ML17181A401

Exam Administrative Items 2C - Delay Release

ML17181A401
Person / Time
Site:	Brunswick
Issue date:	06/30/2017
From:	NRC/RGN-II
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Download: ML17181A401 (53)

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ES-207 Examination Preparation Checklist Form ES-201-J Facility: _Brunswick Date of Examination: 12/16 Developed by: Written: Facility NRC II Operating Facility NRC LI Target . .

Task Description (Reference) Chief ate Examiners Initials

-180 1. Examination administration date confirmed (Cia; C.2.a and b) fbI 1L

(

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

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

-150 4. Corporate notification letter sent (C.2.d) YL /_j 1..c

[-1201 5. Reference material due (C.1.e; C.3.c; Attachment 3) I.St ?IcI,J

(-90] 6. Integrated examinaon 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-i/2, ES-401-3, ES-401N-3, .0 ES-401-4, and ES-401N-4, as applicable (C.1.e and f; C.3.d)

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

{-6o) 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, t-J - tzç /

ES-301-1, 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)

I I

-30 10. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202) . I t2Zf

-21 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) 5L c YI LC

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

-14 13. Final license applications due and Form ES-201 -4 prepared (C.i .1; C.2.i; ES-202) ..ts Ci //ft 4

-14 14. Written examinations and operating tests approved by NRC supervisor fC.2.i; C.3.h) icl P tdl

-7 15. Facility licensee management queried regarding the licensees views on the 1ç- tj examination. (C.2j) L

-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)

P I L1 IIL

-7 17. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k) j3 e!i.2 /Ii

-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 only] (Does not apply) to examinations prepared by the NRC.

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Brunswick Date of Examination: December, 2016 Initials Item Task Description

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

R b. Assess whether the outline was systematically and randomly prepared in accordance with

.. Section D. 1 of ES-401 or ES-401 N and whether all K/A categories are appropriately sampled.

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

N

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

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

G E 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.

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

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

f.__Assess_whether_the_exam_fits_the_appropriate_job_level_(RD_or_SRO).

pate/h a Author

b. Facility Reviewer (*) A ._

c. NRC Chief Examiner (#) I

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

Not applicable for NRC-prepared examination outlines.

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Date of Examination:

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-401 N.

b

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

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

N

/

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

I *4_

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 0)

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 A least one new or significantly modified scenario, that no scenarios are duplicated from the

-r 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) - 7 L K (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of altemate 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 U (2) at least one task is new or significantly modified 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.

E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 44 j 0

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. 44 t:::.

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

)

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

4 -% 1J_

f.__Assess_whether_the_exam_fits_the_appropriate job_level_(RO_or_SRO).

Pnted Name/Signaiije .-..

Date

a. Author Zic,/ i5t7/i.

b. Facility Reviewer (*)

c.

d.

NRCChiefExaminer(#)

NRC Supervisor i

C c-- 3

7. 6

)-.-k ---.

5 rfY7f 6 1

ii I7J7.

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: Brunswick Date of Examination: 11/28/2016 Examination Level: RO SRO Operating Test Number: Final Administrative Topic (see Note) Type Describe activity to be performed Code*

Conduct of Operations #1 R, N 2.1.25 Perform SJAE Off-Gas Radiation (RO, then SRO) Monitors Channel Check Calculation Conduct of Operations #2 R, D 2.1.07 Determine Primary Containment Water (All) Level and Evaluate PCPL-A.

Equipment Control R, N 2.2.12 Calculate Drywell Leakage Rate.

(RO, then SRO)

Radiation Control R, P,D 2.3.07 Determine Stay Time Limitations in (All) High Radiation Areas.

Emergency Plan R, M 2.4.29 Classify An Emergency per PEP-02.1.

(SRO Only)

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)

Conduct of Operations #1 Perform SJAE Off-Gas Radiation Monitors Channel Check Calculation RO, then SRO 2.01 .25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9/4.2 This is a new JPM developed for the 2016 NRC Initial Exam. The examinee will perform item 10$, SJAE Off-Gas Radiation Monitors Channel Check, of 201-03.2, Reactor Operator Daily Surveillance Report, and state the status of the channel check. Then the SRO examinees will determine any required actions.

Conduct of Operations #2 Determine Primary Containment Water Level and Evaluate PCPL-A All 2.01.07 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.4/4.7 This is a bank JPM. The examinee will determine Primary Containment water level per EOP-01-UG, Attachment 11. Determine the current region of operation (Safe/Unsafe) on Primary Containment Pressure Limit A (PCPL-A).

Equipment Control Calculate Drywell Leakage Rate RO, then SRO 2.2.12 Knowledge of surveillance procedures 3.7/4.1 This is a new JPM developed for the 2016 NRC Initial Exam. The examinee will determine the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leak rate for the equipment and floor drains, and the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> total leak rate to the drywell lAW Attachment 1, Drywell Leakage Calculation, of 201-03.2, Reactor Operator Daily Surveillance Report, for Sunday Nightshift at time 2000.. Then the SRO examinees will determine if TS LCO 3.4.4 is met and if it is not met identify the latest time the Unit is required to be in MODE 3.

Radiation Control Determine Stay Time Limitations in High Radiation Areas.

All 2.3.07 Ability to comply with radiation work permit requirements during normal and abnormal conditions.

3.5/3.6 This was a randomly selected JPM that was on the 2015 NRC exam. The examinee will determine the total dose accumulated for both workers and determine if any Brunswick administrative dose limitations will be exceeded.

Emergency Plan Classify An Emergency per PEP-02.1 SRO Only 2.4.29 Knowledge of the Emergency Plan 3.1/4.4 This is a modified JPM that was used on the 2012 NRC Initial Exam. Changed EAL from Site Area Emergency to an Alert. The SRO examinees will determine the highest required classification and its EAL Identifier. This JPM is time critical (15 minutes).

ES-301 Control RoomIl n-Plant Systems Outline Form ES-301-2 Facility: Brunswick Date of Examination: 11/28/2016 Exam Level: RO SRO-l SRO-U Operating Test No.: Final Control Room Systems:8 for RO; 7 for SRO-l; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. Reset Recirc Pump Runback, Both Recirc Pumps trip 5, N, A 1

b. Mechanical Trip Valve Oil Trip Test S, N 4

c. Operate the H2102 Monitor using the Hard Card. S, D, EN 5 U. Reduce RPV Water Level using RWCU to Radwaste S, M, A 2

e. Vent Drywell w/ Stack Rad Mon >50% increase S, D, A 9

f. Shifting Caswell Beach Lube Water Pumps From The RTGB 5, N 8

g. Substitute Control Rod Position 5, D, L 7

h. RO ONLY Test the Main Steam Isolation Valves S, P 3 In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

i. LEP-Ol, Heater Drain Pumps R, D, E, L 2

j. LEP-05, SRV operation from RSDP R, N, E, L 7

k. Rack in E6 Crosstie Breaker D, A, E 6 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-l / SRO-U A)ltemate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant 1 / 1 I 1 (EN)gineered safety feature 1 I 1 / 1 (control room system)

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

(R)CA (S)imulator

a. Reset Recirc Pump Runback with both Recirc Pumps Tripping 202002 A2.01 Ability to predict the impacts of recirculation pump trip and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. 3.4/3.4 RO/ISRO/USRO This is a simulator alternate path JPM that will have the examinees resetting a Recirc Pump runback signal. When the runback is reset both recirc pumps will trip, this will require an immediate operator action to insert a manual reactor scram. This JPM is a new alternate path JPM.

b. Mechanical Trip Valve Oil Trip Test 245000 A3.01 Ability to manually operate and/or monitor in the control room:

Turbine Trip. 3.6/3.6 RO/ISRO/USRO This is a new simulator JPM that will require the examinee to perform the Mechanical Trip Valve Oil Trip Test.

c. Operate The Hydrogen And Oxygen Monitor Using The Hard Card 223001 A4.04/.05 Ability to manually operate and/or monitor containment drywell hydrogen/oxygen concentrations. 3.5/3.6 3.6/3.6 RO/ISRO/USRO This is a simulator JPM that will requite the examinee to start up and align the containment H2&02 monitors pet the Hard Card.

