NRC-developed examinations.

1. Independent NRC reviewer initials items in Column c: chief examiner concurrence required.

ES-401 Written Examination Review Worksheet Form ES-401-9

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only SYS003 K2.02 1 H 2 N S K/A is met. drl r2/8/16 SYS005 K2.01 K/A is not really met. The K/A is knowledge of bus power supplies : Here you tell them that the bus is 2 F 2 X B S lost and re-supplied with the D/G. Youre not really testing the PS knowledge aspect, but the load restoration aspect. drl 2/8/16 Revised question is SAT. drl 3/1/16 SYS004 K3.06 3 H 2 M S K/A is met. drl 2/8/16 SYS005 A1.01 4 H 2 B S K/A is met. drl 2/8/16 SYS006 A1.15 K/A is mostly met.

5 H 2 X N S Is a 0.5 ºF/min HUR attainable with only one set of heaters failed on? drl 2/8/16 Revised question is SAT. drl 3/1/16 Instructions (Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts:

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) of each question a 1(easy) to 5 ( difficult); (questions with a difficulty between 2 and 4 are acceptable)

3. Check the appropriate box if a psychometric flaw is identified:

• Stem Focus: The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

• Cues: The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc.).

• T/F: The answer choices are a collection of unrelated true/false statements.

• Cred. Dist: The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

• Partial: One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if a job content error is identified:

• Job Link: The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

• Minutia: The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

• # / Units: The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

• Backward: The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved K/A and those K/As that are designated SRO-only (K/A and license level mismatches are unacceptable)

6. Enter questions source: (B)ank, (M)odified, or (N)ew. Verify that (M)odified questions meet the criteria of ES-401 Section D.2.f.

7. Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8. At a minimum, explain any "U" Status ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2 Form ES-401-9

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only SYS006 K6.05 K/A is not really met. What is the effect on ECCS. If a SI were to occur with a loss or partial loss of 6 H 2 X N S cooling, how are the ECCS pumps affected? What you have is close, but does not really meet it. drl 2/8/16 Revised question is SAT. drl 3/1/16 SYS007 A2.05 K/A is partially met. This question does not use procedures to correct, control, or mitigate anything.

7 F 2 X B S The first part is fine as long as Operations deems that the ROs should know PRT rupture setpoint from memory. drl 2/8/16 Revised question is SAT. drl 3/1/16 SYS008 K4.09 8 H 3 B S K/A is met. drl 2/8/16 SYS010 A3.02 9 F 2 N S K/A is met. drl 2/8/16 SYS010 K6.04 K/A is met.

Does the information provided here give the applicants any information that might help them 10 H 2 B S answer question 7 or vice versa? If so we should probably replace the K/A for question 7 or 10.

This is really just a GFES question. drl 2/8/16 After further review this question is SAT. drl 3/1/16 SYS012 A4.06 11 F 2 N S K/A is met. drl 2/8/16 SYS013 K1.13 12 F 3 B S K/A is met. drl 2/8/16 SYS022 A4.01 K/A is met.

13 F 2 B S Is B plausible? Are there other instances of running fans with closed dampers? drl 2/8/16 SYS025 K5 02 14 H 2 B S K/A is met. drl 2/8/16 SYS026 A2.07 K/A may be met, but it definitely is not clear.. The 15 H 3 X X M S fact that you are in ECA-1.1 means that you lost recirculation capability at some point, but you give no

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only indications that that is so.

Im not certain why you state that ECA-1.1 would not direct going to recirc. Step 8.b only requires one of the alarms (1AD-14 or 15) needs to be in alarm in order to meet the requirements of the procedure to go onto recirc. What am I missing? drl 2/8/16 Revised question is SAT. drl 3/1/16 SYS026 K2.01 K/A is met.

A side buses probably arent very plausible. Could 16 F 2 X N S we keep the vital B side buses as answers and provide high voltage non-safety related B buses as the alternative? drl 2/8/16 Revised question is SAT. drl 3/1/16 SYS039 2.4.1 K/A is met.

The format of the first question seems confusing to me. If the applicants are used to seeing it this way, 17 F 2 X N S that is fine. Otherwise we might want to look at reformatting that part.

This one is very close to 2 different unrelated questions. Drl 2/8/16 Revised question is SAT. drl 3/1/16 SYS039 K3.03 K/A is met.

A is not very plausible. Could we change the question a bit to put a tube rupture in C and ask what to isolate per the Emergency Procedures. The correct answer should be 2-SA-2 and 78. The other 18 H 2 X M S two choices would be the corresponding C SG valves. drl 2/8/16 Not quite. I wanted the steam break in A and tube rupture in C. Procedurally they should stop the steam break first and keep steaming the one with the tube leak. drl 3/1/16 Revised question is SAT. drl 3/3/16 SYS059 K4.08 K/A is met.

This is acceptable as long as Operations agrees that 19 F 2 N S their ROs need to have these values memorized. drl 2/8/16 After further review this question is SAT. drl 3/1/16 SYS061 K5.03 20 F 2 N S K/A is met. drl 2/8/16 SYS062 A3.01 21 H 2 B S K/A is met. This is a GFES question. drl 2/8/16

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only SYS063 A3.01 22 H 2 N S K/A is met. drl 2/8/16 SYS063 K4.02 23 F 2 B S K/A is met. drl 2/9/16 SYS064 A2.14 24 F 2 N S K//A is mostly met. drl 2/9/16 SYS073 2.2.12 25 F 3 B S K/A is met. drl 2/9/16 SYS076 K1.19 K/A is .met.

The way this is written, A is potentially not incorrect.

If the valve manually failed, it could be in this position. I agree it is not the best answer, but not 26 H 3 X X B S incorrect. If challenged, I would probably have to accept it as correct.

ON the other hand, would anyone choose a failed valve as an answer? Either way, A is not a good distractor. drl 2/9/16 Revised question is SAT. drl 3/1/16 SYS078 K3.03 27 F 2 B S K/A is met. drl 2/9/16 SYS103 2.2.22 28 F 3 N S K/A is met. drl 2/9/16 SYS002 K6.07 29 H 2 N S K/A is met. drl 2/9/16 SYS015 A2.02 K/A is met.

Can we state that the detector failed low?

30 F 3 X M S Should we give the TS as a reference here? This looks like it might be SRO (below the line) knowledge. drl 2/9/16 Revised question is SAT. drl 3/1/16 SYS016 2.4.4 31 H 2 B S K/A is met. drl 2/9/16 SYS041 K2.01 32 F 2 N S K/A is met.

Loosely related questions. drl 2/9/16 SYS033 K1.05 K/A is met.

Probably need to reference OP/1(2)/A/6200/005 in 33 F 2 X X N S the stem of the question.

Is assured makeup a defined term? I need to verify that RN is the one and only answer. drl 2/9/16

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only Revised question is SAT. drl 3/1/16 SYS034 A1.02 34 H 2 M S K/A is met. drl 2/8/16 SYS001 A4.06 K/A is met.

You dont need to know much to guess that you 35 F 2 X B S disconnect the rods you dont want to move.

Perhaps you can ask where the disconnect is located (MCR or locally). drl 2/9/16 Revised question is SAT. drl 3/1/16 SYS072 K4.01 36 F 3 N S K/A is met. drl 2/9/16 SYS011 K3.03 37 H 3 B S K/A is met. drl 2/9/16 SYS086 K5.04 K/A is not really met.

Second question is irrelevant as written. If you know the answer to the first question, the second question 38 F 2 X X N S does not need asked. Since the K/A is asking to discuss hazards, this really does not work. drl 2/9/16 K/A changed at licensees request. 2/29/16 SYS017K5.02 Revised question is SAT. drl 3/2/16 EPE007 EK1.05 39 H 3 M S K/A is met. drl 2/9/16 EPE009 EK3.11 40 H 2 B S K/A is met. drl 2/9/16 APE015/017 2.1.32 K/A is mostly met.

41 H 3 M S This is acceptable if Operations agrees that their ROs need to have these setpoints memorized. drl 2/9/16 After further review this question is SAT. drl 3/2/16 APE022 2.4.6 42 F 2 N S K/A is met. drl 2/9/16 APE025 AK2.03 43 H 2 N S K/A is met. drl 2/9/16 APE026 AA2.02 44 F 2 N S K/A is met. drl 2/9/16 EPE055 EK1.02 45 H 3 B S K/A is met. drl 2/9/16

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only APE025 2.4.35 46 H 3 N S K/A is met. drl 2/9/16 APE040 AA1.13 K/A is met.