Combustible Gas Monitoring is an Engineered Safety Feature lAW USFAR 6.2.5.2.2.

d. Reduce RPV Water Level Using RWCU To Radwaste 204000 A4.08 Ability to manually operate and/or monitor in the control room:

Reactor Water Level. 3.4/3.4 RO/ISRO This is a modified alternate path simulator JPM that will require the examinee to reduce RPV water level using RWCU drain path to Radwaste. While lowering level, the RWCU Reject FCV will fail to close automatically on inadequate discharge pressure .The examinee will have to close the FCV.

e. Vent Drywell w/ Stack Rad Mon >50% increase 261000 A4.04 Ability to manually operate and/or monitor Primary Containment Pressure. 3.3/3.4 RO/ISRO This is a banked simulator JPM that will require the examinee to vent the Drywell via Standby Gas Treatment. This JPM is alternate path in that Main Stack Rad will rise requiring the examinee to isolate the system.

f. Shifting Caswell Beach Lube Water Pumps From The RTGB 400000 A4.01 Ability to manually operate and/or monitor in the control room: CCW indications and control. 3.1/3.0 RO/ISRO This is a new simulator JPM that will require the examinee to perform shift Caswell Beach Lube Water Pumps From The RTGB.

g. Substitute Control Rod Position 201006 A4.06 Ability to manually operate and/or monitor in the control room:

Selected rod position indication. 3.2/3.2 RO/ISRO This is a banked JPM that will requite the examinee to substitute in the Rod Worth Minimizer the indicated rod position.

h. Test the Main Steam Isolation Valves 239001 A4.01 Ability to manually operate and/or monitor the MSIVs in the Control Room. 4.2/4.0 RO This is a new JPM that will require the examinee to perform post-maintenance testing of a MSIV. This JPM was randomly selected from the previous exam (2015).

i. LEP-Ol, Heater Drain Pumps 295031 EA1 .08 Ability to operate alternate injection system systems as they apply to Reactor Water Level Low. 3.8/3.9 RO/ISRO This is a banked in-plant JPM that will require the examinee to simulate the Auxiliary Operator actions for Alternate Coolant Injection, Heater Drain Pump Injection per OEOP-01-LEP-01. This JPM is performed in the RCA.

j. LEP-05, SRV operation from RSDP 295016 Ml 08 Ability to operate and/or monitor Reactor Pressure as it applies to Control Room Abandonment. 4.0/4.0 RO/ISRO/USRO This is a new in-plant JPM that will require the examinee to simulate the actions associated with performing the field actions for pressure control from the RSDP (Remote Shutdown Panel)

k. Rack in E6 Crosstie Breaker 295003 AA1 .01 Ability to operate and/or monitor AC Electrical Distribution System as it applies to a partial or complete loss of A.C. power. 3.7/3.8 RO/ISRO/USRO This is a banked in-plant alternate path JPM that will require the examinee to simulate manually racking in the crosstie breaker. The charging springs on the breaker will not automatically re-charge and will have to be manually charged.

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: ci ck Date of Examination: o/ Operating Test Number O( C3)

1. General Criteria Initials a b c#

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

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

c. The operating test stiall not duplicate items from the applicants audit test(s). (see Section 0.1 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 tessthan-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:

lID 7 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 oudines (Forms ES-301 4 and 2) have not caused the test to deviate from any of the acceptance ,0 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 301-4andacopytsattached. 7 Printed Name I Signature Date

a. Author a,v\

b. Facility Reviewer(*) C Ce, 0 (, jer

c. NRCChieFExamIner(#) L&,y,.u: ii/t ,/tt

d. NRC Supervisor \

NOTE;

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

1. Independent NRC reviewer Initial items in Column c; chief examiner concurrence requited.

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Brunswick Date of Exam: 11/28/16 Scenario Numbers 1 / 2 / 3 I 4 / 5 Operating Test No.: Final QUALITATIVE ATTRIBUTES lnials a b* c#

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

2. The scenarios consist mostly of related events.

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.

J*_

5. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives. / 7 }Y-

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

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

Cues are given.

7. The simulator modeling is not altered. ,%. 7 -

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. / pt.

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).

11. 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.) I 7

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). fr IJ

13. The level of difficulty is appropriate to support licensing decisions for each crew position. / 7 D-Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- --

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

2. Abnormalevents(2-4) 4/2/4/4/2

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

4. EOPs entered/requiring substantive actions (12) 2 I 2 I 2 I 2 I 2  %

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

6. EOPbasedCriticaltasks(23) 2/3/2/2/2 Y 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: Brunswick Nuclear Plant Date of Exam: 11/ 28/201 6 Operating Test No.: Final A E Scenarios P V P E 2 3 4 5 T M j CREW POSITION CREW POSITION CREW POSITION CREW POSITION I C T A T S A B S A B A S A B S A B M N Y R T 0 R T 0 R T 0 R T o L u I P 0 C P 0 C P 0 C P 0 C P M(*)

E RX 1 6 2110 NOR 2 1 2111 I/C 3,4,5,6, 5,6,7 2a,4,8 12 4 4 2 SRO-If MAJ 7 7,8 7,8 5 2 2 1 TS 3,5 2022 RX 1 4 2110 NOR 1 1 2 1 1 1 3,5,8 2,3,5,6,7 4,6,7 12 4 4 2 SRO-12 MAJ 7 7,8 7,8 5 2 2 1 TS 3,5 2022 RX 4 6 2110 NOR 2 1 SRO 13 I/C 4,6,9 2,3,8 2,2a,3, 13 4 4 2 4,5,7,8 MAJ 7 7,8 7,8 5 2 2 1 IS 2,4 2022 RX 1 6 2110 NOR 2 1 2 1 1 1 I/C 3,4,5,6, 5,6,7 2a,4,8 12 4 4 2 SRO-14 MAJ 7 7,8 7,8 5 2 2 1 TS 3,5 2022 RX 1 4 2110 NOR 1 1 2 1 1 1 I/C 3,5,8 2,3,5,6,7 4,6,7 12 4 4 2 SRO-15 MAJ 7 7,8 7,8 5 2 2 1 TS 3,5 2022 RX 4 6 2110 NOR 2 1 2 1 1 1 I/C 4,6,9 2,3,8 2,2a,3, 13 4 4 2 SRO-16 MAJ 7 7,8 7,8 5 2 2 1 IS 2,4 2022

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Brunswick Nuclear Plant Date of Exam: 11/ 28/2016 Operating Test No.: Final A E Scenarios P V P E 2 3 4 5 T M CREW POSITION CREW POSITION CREW POSITION CREW POSITION C S B T A S A B S A B S A B I A T A R T 0 R T 0 R T 0 R T o M N Y 0 C P 0 C P 0 C P 0 C P L u T P M(*)

E RX 1 6 2110 NOR 2 1 2111 SRO-17 I/C 3,4,5,6 5,6,7 2a,4,8 12 4 4 2 MA] 7 7,8 7,8 5 2 2 1 TS 3,5 2022 RX 1 4 2 110 NOR 1 1 2111 I/C 3,5,8 2,3,5,6,7 4,6,7 12 4 4 2 SRO-18 MA] 7 7,8 7,8 5 2 2 1 TS 3,5 2022 RX 6 2 2110 NOR 1 1 1 1 1 SRO 19 I/C 2,2a,3, 3,5,7 10 4 4 2 4,5,7,8 MA] 7,8 7,8 4 2 2 1 TS 2,4 2022 RX 2 1 110 NOR 1 1 111 SRO-U1 I/C 3,4,5,6, 5 4 4 2 MA] 7,8 2 2 2 1 TS 5,6 2022 RX 4 1110 NOR 2 1 111 RO-1 I/C 4,6,9 2,3,8 6 4 4 2 MA] 7 7,8 3 2 2 1 TS 0022

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-l) 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-l 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-l applicants in either the ATC or SOP position to best evaluate the SRO-l in manipulating plant controls.