LOD is 1 on this one. If they can read the tiles, they 47 F 2 N S can answer the question. No plant knowledge is required. drl 2/9/16 Revised question is SAT. drl 3/2/16 APE054 AK3.01 48 F 2 N S K/A is met. drl 2/9/16 APE057 AA1.05 K/A is not really met.

Again the second question is not required to be answered If you know the answer to the first 49 F 2 X N S question.

Is there any overlap with the information required by question 22? Drl 2/9/16 Revised question is SAT. drl 3/2/16 APE058 AA2.03 50 H 3 B S K/A is met. drl 2/9/16 APE062 AK3.04 51 H 3 N S K/A is met. drl 2/10/16 APE065 AA1.04 K/A is met.

Are there any instances that you can cite where an A/C will shut down automatically on high or adequate pressure? Thats what unloaders are for. The second question is not discriminating. drl 2/1016 52 H 2 X M S RUN sounds like it should work all the time. How about we change the second question to If an auto start signal is received, the Diesel VI compressors will / will not start and load if the START/WARM-UP/RUN switch is selected to the Warm-up position.

drl 3/2/16 Second revised question is SAT drl 3/2/16 APE077 AA2.01 53 H 2 M S K/A is met. drl 2/10/16 WE04 EK1.1 54 F 3 M S K/A is met. drl 2/10/16 WE05 EK2.1 K/A is met.

55 F 2 X B S I think that the applicants will know that there is an allowance in the procedure to have a blocked PORV.

So they would not choose 3. Could we change the

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only option for 3 PORVs to 1? drl 2/10/16 Revised question is SAT. drl 3/2/16 WE11 EK2.2 K/A is met.

This is not a very discerning question. Why would 56 H 1 X B S anyone state recirc is available on a loop with the recirc valve closed? The second question is ok. Drl 2/10/16 Revised question is SAT. drl 3/2/16 APE003 AK2.05 57 H 3 N S K/A is met. drl 2/10/16 WE13 EK1.2 K/A is met.

58 F 2 X N S Put 2 of the indications in the white zones. drl 2/10/16 Revised question is SAT. drl 3/2/16 APE037 AA1.07 59 H 3 N S K/A is met. drl 2/10/16 APE051 AK3.01 60 H 2 N S K/A is met. drl 2/10/16 APE059 AA2.05 61 F 3 B S K/A is met. drl 2/10/16 APE069 AK3.01 62 F 2 N S K/A is met. drl 2/10/16 EPE074 EK2.06 K/A is kind of met.

A better K/A match might be to give them a condition 63 F 2 X M S in which vacuum was lost (say a LOOP) and instead of asking question 2 ask if they will use dumps or SG PORVs to cooldown. drl 2/10/16 Revised question is SAT. drl 3/2/16 WE03 2.1.31 K/A is met.

The first question is acceptable if Operations requires their ROs to have this value memorized.

The second question appears trivial. Knowing the switch number does not seem to be of great 64 F 3 X B E importance. Perhaps knowing what position those switches should be in would be acceptable and still meet the K/A.

The other bank question that this was derived from looks pretty good. drl 2/10/16 Could we move 2NC-34A OR into the stem of the question to make discerning the differences in the

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only answers easier. Drl 3/2/16 Revised question is SAT. drl 3/2/16 WE15 EA2.2 65 H 2 B S K/A is met. drl 2/10/16 GEN2.1 2.1.2 K/A is met.

Could C be correct? It only says to borate to reduce 66 F 2 X B S power. Additionally, I dont see a prohibition from use of Emergency Boration. drl 2/10/16 After further review this question is SAT. drl 3/2/16 GEN2.1 2.1.36 67 F 3 B S K/A is met. drl 2/10/16 GEN2.1 2.1.45 68 F 2 B S K/A is met. drl 2/10/16 GEN2.2 2.2.1 K/A is met.

Change the words in question 2 from immediately and directly threatened is to in a reduced condition 69 F 2 X M S is. The two options would be YELLOW or RED.

With YELLOW as the correct answer. drl 2/10/16 Make all first answer Mode x and below. Instead of RED would ORANGE be more plausible? drl 3/2/16 Revised question is Sat.drl 3/3/16 GEN2.2 2.2.38 K/A is met.

The answers for question 2 needs to be re-written.

As written, it drives the applicant to within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 70 H 2 X M because it would be impossible to restore it to S

operable status immediately. So you will need to use the long version of the action as shown in the question that this was modified from. .drl 2/10/16 Revised question is SAT. drl 3/2/16 GEN2.3 2.3.13 71 F 2 B S K/A is met. drl 2/10/16 GEN2.3 2.3.4 72 H 2 B S K/A is met. drl 2/10/16 GEN2.4 2.4.11 73 H 3 N S K/A is met. drl 2/10/16 GEN2.4 2.4.25 K/A is met. drl If Operations agrees that the ROs are required to 74 F 2 M S memorize these setpoints, this question is SAT. drl 2/10/16 After further review, this question is SAT. drl 3/2/16

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only GEN2.4 2.4.31 K/A is met.

75 H 3 B S Potential overlap with question 64. drl 2/10/16 Revised Question is SAT. drl 3/2/16 SRO ONLY SYS012 A2.01 76 H 2 N S K/A is met. drl 2/11/16 SYS013 A2.06 77 H 3 B S K/A is met. drl 2/11/16 SYS061 2.4.31 K/A is met.

It seems that it would be logical to declare the pump inoperable when closing either valve. It would be nice to be able to test the TS knowledge that this surveillance is not applicable below 10% RTP.

However, procedurally you have to declare the pump inoperable no matter what the power level is. Could we change the power to *%, provide them with TS 78 H 3 X X B/M S 3.7.5.1 and change question 2 to read Based upon the actions taken to reduce the temperature of the check valve, TS 3.7.5.1 requires the U1 TD CA pump to be declared _____.?

The revised question looks SAT as written. We just need to verify that Operations would expect the SROs to know this without the TS as a reference. drl 3/3/16 After further review, question is SAT. drl 3/11/16 SYS076 2.2.44 79 H 2 M S K/A is met. drl 2/11/16 SYS078 A2.01 K/A is met.

Could we modify this one slightly? Add that the pressure is at 58 psig. For question 1 Ask which Enclosure should be entered 7 or 5. drl 2/11/16 Im pretty certain that the first question should ask 80 H 3 X B/M S what the MAXIMUM VI Header pressure which .

As pressure is lowering, we want to know what the first pressure is that it is required. Otherwise we would alays pick the lowest to get the minimum. drl 3/3/16 Revised question is SAT. drl 3/11/16 SYS014 2.2.25 K/A is almost met.

81 H 3 X N S Question 2 doesnt really hit the K/A mark as written.

Why not ask what the bases for the TS is. The

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only distractor could be fuel burnup distributions (TS 3.1.6). drl 2/11/16 Revised question is SAT. drl 3/3/16 SYS016 A2.02 K/A is met.

82 H 3 N S Does I&E place anything in TRIP? drl 2/11/16 After further review, this question is SAT. drl 3/3/16 SYS035 2.2.42 K/A is mostly met.

Although SLC item were formerly TS items, this particular item is bordering on minutia. How often will 83 H 3 X X M S the operators find themselves in this condition? This is not very operationally valid.

Perhaps TS 3.7.4 can be used instead.

Revised question is SAT. drl 3/3/16 APE015/017 2.4.45 K/A is met.

This is SAT as long as Operations agrees that their 84 H 2 N S SROs are required to know the bearing temperature setpoints. drl 2/11/16 After further review, this question is SAT. drl 3/3/16 APE027 AA2.15 85 F 2 N S K/A is met. drl 2/11/16 EPE029 EA2.09 86 H 3 B S K/A is met. drl 2/11/16 EPE038 2.2.22 87 H 2 N S K/A is met. drl 2/11/16 EPE011 2.2.38 88 F 2 B S K/A is met. drl 2/11/16 WE11 EA2.1 89 H 2 B S K/A is met. drl 2/11/16 APE005 AA2.04 K/A is met.

There is not a lot of difference between the two (as compared to the original question). Is this data take 90 H 3 X B S from the simulator during a stuck rod event? If so, it is fine. Otherwise, Id like to verify the data to make sure it is what the applicants would see. drl 2/12/16 Revised question is SAT. drl 3/3/16 APE024 2.1.7 K/A is met.

Second question is mildly related to the 1rst question.