ES-301 Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: 1 1/28/16 Operating Test No.: Final APPLICANTS RO-l RO El RO El RO El SRO-I El SRO-17 I SRO-18 I SRO-19 I SRO-U El SRO-U El SRO-U El SRO-U El Competencies SCENARIO SCENARIO SCENARIO SCENARIO 2345234523452345 Interpret/Diagnose 4,6, 2,3, 3- 5,6, 2a, 3,5, 2- 4,6, 2-8 2,3, Events and Conditions 7 48 9 7 2,3, 7,8, 8 7,8 5,7, 5,7, 9 8 8

Comply With and 2,4, 2,3, all 1,5, 2a, 1,3, all 1,4, all 2,3, Use Procedures (1) 6,7 4,7, 6,7, 2,3, 5,7, 6,7, 5,7, 8 8 5,7, 8,9 8 8 8

Operate Control 2,4, 2,3, nJ 1,5, 2a, 1,3, nI 1,4, n/a 2,3, Boards (2) 6,7 4,7, a 6,7, 2,3, 5,7, a 6,7, 5,7, 8 8 5,7, 8,9 8 8 8

Communicate all all all all all all all all all all and Interact Demonstrate n/a n]a all n/a n/a n/a all n/a all n/a Supervisory Ability (3)

Comply With and n/a n/a 3, n/a n/a n/a 3, n/a 2,3 n/a Use Tech. Specs. (3) 5 Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

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-3Q3-1 and ES-303-3.

ES-301 Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: 11/28/16 Operating Test No.: Final APPLICANTS RD El RO El RD El RD El SRO-l El SRO-l1 I SRO-12 I SRO-l3 I 3RD-Ui I 3RD-U El 3RD-U El 3RD-U El Competencies SCENARIO SCENARIO SCENARIO SCENARIO 2345234523452345 Interpret/Diagnose 2-8 3- 5,6, 2a, 3,5, 2- 4,6, 4, 2,3, 2-8 Events and Conditions 7 2,3, 7,8, 8 7,8 6, 4,8 5,7, 9 7 8

Comply With and all all 1,5, 2a, 1,3, all 1,4, 2, 2,3, all Use Procedures (1) 6,7, 2,3, 5,7, 6,7, 4, 4,7, 8 5,7, 8,9 8 6, 8 8 7 Operate Control n/a n/ 1,5, 2a, 1,3, n/ 1,4, 2, 2,3, n/a Boards (2) a 6,7, 2,3, 5,7, a 6,7, 4, 4,7, 8 5,7, 8,9 8 6, 8 8 7 Communicate all all all all all all all all all all and Interact Demonstrate alt all n/a n/a n/a all n/a n/ n/a all Supervisory Ability (3) a Comply With and 5,6 3, n/a n/a n/a 3, n/a n/ n/a 2,3 Use Tech. Specs. (3) a Notes:

(1) Includes Technical Specification compliance for an RD.

(2) Optional for an S RD-U.

(3) Only applicable to SROs.

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-301 Competencies Checklist Form ES-301-6

[Iity: Brunswick Date of Examination: 11/28/16 Operating Test No.: Final APPLI CANTS RO RO D RO D RO SRO-l D SRO-14

• SRO-15

• SRO-16 U SRO-U D SRO-U D SRO-U D SRO-U LI Competencies SCENARIO SCENARIO SCENARIO SCENARIO 2345234523452345 Interpret/Diagnose 3- 5,6, 2a, 3,5, 2- 4,6, 4, 2,3, 2-8 Events and Conditions 7 2,3, 7,8, $ 7,8 6, 4,8 5,7, 9 7 8

Comply With and all 1,5, 2a, 1,3, all 1,4, 2, 2,3, all Use Procedures (1) 6,7, 2,3, 5,7, 6,7, 4, 4,7, 8 5,7, 8,9 8 6, 8 8 7 Operate Control n/ 1,5. 2a, 1,3, n/ 1,4, 2, 2,3, n/a Boards (2) a 6,7, 2,3, 5,7, a 6,7, 4, 4,7, 8 5,7, 8,9 8 6, 8 8 7 Communicate all all all all all all all all all and Interact Demonstrate all n/a n/a n/a all n/a n/ n/a all Supervisory Ability (3) a Comply With and 3, n/a n/a n/a 3, n/a n/ n/a 2,3 Use Tech. Specs. (3) 5 5 a Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

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 BWR Examination Outline Form ES-401-1 Facility: Brunswick Tier Group Date of Exam: December, 2016 1

RD K/A Category Points SRO-Only Points K K K K K[K A A1A A G* A2 G* Total 1 2 3 4 1 J3 4 Total I 1 3 3 4 4 3 3 20 4 3 7 Emergency& N/A N/A 2 1 1 1 2 1 1 7 2 1 3 Abnormal Plant Evolutions Tier Totals 4 4 5 6 4 4 27 6 4 10 2 1 32323223222 26 3 2 5 Plant Systems 2 11111211111 1 12 012 1 3 Tier Totals f

4 3 4 3 4 4 3 4 13 3 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 2 2 1 2 Note: 1 Ensure that at least two topics from every applicabie K/A category are sampled within each tier of the RD 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 RD 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 RD 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

ES4OI 2 Form ES4OI-1 ES-401 BNR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

EIAPE # / Name I Safety Function K K K A A2 G* K/A Topic(s) lR #

1 231 G2.2.12; Knowledge of surveillance 295001 Partial or Complete Loss of Forced X procedures.

Core Flow Circulation I 1 & 4 AA2.05; Ability to determine and/or interpret x the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:_Jet_pump_operability.

AK1 .03; Knowledge of the operational 295003 Partial or Complete Loss of AC / 6 X implications of the following concepts as they 2.9 apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Under voltage/degraded voltage effects on electrical loads.

AK2.01; Knowledge of the interrelations 295004 Partial or Total Loss of DC Pwr/ 6 X between PARTIAL OR COMPLETE LOSS OF 3.1 D.C. POWER and the following: Battery charger.

AK3.04; Knowledge of the reasons for the 295005 Main Turbine Generator Trip I 3 X following responses as they apply to MAIN 3.2 TURBINE GENERATOR TRIP: Main generator trip.

AA1 .06; Ability to operate and/or monitor the 295006 SCRAM / 1 X following as they apply to SCRAM: CRD 35 hydraulic system.

AK3.03; Knowledge of the reasons for the 295016 Control Room Abandonment! 7 X following responses as they apply to CONTROL ROOM ABANDONMENT:

Disabling control room controls.

AK2.02; Knowledge of the interrelations 295018 Partial or Total Loss of CCW / 8 X between PARTIAL OR COMPLETE LOSS OF 3.4 COMPONENT COOLING WATER and the following: Plant operations.

AA2.02; Ability to determine and/or interpret 295019 Partial or Total Loss of Inst. Air! 8 X the following as they apply to PARTIAL OR 3.6 COMPLETE LOSS OF INSTRUMENT AIR:

Status of safety-related instrument air system loads.

AK2.05; Knowledge of the interrelations 295021 Loss of Shutdown Cooling / 4 X between LOSS OF SHUTDOWN COOLING 2.5 and the following: Fuel pool cooling and cleanup system.

A?\203; Ability to determine and/or interpret the following as they apply to LOSS OF X

SHUTDOWN COOLING : Reactor water level.

AA1 .04; Ability to operate and/or monitor the 295023 Refueling Acc / 8 X following as they apply to REFUELING 34 ACCIDENTS: Radiation monitoring equipment.

G2.2.25, Knowledge of the bases in Technical X Specifications for limiting conditions for 4 2 operations and safety limits.

EA1 .05; Ability to operate and/or monitor the 295024 High Drywell Pressure / 5 X following as they apply to HIGH DRYWELL 3.9 PRESSURE: RPS.

EK3.02; Knowledge of the reasons for the 295025 High Reactor Pressure /3 X following responses as they apply to HIGH 39 REACTOR PRESSURE: Recirculation pump trip: Plant-Specific. =

G2.4.50; Ability to verify system alarm 295026 Suppression Pool High Water X setpoints and operate controls identified in the 2.7 Temp. / 5 alarm response manual.

G2.1.23; Ability to perform specific system and X integrated plant procedures during all modes of

.. plant operation.

295027 High Containment Temperature I 5 EA2.01 Ability to determine and/or interpret 295028 High Drywell Temperature / 5 X the following as they apply to HIGH DRYWELL 4.0 TEMPERATURE: Drywell temperature.

G2.4.50; Ability to verify system alarm 295030 Low Suppression Pool Wtr LVI /5 X setpoints and operate controls identified in the 4.2 alarm response manual.

EKJ.03; Knowledge of the operational 295031 Reactor Low Water Level / 2 X implications of the following concepts as they 37 apply to REACTOR LOW WATER LEVEL:

Water level effects on reactor power.

EK1 .03; Knowledge of the operational 295037 SCRAM Condition Present and X implications of the following concepts as they 4.2 Reactor Power Above APRM Downscale or apply to SCRAM CONDITION PRESENT AND Unknown /1 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Boron effects on reactor power (SBLC).

02.421; Knowledge of the parameters 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 EA1 .01; Ability to operate and/or monitor the 295038 High Off-site Release Rate /9 X following as they apply to HIGH OFF-SITE 3.9 RELEASE RATE: Stack-gas monitoring system: Plant-Specific.

EA2.01: Ability to determine and/or interpret the following as they apply to 1-1101-1 OFF-SITE X RELEASE RATE: tOff-site.

AK3.04; Knowledge of the reasons for the 600000 Plant Fire On Site / 8 X following responses as they apply to PLANT 2.8 FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site.

AA2.07; Ability to determine and interpret the following as they apply to PLANT FIRE ON X SITE: Whether malfunction is due to common 3 mode electrical failures.

M2.03; Ability to determine and/or interpret 700000 Generator Voltage and Electric Grid X the following as they apply to GENERATOR 35 Disturbances / 6 VOLTAGE AND ELECTRIC GRID DISTURBANCES: Generator current outside the capability curve.

K/A Category Totals: 3 3 4 4 3/4 3/3 Group Point Total: 20/7

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 #

1 231 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure! 3 295008 High Reactor Water Level / 2 AK2.04; Knowledge of the interrelations 295009 Low Reactor Water Level / 2 X between LOW REACTOR WATER LEVEL 2.6 and the following: Reactor water cleanup.

295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. /5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM! 1 X 02.4.31; Knowledge of annunciator alarms, 4.1 indications, or response procedures.

AA2.03; Ability to determine and/or interpret 295017 High Off-site Release Rate / 9 X the following as they apply to HIGH OFF- 3.1 SITE RELEASE RATE: tRadiation levels:

Plant-Specific.

AA1 .02; Ability to operate and/or monitor the 295020 Inadvertent Cont. Isolation I5&7 X following as they apply to INADVERTENT 3.2 CONTAINMENT ISOLATION: Drywell ventilation/cooling system.

295022 Loss of CR0 Pumps I 1 X AA2.02; Ability to determine and/or interpret 3.4 the following as they apply to LOSS OF CRD PUMPS : CRD system status EA1 .01; Ability to operate and/or monitor the 295029 High Suppression Pool Wtr LVI / 5 X following as they apply to HIGH 34 SUPPRESSION POOL WATER LEVEL:

HPCI: Plant-Specific.

EK3.01; Knowledge of the reasons for the 295032 High Secondary Containment Area X following responses as they apply to HIGH 3.5 Temperature /5 SECONDARY CONTAINMENT AREA TEMPERATURE: Emergency/normal depressurization.

295033 High Secondary Containment Area Radiation Levels / 9 G2.4.8; Knowledge of how abnormal 295034 Secondary Containment X operating procedures are used in conjunction 3.8 Ventilation High Radiation / 9 with EOPs.

EA2.01; Ability to determine and/or inteFpret 295035 Secondary Containment High X the following as they apply to SECONDARY 3.9 Differential Pressure / 5 CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment pressure: Plant-Specific.

EK1.02; Knowledge of the operational 295036 Secondary Containment High X implications of the following concepts as they 2.6 Sump!Area Water Level / 5 apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL:

Electrical ground! circuit malfunction.

500000 High CTMT Hydrogen Conc. I 5 =

K/A Category Point Totals: ]1 1 1 2 1/2 1/1 Group Point Total: 7/3

ES-401 4 Form ES-401-1 ES-401 B\NR Examination Outline Form ES-401-l

= Pnt Systems- ]ler2/Groupl (RO/SRO)

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

234561 34 A4.04; Ability to manually 203000 RHR/LPCI: Injection Mode X operate and/or monitor in the 3.6 control room: Heat exchanger cooling flow.

K5.03; Knowledge of the 205000 Shutdown Cooling X 2.8 operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Heat removal mechanisms.

Kilo; Knowledge of the physical 206000 HPCI X 34 connections and/or cause/effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following: Condensate storage and transfer system.

207000 Isolation (Emergency)

Condenser K3.03; Knowledge of the effect 209001 LPCS X 2.9 that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following: Emergency generators.

X G2435; Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

209002 HPCS Ki.01; Knowledge of the physical 211000 SLC X 3.0 connections and/or cause/effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following: Core spray line break detection: Plant-Specific.

K2.01; Knowledge of electrical 212000 RPS X 3.2 power supplies to the following:

RPS motor-generator sets.

G2244: Ability to interpret X control room indfcations to verify the status and I operation of a system, and understand how operator actions and directives atfecl plant and system conditions

A2.06; Ability to (a) predict the 215003 IRM x impacts of the following on 3.0 the INTERMEDIATE RANGE MONITOR fIRM) SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty range switch.

K6.04; Knowledge of the effect x that a loss or malfunction of the following will have on the 4.0 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM:

Detectors.

K5.03; Knowledge of the 215004 Source Range Monitor X operational implications of the 2.8 following concepts as they apply to SOURCE RANGE MONITOR (SRM) SYSTEM: Changing detector position.

K2.02; Knowledge of electrical 215005 APRM / LPRM X power supplies to the following: 2.6 APRM channels.

K5.04; Knowledge of the X

operational implications of the 2.9 following concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

LPRM detector location and core symmetry.

Al .01 Ability to predict and/or 217000 RCIC X monitor changes in parameters 37 associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: RCIC flow.

K1.03; Knowledge of the physical 218000 ADS X connections and/or cause/effect 3.7 relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Nuclear boiler instrument system.

x K3.0l; Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following:

Restoration of reactor water level after a break that does not depressurize the reactor when required.

A1.Ol; Ability to predict and/or 223002 PCIS/Nuclear Steam X monitor changes in parameters 35 Supply Shutoff associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including: System indicating lights and alarms.

239002 SRVs K4.03; Knowledge of X RELIEF/SAFETY VALVES 3.1 design feature(s) and/or interlocks which provide for the following: Prevents siphoning of water into SRV discharge piping and limits loads on subsequent actuation of SRVs.

X A2.01; Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES : anti (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ot those abnormal conditions or operations: Stuck ooen vacuum breakers.

A3.08; Ability to monitor 259002 Reactor Water Level X automatic operations of the 40 Control REACTOR WATER LEVEL CONTROL SYSTEM including:

FWCI system initiation: FWCI.

261000 SGTS A4.02; Ability to manually X operate and/or monitor in the 3.1 control room: Suction valves.

X A2.09; Ability to (a) predict the impacls of the following on the STANDBY GAS TREATMENT 2.6 SYSTEM and (b) based on those predictions. use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Plant air system failure.

262001 AC Electrical Distribution X G2.2.40; Ability to apply 3.4 Technical Specifications for a system.

x A2.01; Ability to (a) predict the impacts of the following on the AC. ELECTRICAL DISTRIBUTION : and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine/generator trip 262002 UPS (AC/DC)

A3.01 Ability to monitor X automatic operations of the 2.8 UNINTERRUPTABLE POWER SUPPLY (AC/D.C.) including:

Transfer from preferred to alternate source.

G2.2.37; Ability to determine 263000 DC Electrical Distribution X operability and/or availability of 3.6 safety related equipment.

K6.03; Knowledge of the effect 264000 EDGs X that a loss or malfunction of the 35 following will have on the EMERGENCY GENERATORS (DIESEUJET):Lubeoilpumps. =

A2.01 Ability to (a) predict the 300000 Instrument Air X impacts of the following on the 2.9 INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions.

K3.01 Knowledge of the effect that a loss or malfunction of the 27 Containment air system.

A2.01; Ability to (a) predict the 400000 Component Cooling Water X impacts of the following on the 33 CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Loss of CCW pump.