91 H 2 X N S Think about deleting the second question and have the answers look something like:

A. NV from BAT after locally aligning 269 and

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only 267 because it is the preferred flow path.

B. NV from FWST because it is the preferred flow path.

C. NV from FWST because the BAT is inoperable.

D. NI from FWST because it is the preferred flowpath with an inoperable BAT.

drl 2/12/16 Revised question is SAT.drl 3/4/16 WE08 2.1.7 92 H 2 N S K/A is met. drl 2/12/16 WE16 EA2.2 K/A is met. I know this was previewed. But Im having trouble as to why one would choose to go 93 H 2 X B S to I.3. I see the words about confusing inventory and integrity. Perhaps we could give them some more cues that might at least consider I.3. drl 2/12/16 Revised question is SAT. drl 3/4/16 GEN2.1 2.1.35 K/A is met.

Question: Can a single individual really approve something like this? I want to ensure that there are no other procedural requirements out there that 94 F 3 X B S would require the Refueling SRO to get some kind of concurrence from another SRO that this is the right thing to do. If that requirement exists then C might be correct too. drl 2/12/16 Revised question is SAT. drl 3//16 GEN2.1 2.1.40 K/A is met.

The second question needs a little editing to ensure there are no subset issues. Part 20m is more 95 F 2 X B S restrictive than Part 100, therefore technically both answers are correct. So if you specify that the design basis for a total system failure , you will ensure only Part 100 is correct. drl 2/12/16 Revised question is SAT. drl 3//16 GEN2.2 2.2.21 K/A is met.

Answer 1 should be have or have not automatically tripped.

Based upon the way the question is written, it 96 H 3 X B S appears that the heaters are inoperable due to the malfunction and need to be returned to service within 7 days of the failure. You could go into TS 5.6.6 requirements. drl 2/12/16 Revised question is SAT. drl 3//16

3. Psychometric Flaws 4. Job Content Flaws 5. Other

1. 2.

6. Source 7. Status Q LOK LOD SR 8. Explanation Stem Cred. Job- #/ Back Q- (B/ M / N) (U /E /S)

(F/H) (1-5) Cues T/F Partial Minutia O Focus Dist Link Units ward K/A Only GEN2.2 2.2.6 97 F 2 N S K/A is met. drl 2/12/16 GEN2.3 2.3.12 98 F 2 N S K/A is met. drl 2/12/16 GEN2.3 2.3.14 99 H 2 M S K/A is met. drl 2/12/16 GEN2.4 2.4.44 K/A is met.

100 F 2 N S Change suspend to recommend suspending in question 2.drl 2/12/14 Revised question is SAT. drl 3//16

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Watts Bar Date of Exam: July 2076 Exam Level: RO

• SRQ S Item Description Initials a b c

1. Clean answer sheets copied before grading N/A

2. Answer key changes and question deletions justified and documented

3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail

5. All other failing examinations checked to ensure that grades are justified

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader Jc1i-

b. Facility Reviewer(*) N/A N/A

c. NRC Chief Examiner /9/tt

d. NRC Supervisor (*) PVL , LC L

(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

Personally ..entifiable Information Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from the enclo sure Tennessee Valley Authority Post Office Box 2000. Spring City Tennessee 37381-2000 June 30, 2016 10 CFR 55.5 10 CFR 5549 10 CFR 55.40(b)f3)

Ms. Catherine Haney. Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue. NE, Suite 1200 Atlanta, Georgia 30303-1257 Attention Mr Eugene Guthrie Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License No. NPF-90 and NPF-96 NRC Docket Nos 50-390 and 50-391

Subject:

Reactor and Senior Reactor Operator Initial Examination Application References. 1. NRC letter to TVA, Watts Bar Nuclear Plant Units 1 and 2 Notification of Licensed Operator Initial Examination 05000390/2016301, 05000390/2016301 dated February 19, 2016

2. TVA Letter to NRC, Reactor Operator Initial Examination s Waiver of Eligibility Requirements, dated May 15, 2014 The Nuclear Regulatory Commission (NRC) informed the Tenn essee Valley Authority (WA) in Reference 1 that the NRC will be administering the licensing examination operating tests during the week of July 18, with written examinations being administered during the week of July 25, 2016.