X K4.01; Knowledge of CCWS design feature(s) and or interlocks which provide for the following: Automatic start of standby pump.

[ K/A Category Point Totals: 3 2 3 j2 2 2/2 Group Point Total:

ES4OI 5 Form ES4OI-1 ES4O1 BWR Examination Outline Form ES-401-1

Plant Systems -Tier 2/Group 2 (RO!SRO) =

System#/Name K K K K K K A A2 A A G KJATopic(s) 201001 CRD Hydraulic K6.02; Knowledge of the effect that a X 3.0 loss or malfunction of the following will have on the CONTROL ROD DRIVE HYDRAULIC System:

Condensate storage tanks.

201002 RMCS 201003 Control Rod and Drive G2.4.49; Ability to perform without X

Mechanism reference to procedures those actions that require immediate operation of system components and controls.

201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control K6.03; Knowledge of the effect that a X 2.8 loss or malfunction of the following will have on the RECIRCULATION FLOW CONTROL SYSTEM:

Recirculation system.

204000 RWCU 214000 RPIS 21 5001 Traversing In-Core Probe X G2.2.44: Ability to interpret control 4.4 room indications to veiify the status and operation of a system. and understand how operator actions and directives affect plant and system conditions.

215002 RBM Ki .02; Knowledge of the physical X 32 connections and/or cause/effect relationships between ROD BLOCK MONITOR SYSTEM and the following: LPRM.

216000 Nuclear Boiler Inst. A2.1 1 Ability to (a) predict the X 3.2 impacts of the following on the NUCLEAR BOILER INSTRUMENTATION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Heatup or cooldown of the reactor vessel.

219000 RHR/LPCI: Torus/Pool Cooling A2.12; Ability to (a) predict the X impacts of the following on the 3 1 Mode RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE: and b) based on those predictions, use procedures to correct, control, or irlitigate the consequences of those abnormal conditions or operations:

Valve logic failure Plant-Specific 223001 Pnmary CTMT and Aux. X K3.09; Knowledge of the effect that a loss or malfunction of the PRIMARY 2.8 CONTAINMENT SYSTEM AND AUXILIARIES will have on following:

Nuclear boiler instrumentation.

226001 RHR/LPCI: CTMT Spray Mode X K2.02; Knowledge of the physical 2.9 connections and/or cause/effect relationships between RHR/LPCI:

CONTAINMENISPRAY SYSTEM MODE and the following: Pumps.

230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment A3.01 Ability to monitor automatic X 2 6 operations of the FUEL HANDLING EQUIPMENT including: Crane/refuel bridge movement: Plant-Specific.

239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure A4.14; Ability to manually operate X 3.8 Regulator and/or monitor in the control room:

Turbine trip.

245000 Main Turbine Gen. /Aux. X K4.07; Knowtedge of MAIN TURBINE GENERATOR AND 2.5 AUXILIARY SYSTEMS design feature(s) and/or interlocks which provide for the following: Generator voltage regulation.

256000 Reactor Condensate 259001 Reactor Feedwater Al .04; Ability to predict and/or X 2.8 monitor changes in parameters associated with operating the REACTOR FEEDWATER SYSTEM controls including: RFP turbine speed: Turbine-Driven-Only.

268000 Radwaste 271000 Offgas A2.10; Ability to (a) predict the X

impacts of tte following on the OFFGAS SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations Offgas system high flow.

272000 Radiation Monitoring X K5.Ol; Knowledge of the operational implications of the following concepts 3.2 as they apply to RADIATION MONITORING SYSTEM: Hydrogen injection operations effect on process radiation indications: Plant 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/ACategoryPointTotals 1 1}1 i[i]2 1 l/2Ji J1/1[oupPointTotal

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Brunswick Date of Exam: December, 2016 Category K/A# Topic RO SRO-Only IR # IR #

2.1.1 Knowledge of conduct of operations requirements. 3.8 2.1.32 Ability to explain and apply system limits and precautions. 3.8 2.1.36 Knowledge of procedures and limitations involved in core 3.0

1. alterations.

Conduct of Ability to use procedures related to shift staffing such as Operations 2 1 5 39 mininium crew complement, overbme limitations. etc.

2 1 43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant 4 3 system temperature, secondary plant, fuel depletion. etc.

Subtotal Ability to manipulate the console controls as required to 2*2 2 46 operate the facility between shutdown and designated power levels.

(multi-unit license) Ability to explain the variations in 224 36 control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.

2 Ability to interpret control room indications to verify the

. . 2 2 44 42 status and operation of a system, and understand how Equipment operator actions and directives affect plant and system Control conditions.

Ability to determine the expected plant configuration using 2

• 2 15 4 3 design and configuration control documentation, such as drawings._line-ups,_tag-outs,_etc._I 2.2,22 Knowledge of limiting conditions for operations and safety 4.7 limits.

Subtotal Knowledge of radiological safety principles pertaining to 2 3 12 3 2 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to 3 .

locked high-radiation areas, aligning filters, etc.

V Knowledge of radiation monitoring systems, such as fixed Radiation 2.3.15 .

2.9 radiation monitors and alarms, portable survey Control instruments, personnel monitoring equipment, etc.

2.3.1 1 Ability to control radiation releases. 4.3 Subtotal Knowledge of the operational implications of EOP 2

• 4 20 38 warnings, cautions, and notes.

2.4.27 Knowledge of fire in the plant procedures. 3.4 Knowledge of events related to system operation/status Emergency 2 4 30 4 that must be reported to internal organizations or external V Procedures / agencies, such as the State, the NRC, or the Plan transmission system operator.

Knowledge of local auxiliary operator tasks during an 2 4 35 V

4 V emergency and the resultant operational effects V Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected KIAs Form ES-401 -4 Tier I Randomly Reason for Rejection Group Selected K/A ill 295024EA1.14 Too similar to 295020AA1.02. Reselected 295024EA1.05 as a replacement.

2/1 259002A3.05 Not representative of how plant operates. Reselected 259002A3.08 as a replacement.

2/1 262002K6.03 Too similar to 26002A3,01. Reselected 215003K6.04 1/1 295028G2.19 Cannot write at SRO level. Replaced by 295023G2.2.25.

1/1 700000AA208 Cannot write at SRO level. Replaced by 29502 1AA2.03.

1/1 295024G2.2.37 Cannot write at SRO level. Replaced by 295037G2.421.

2/1 217000A209 Cannot write operationally valid question. Replaced with 262001A2.01.

2/2 256000A217 Not in plant design. Reselected 219000A212.

2/2 268000A2.01 Unable to write a operationally valid and discriminating question. Reselected 216000 A2.11 2/2 2860000K2.03 Unable to write a discerning question. Reselected to 2260001 K2.02.

1/2 295013.A2.02 Unable to write to the K/A. The plant doesnt really monitor stratification Reselected with 295022A.2.02.

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Brunswick Date of Exam: 11/28/16 Exam Level: RD SRO Initial Item Description a b*

I Questions and answers are technically accurate and applicable to the facility.

2. a. NRC KJAs are referenced for all questions.

b. Facility learning objectives are referenced as available. ,>

3. SRD questions are appropriate in accordance with Section D.2.d of ES-401 y 4 The sampling process was random and systematic (If more than 4 RD or 2 SRD questions A

were repeated from the last two NRC licensing exams, consult the NRR/NRD DL program office).

5. Question duplication from the licensee screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate X The audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed independently; or 7

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 RD / S RD-only question distribution(s) at right 33! 5 1 I 2 41/18 7

7. Between 50 and 60 percent of the questions on the RD Memory C/A exam are written at the comprehension! analysis level; the SRD exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter 36 I 5 39 / 20 the actual RD / SRO_question_distribution(s)_at_right.

8. References/handouts provided do not give away answers or aid in the elimination of distractors. / 7

9. Question content conforms to specific KIA statements in the previously approved examination outline and_is_appropriate_for the tier to_which_they are_assigned;_deviations_are justified.

10. Question psychometric quality and format meet the guidelines in ES Appendix B. ,4J

11. 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. /.;?

7 Printed Name / Signature Date

a. Author ,tef/ (/ij 4 - - i1

b. Facility Reviewer (*) M C. NRC Chief Examiner (#)

d. NRC Regional SupeMsor 1. /Iil7)2.

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 2.

Q LOK LOD 6. Source 7. Status SR 8. Explanation (F/H) (1-5) Stem Cred. Job- #/ Back (B/M/N) (U/E/S)

Cues T/F Partial Minutia 0 Focus Dist Link Units ward K/A Only I H 2 201001 K6.02 N

K/A is met. drl 10/5/16 2 F 2 201003 G2.4.49 N

K/A is met. Un 10/5/16 3 F 2 202002 K6.03 N

K/A is met. Un 10/5/16 203000A4.04 K/A is met.

You can get the right answer for the wrong reason. A possible modification would be to change the question to 2-El 1-F048A can first be throttled B/M if (1) minutes after _(2)_.

4 H 3 suggestio E The answer would be a toggle between 3 or 5 n used. minutes AND RPV pressure dropping below 410# or RPV level dropping to LL3. DrI 10/5/16 Changed the time of the hi drywell pressure remove the possibility of getting it right for the wrong reason.

10/20 rsb 205000 K5.03 K/A is met.

This is too closely related to the previous question.

Perhaps we could go with a question about what happens if flows change. Since this is a systems 5 F 2 x related question, we dont need to stick with what procedural guidance is directing, we can go with system response. DrI 10/5/16 Changed the question conditions and the question to closing a valve which changed the answer to the F068 valve.10/20 rsb 6 H 3 206000 KilO B

K/A is met. drl 10/5/16 7 H 3 209001 K3.03 N

I K/A is met. drllO6/16 8F2 211000 Kl.0l BPS K/A is met. drl 10/6/16

212000 K2.O1 K/A is met.

Im not certain why someone would chose 2XC or 2XD. They have nothing to do with RPS or the MG sets. Perhaps you can rephrase for a two part question. Ask the PS to the B MG set (E7 or E8) and then if RPS can be powered from the other division.

drl 10/6/16 Q21 Changed to 2 part question:

Part 1 asks power supply to MG Set B Part 2 asks the normal alternate power supply 10/20 rsb 215002 K1.02 K/A is met. drl 10/6/16 215003 A2.06 K/A is met drl 10/6/16 215003 K6.04 K/A is met.

Need to reword first question to avoid a subset issue.

I know what you mean, but since 6.5> 3 then 6.5 can never be wrong. In this case I think the easiest fix is to say A-05 (1-4) IRM Downscale, states that the alarm setpoint is ... drl 10/6/16 Added lAW prior to the annunciator. 10/20 rsb 215004 K5.03 K/A is kind of met. The K/A is asking about the operational implications of changing detector position. This appears to mean that they need to show knowledge of what happens when you move the switch. Could we make a two by two question?

The question as written would be first with C and D 13 F 2 as the answers. The second question could be how X N E far to withdraw detectors: fully or to maintain 100 to 200000 cps. DrI 10/7/16 Cannot toggle on fully inserted or maintain 100 to 200,000 cps as a fully inserted detector may indicate between 100 to 200,000 cps. Knowing that you have to wait until overlap is established implies they know that this is needed to determine operability of the detectors. 10/20 rsb 14 F 2 215005 K2.02 M S K/A is met. DrI 10/7/16 15 F 2 215005 K5.04 N S K/A is met. DrI 10/7/16 16 H 3 216000 A2.11 N SI K/A is met. DrI 10/7/16 17 H 3 217000 AlOl N

K/A is met. DrI 107/16 18 F 2 218000 K1.03 N

K/A is met. On 10/7/16

218000 K3.01 K/A is met.

19 H 3 Could we change the second question to state that B E RPV level will/will not be restored with both RHR loops? DrI 10/7/16 Made the change as requested. 10/20 rsb 223001 K3.09 20 H 2 K/Aismet.

B S This is a GFE question. Drl 10/7/16 It is plant specific rsb 10/20 223002 Al .01 K/A is met.

Instead of stating that RPS Bus A has not been 21 H 2 N E transferred to an alternate power supply, could we state that No operator actions have been taken?

DrI 10/7/16 Made change as requested. 10/20 rsb 234000 A3.0l K/A is met.

22 F 3 Are your ROs required to know this information? Is N E fuel movement within their job description? Dri 10/7/16 This is a trained topic for the RDs. 10/20 rsb 239002 K4.03 23 F >1 K/A is met.

C and D are weak. DrI 10/7/16 241000 A4.14 24 F 2 K/A is met drl 10/12/16 25 F 2 245000 1<4.07 K/A is met dii 1012116 26 F 2 2590001 Al.04 K/A is met. DrI 10/12/16 27 F 2 259002 A3.01 K/A is met. Dii 10/12/16 28 H 2 261000 A4.02 K/A is met. DrI 10/12/16 262001 G2.2.40 K/A is met.

This is not very discerning. If all of your equipment is operable, do you meet TS? I would hope so. Could we make this a TS 3.8.2 question instead, Put one of 29 F 1 X the units in Mode 5 moving fuel. Give them 2 EDGs and 1 SAT on the S/D unit. The answer remains the same, but it is more discerning dii 10/12/16 The question was changed to make Unit 2 in MODE 5, do not believe it would be RD level if I asked TS 3.8.2 as it would have to get very specific, beyond the RD knowledge to ask a good question. rsb 10/24 30 H 3 262002 A3.0l K/A is met. DrI 10/12/16

263000 G2.2.37 K/A is met.

The second question appears to answer the first question. If I know that either the inboard or outboard 31 H 2 X X isolation logic has lost power, then Why would I consider the system operable? Perhaps the second question could ask about the loss of power on another system (ADS or HPCI maybe)? drl 10/12/16 Changed to question conditions to a loss of 4A which makes RCIC available for injection. 10/20 rsb 32 H 3 264000 K6.03 K/A is met. DrI 10/12/16 272000 K5.01 K/A is met.

Could we toggle on the answers from choice A and B 33 F 2 x N E and toggle if the setpoint will/will not require to be raised due to HWC being placed in service. DrI 10/12/16 2x2 will not work for plausibility. RB 10/20 286000 K2.03 K/A is met.

34 F 2 Not very discerning. We could change this K/A if X N desired. Drl 10/13/16 226001 K2.02 New K/A provided and question submitted. rsb 10/24 295001 G2.2.12 K/A is met.

The first question does not seem discerning. Why would someone choose two loop?

Perhaps we could give them the indications of a failed jet pump and then ask if there is a failed jet 35 F 2 pump, what would the procedure have them do? Dri I 10/12/16 The question conditions have a loss of a recirc pump, our power to flow maps are not changed from 2 loop to single loop until thermal limits are adjusted. Some of our validators applied this very logic to answering the question. rsb 10/20 295003 AK1 .03 36 H 3 B K/A is met. drl 10/13/16 295004 AK2.01 37 F 3 N K/A is met. drl 10/13/16 295005 AK3.04 K/A is met.

Is C really plausible? The front standard trip is pretty obvious. The correct answer is pretty deep in the basis. Are you certain it is required RO knowledge and not SRO knowledge? I would typically expect an 38 H 4 X B E RO to know that it is to prevent a reverse power of the main generator, but the rest of that is pretty detailed. DrI 10/13/16 A person off of the street would not know there is a trip device on the front standard.

Changed the correct answer wording to reverse power. rsb 10/20

39 H 2 295006 AA1.06 N

K/A is met. Un 10/13/16 40 F 2 295009 AK2.04 N

K/A is met. drl 10/13/16 295016 AK3.03 K/A is met.

This does not meet the Tier 1 category in that the operator does not need to use any procedural knowledge to answer the question. Instead of giving 41 F 3 s them the whole Caution, only give them the first part and ask the last sentence as a before/after question.

The second question could be The purpose of this sequence is/is not to prevent a loss of .... DrI 10/13/16 Made changes as requested. rsb 10/20 42 H 2 295017 AA2.03 B

K/A is met. drl 10/13/16 295018 AK2.02 K/A is met.

Although the question is OK, Im not sure that C is a 43 H 3 really good distractor. Could we modify this to have x B E the answers as A complete loss of RBCCW has/has not occurred AND A reactor scram is/is not required? drl 10/13/16 a 2x2 as requested. rsb 10/20 K/A is met.