Reference 1 indicated that TVA should submit signed reactor operator and senior reactor operator license applications, medical certifications. and waiver requests, if any, at least 14 days before the first examination date. This letter submits Personal Qualification Statements (NRC Form 398), Certification of Medical Examinations (NRC Form 396) and waiver requests for the individuals scheduled to take the licensing examinations. provides the name, type of examination, and the docket number for the applicants provides the Personal Qualification Statements and Certification of Medical Examinations for the applicants.

Personally Identifiable Information Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from the enclosure U.S. Nuclear Regulatory Commission Page 2 June 30, 2016 This letter contains no regulatory commitments. This letter includes medical information that is considered by WA to be of a personal nature and, as such, is requested to be withheld from public disclosure in accordance with 10 CFR 2.390(a)f6).

If you have any questions, please contact Walter Smith, Operations Training Manager at (423) 365-3318 or Gordon Arent, Director of Watts Bar Site Licensing, at (423) 365-2004.

Respectfully, Paul Simmons Site Vice President Watts Bar Nuclear Plant

Enclosures:

1. Reactor Operator (RO) and Senior Reactor Operator (SRO) Applicants

2. Personal Qualification Statements (NRC Form 398) and Certification of Medical Examinations (NRC Form 396) cc: w/o Enclosures NRC Senior Resident Inspector Unit 1 NRC Senior Resident Inspector Unit 2

Personally Identifiable Information Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from the enclosure Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 July 29, 2016 10 CFR 55.5 10 CFR 55.49 10 CFR 55.40(b)

Ms. Catherine Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1 257 Attn: Mr. David Lanyi Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391

Subject:

Reactor and Senior Reactor Operator Initial Examination Documentation

Reference:

Nuclear Regulatory Commissions (NRCs) letter to the Tennessee Valley Authority (TVA) dated February 19, 2016, Watts Bar Nuclear Plant Units 1 and 2 Notification of Licensed Operator Initial Examination 05000390/2016301, 05000391/2016301 As agreed to in the Reference, the Tennessee Valley Authority (WA) administered a written examination to a group of licensed operator applicants on July 27, 2016. In accordance with NUREG 1021, Operator Licensing Examination Standards for Power Reactors, Examination Standard (ES) 501, Initial Post-Examination Activities, TVA is submitting the following enclosures.

Enclosure 1 The ungraded written examinations (i.e., each applicants original answer and examination cover sheets).

Enclosure 2 - A clean copy of each applicants answer sheet.

Enclosure 3 The master examination(s) and answer key(s), annotated to indicate any changes made while administering and grading the examination(s).

Personally Identifiable Information -Withhold Under JO CFR 2.390 This letter is decontrolled when separated from the enclosure U.S. Nuclear Regulatory Commission Page 2 July 29, 2016 Enclosure 4 Any questions asked by and answers given to the applicants during the written examination (ES-402).

Enclosure 5 Any substantive comments made by the applicants after the written examination, with an explanation concerning why the comment was accepted or rejected (ES-402).

Enclosure 6 The seating chart for the written examination (ES-402).

Enclosure 7 The results of any performance analysis that was performed for the written examination, with recommended substantive changes (ES-403).

Enclosure 8 Original Form(s) ES-201-3, Examination Security Agreement, with a pre- and post-examination signature by every individual who had detailed knowledge of any part of the operating tests or written examination before they were administered.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 55.49, and NUREG-1 021, appropriate measures have been taken to ensure examination integrity and security. Accordingly, the enclosures were forwarded by overnight mail to Mr. David Lanyi, NRC Region II on July 29, 2016.

Because of the administratively confidential nature of the enclosed material, it is requested that the information forwarded to Mr. David Lanyi and contained in Enclosures 1 through 8 be withheld from public disclosure until the examinations are completed.

This letter contains no new regulatory commitments. Should you have questions concerning this submittal, please contact Walt Smith, Operations Training Manager, at (423) 365-3318 or Gordon Arent, Director of Watts Bar Site Licensing, at (423) 365-2004.

Sincerely, CFo Paul Simmons Site Vice President Watts Bar Nuclear Plant

Personally Identifiable Information Withhold Under 10 CFR 2.390 This letter is decontrolled when separated from the enclosure U. S. Nuclear Regulatory Commission Page 3 July 29, 2016

Enclosures:

cc: (wlo Enclosures):

Chief, NRC Operator Licensing Branch NRC Senior Resident Inspector NRC Project Manager