This does not meet the Tier 1 category in that the operator does not need to use any procedural knowledge to answer the question. In this case I 44 F 2 X would suggest that you look at putting them in a situation where they may have to worry about maintaining a negative reactor building pressure.

Could this affect the AU 2 loads? DrI 10/13/16 Change one part to ask the action from the AOP rsb 10/24 295020 AA1 .02 K/A is met.

This does not meet the Tier 1 category in that the operator does not need to use any procedural knowledge to answer the question. In this case, the correction would be to ask what procedure they 45 H 3 X B U/E should enter and then toggle on fans are tripped/running. DrI 10/13/16 To know that it can be over-ridden requires knowledge of the procedure steps for what conditions are over-ridden. Not all of the conditions given can be over-ridden. rsb 10/20

295021 AK2.05 This does not meet the Tier 1 category in that the operator does not need to use any procedural knowledge to answer the question. In this case, the question can be made acceptable by changing the 46 H 3 X N U/E second question to ask if 1-OP-17 can/cannot be used to align fuel pool cooling assist to SDC Loop A.

Reword the first question to state Fuel pool cooling assist is/is not in service.

drl 10/17/16 Add lAW the procedure to the question. rsb 10/20 47 F 2 X 295023 M1.04 B

K/A is met. drl 10/13/16 295024 EAJ .05 K/A is met.

This does not meet the Tier 1 category in that the 48 F 2 X N operator does not need to use any procedural knowledge to answer the question. drl 10/13/16 Changed part 2 to be if the scram procedure is/is not required to be entered. rsb 10/20 295025 EK3.02 K/A is met.

This does not really meet the Tier 1 category in that 49 H 2 the operator does not need to use any procedural B

knowledge to answer the question. However since the proposed question gives a choice of a manual action, I will consider this a SAT question. dri 10/13/16 295026 G2.4.50 K/A is met.

This does not meet the Tier 1 category in that the H 3 operator does not need to use any procedural X N E knowledge to answer the question. In this case, add the procedure name prior to the second question. dri 10/13/16 Add lAW the procedure to the question. rsb 10/20 51 F 2 295028 EA2.01 B

K/A is met. drl 10/13/16 295029 EA1 .01 K/A is met.

This does not meet the Tier I category in that the 52 F 2 operator does not need to use any procedural X N knowledge to answer the question. drl 10/13/16 Inslead of telling them the level gave them the annunciator for them to determine the action based on level. rsb 10/24 295030 G2.4.50 53 H 3 N K/A is met. drl 10/13/16 295031 EK1.03 54 H 3 B K/A is met. drl 10/13/16

295032 EK3.01 K/A is met.

55 H 3 X How realistic is distractor B? drl 10/13/16 B E This would be correct for Max SafeRad Limits. Per UFSAR RBHVAC maintains occupied areas within temp limit for human occupancy. rsb 10/20 56 F 3 295034 G2.4.8 N

K/A is met. drl 10/13/16 57 F 3 295036 EKI.02 N

K/A is met. drl 10/13/16 295037 EK1.03 K/A is not met. The K/A is asking for the boration effect on power while power is above APRM 58 F 2 X downscale.

X B We need to find a way to rewrite this using some kind of procedural knowledge. DrI 10/13/16 Re-wrote question as provided to meet the K/A better K/A is met.

This does not meet the Tier 1 category in that the operator does not need to use any procedural knowledge to answer the question. The easiest fix is 59 F 2 to give more details and have the applicant pick the correct AOP. Use the second question to toggle on.

DrI 10/13116 Changed the first question to be if TBHVAC should be in once through or recirc mode lAW the procedure._rsb_10/24 60 H 2 300000 A2.01 N

K/A is met. drl 10/13/16 61 F 2 300000 K3.01 B

K/A is met. DrI 10/13/16 62 H 2 400000A2.01 B

K/A is met drl 10/13/16 400000 K4.01 K/A is met.

63 F 2 B E This could be written with many less words as a 2x2.

DrI 10/14/16 Made a 2x2 question rsb 10/24 600000 AK3.04 K/A is met.

This would be a better Tier I question by making it a 2x2 question.

OASSD-02 requires that backup nitrogen is placed in service by placing RNA keylock switch in LOCAL /

64 H 2 B E REMOTE and If this is not done correctly the unit could suffer Loss of Drywell Cooling / Inability to Operate SRV5.

DrI 10/14/16 Cannot write as 2x2 as the keylock positions are Normal/Local, no one would pick normal for an ASSD procedure_action._rsb_10/20

65 H 2 700000 AA2.03 B

K/A is met. drl 10/14/16 G2.1.1 K/A is met.

Jet pump flow vs steam and feed flow is not very 66 F 2 X N E discerning. Why not ask if steam/feed flow is/is not one of the parameters that needs to be constantly monitored? DrI 10/14/16 Made change as requested. rsb 10/20 67 F 3 G2.1.32 B

K/A is met. drl 10/14/16 68 H 3 G2.1.36 N

K/A is met. drl 10/14/16 69 F 2 G2.2.2 B

K/A is met. drl 10/14/16 70 F 2 G2.2.4 B

K/A is met. drl 10/14/16 G2.2.44 K/A is met.

71 H 3 Need to change second answer in A to in the PUMP B

B RUN position. The choice of leaving it in A might make some think it was improbable. DrI 10/14/16 Made chanae as reauested. rsb 10/20 72 F 2 G2. 3. 12 B

K/A is met. drl 10/14/16 73 H 2 G2.3.15 B

K/A is met. drl 10/14/16 74 H 2 G2.4.20 B S K/A is met. drl 10/14/16 75 F 2 K/A is met.

N E The word is needs to be added to the second line.

Made change as requested. rsb 10/20

SRO ONLY 209001 G2.4.35 KJA is met.

This provides information that would make Question 76 H 3 N E 55 distactor B even less plausible. DrI 10/17/16 Question 55 is dealing with temperature limits while this question deals with cad levels. No cueing is provided. rsb 10/20 212000 G2.2.44 K/A is met.

In the Explanation section, I am confused why you 77 H 2 N E state Groups 2 and 4 remained lit,.. Diidnt all groups remain lit? It does not change anything. Dcl 10/17/16.

Made changes as requested. rsb 10/20 215001 G2.2.44 K/A is met.

Would Condition A always be correct here? At some 78 H 3 facilities, if two PCI Vs inoperable they would enter N E both A and B. Obviously B is more limiting. If this is true at Brunswick then the question 2 answers should be A only AND A and B. drl 10/17/16 Made changes as requested. rsb 10/20 219000 A2.12 79 H 3 N K/A is met. drl 10/17/16 239002 A2.01 K/A is mostly met.

80 H 2 This is Ok as long as there are no other questions in N E which the mitigation portion is to determine the e-plan call. Dcl 10/17/16 k r E-Plan calls on this topic. rsb 10/20 81 H 2 261000 A2.09 N

K/A is met. drl 10/17/16 82 H 2 262001 A2.09 N

K/A is met. drl 10/17/16 83 H 3 271000A2.10 N

K/A is met. dcl 10/17/16 295001 AA2.05 K/A is met.

Could we modify this question to change the power 84 H 2 B E level to 72%. That would change the correct answer toA. drl 10/17/16 Changed the power level and conditions for 72%

power. rsb 10/20

295013 AA2.02 K/A is NOT met..

The K/A requires the question to test the ability to 85 F 2 x N determine localized heating or stratification, not e locations of indications. DrI 10/17/16 AA2.02, New K/A provided and question 10/24 K/A is met.

C is not plausible. You give them that the pumps are tripped already. Recommend asking _(l)_is required first followed by (2). Then the two 86 H 2 X N E answers can be terminate and prevent and SLC. Dri 10/17/16 The Recirc pumps tripped was removed and the conditions for a tripped pump were provided so that the students will have to determine that the recirc pumps are

.rsb10/20 1 AA2.03 K/A is kind of met.

Im not certain how you determined the level for the UE. The way I read this EAL, the UE is required whenever you cannot maintain the required level band.

I think a better question would be to tell them they were in GP-5 and that RWL was at 192 when all AC was lost 20 minutes ago. No recirc or SDC poumps 87 H 3 x x N have been started. AOP-1 5 has been entered. Then ask RPV level is/is not adequate to support natural circulation AND lAW OPEP-02.2.1, a UE is/is NOT required to be declared.

If you make a statement that all level bands are designated in accordance with the controlling procedure, then I believe the lower limit would be 200 and a UE would be required. DrI 10/17/16 Provided the basis document that clearly states that LL1 is the lower limit. rsb 10/24 295023 G2.2.25 88 F 2 N I K/A is met. drl 10/17/16 295026 G2.1.23 89 H 2 N S K/A is met. drl 10/17/16 295035 EA2.01 90 H 2 N K/A is met. drl 1017/16 295037 G2.4.21 91 H 3 N K/A is met. dl 10/18/16 295038 EA2.01 92 F 2 N K/A is met. drl 10/18/16 600000 AA2.07 93 F 2 N K/A is met. drl 10/18/16 G2.1.5 94 F 2 B K/A is met. drl 10/18/16

( 4 G2.1.43 K/A is met.

I find the first question confusing. What does the term implement thermal penalties mean?

If youre asking if they need too change power/flow 95 H 3 maps, lets just ask that.

N E/U The second question is strange and kind of provides clues to the first question. Instead could we ask if continued operation would be allowed if the B Recirc Pump tripped? DrI 10/18/16 The term implement thermal penalties is a common term here. No changes required. rsb 10/20 96 H 2 G2.2.15 N

K/A is met. drl 10/18/16 97 H 2 G2.2.22 B

K/A is met. drl 10/18/16 98 H 3 G2.3.1 1 N

K/A is met. dl 10/18/16 G2.4.30 K/A is met.

A and D are really not plausible. A better question would be:

An ENS report to the NRC must be made by An LER _2_ required.

A. 1)0400

2) is B. U 0400 99 H 2 2) is not B E/U C. 1)0430

2) is

0. 1) 0430

2) is not This would include adding NUREG-1022 (or other appropriate site procedure) to the reference list. FrI 10/18/16 s as requested. rsb 10/20 K/A is met.

100 F 2 N In the first question change before to no later than.

DrI 10/18/16 Made changes as requested. rsb 10/20

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Date of Exam: il1 Exam Level: RO SRO Item Description Initials a b c

1. Clean answer sheets copied before grading

2. Answer key changes and question deletions justified and documented 7

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

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 Q%_

deficiencies and wording problems; evaluate validity of /

questions missed by half or more of the applicants Printed Name/Signature Date

a. Grader / i /2 -1cc- /

b. Facility Reviewer(*)

c. NRC Chief Examiner(*)  ?. Ly:

U. NRC Supervisor (*) Gec I

) 2)1

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

g ,-, Enclosures Contain Operator Examination Material Brunswick Nuclear Plant lJUF% Withhold from public disclosure until P.O. Box 10429 ENERGYS completion of examination Southport, NC 28461 SEP2 22016 Serial: BSEP 16-0086 U. S. Nuclear Regulatory Commission, Region Il AUN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1 257

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Operating Test, Written Exam, and Reference Materials for Licensed Operator Initial Examination 50-325/2016-301 and 50-324/2016-301

References:

1. Letter from Gerald J. McCoy (NRC) to William R. Gideon (Duke Energy

), Brunswick Steam Electric Plant Notification of Licensed Operator Initial Examination 05000325/2016301 and 05000324/2016301, dated June 17, 2016, ADAMS Accession Number ML16173A365

2. Letter from Annette H. Pope (Duke Energy) to Catherine Haney (NRC)

, Operating Test Outline for Licensed Operator Initial Examination 50-325/2016-301 and 50-324/2016-301, dated August 23, 2016

Dear Ms. Haney:

In accordance with the guidelines in Revision 10, of NUREG-1021, Opera tor Licensing Examination Standards for Power Reactors, Duke Energy Progress, LLC, is providing the proposed examinations and reference material supporting the operati ng test, which is scheduled to be administered during the weeks of November 28, 2016, and Decem ber 5, 2016; and the written examination scheduled to be administered the week of December 12, 2016.

In accordance with the schedule contained in the NRCs letter dated June 17, 2016, a list of the examination materials is provided in Enclosure 1. Copies of Examiner Standard Forms and Checklists are provided in Enclosure 2. Copies of Forms ES-D-1 and ES-D-2, the simulator scenarios, and Job Performance Measures (JPMs) are provided in Enclos ure 3. A copy of the written examination is provided in Enclosure 4. Copies of the referen ce materials are provided in Enclosure 5 (i.e., on 3 CD-ROMs), along with a Reference Materials Index.

In accordance with 10 CFR 55.40(b)(3), Mr. Craig Oliver, as the design ated authorized representative of the Brunswick Steam Electric Plant, Units 1 and 2, has approved the enclosed Operating Test Quality Checklist, Simulator Scenario Quality Check list, and Written Examination Quality Checklist (i.e., part of Enclosure 2).

Enclosures Contain Operator Examination Material Withhold from public disclosure until completion of examination

U. S. Nuclear Regulatory Commission, Region II Page 2 of 3 Enclosures 2, 3, 4, and 5 are being provided only to Mr. David R. Lanyi, the assigned NRC chief examiner. In accordance with Revision 10, of NUREG-1 021, Section ES-201, Initial Operator Licensing Examination Process, please ensure that the proposed examinations and associated forms and checklists are withheld from public disclosure until after the examinations are complete.

This document contains no regulatory commitments.

Please refer any questions regarding this submittal to Mr. Bob Bolin, Senior Nuclea r Operations Instructor, at (910) 457-3078, or Mr. Craig Oliver, Control Room Supervisor, at (910) 454-2108.

Sincerely, H. Pope Director Organizational Effectiveness Brunswick Steam Electric Plant AHP/mkb Enclosures

1. List of Examination Materials

2. Examiner Standard Forms and Checklists (Enclosure only being sent to Chief Examiner)

3. Forms ES-D-1 and ES-D-2, Simulator Scenarios, and Job Performance Measu res (JPMs) (Enclosure only being sent to Chief Examiner)

4. Written Examination Questions and Exam Keys (Enclosure only being sent to Chief Examiner)

5. Reference Materials (3 CD-ROM5) and Reference Materials Index (Enclosure only being sent to Chief Examiner)

U. S. Nuclear Regulatory Commission, Region II Page 3 of 3 cc (with Enclosures 1 through 5):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. David R. Lanyi, Chief Examiner 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 cc (with Enclosure 1 only):

U. S. Nuclear Regulatory Commission AHN: Document Control Desk Washington, DC 20555-000 1 U. S. Nuclear Regulatory Commission, Region II AHN: Mr. Gerald J. McCoy, Chief Operations Branch 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission AHN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27626-0510 swatson @ ncuc.net

BSEP 16-0086 Enclosure 1 List of Examination Materials The following documents, developed in accordance with NUREG-1 021, Revision 10, Operator Licensing Examination Standards for Power Reactors, are provided in Enclosure 2:

Form ES-201-2 Examination Outline Quality Checklist Form ES-201-3 Examination Security Agreement (Photocopy)

Form ES-301-1 Administrative Topics Outline (for RO and SRO positions)

Form ES-301 -2 Control Room/In-Plant Systems Outline (for RO, SRO-U, and SRO-l positions)

Form ES-301-3 Operating Test Quality Checklist Form ES-301 -4 Simulator Scenario Quality Checklist Form ES-301-5 Transient and Event Checklist Form ES-3d -6 Competencies Checklist Form ES-401 -4 Record of Rejected KJAs Form ES-401-6 Written Examination Quality Checklist provides Forms ES-D-1 and ES-D-2 for each active scenario, and the Simulator and Job Performance Measures (i.e., Administrative, In-Plant, and Simulator). provides the proposed written examinations (RO and SRO) with exam keys and a copy of all exam questions with corresponding distracter analysis. provides the reference materials on 3 CD-ROMs and the Reference Materials Index.

William R. Gideon f.. DUKE

ç Enclosures Contain Operator Examination Material Withhold from public disclosure until .

Vice President Brunswick Nuclear Plant

- ENERGY completion of examination P.O. Box 10429 Southpo, NC 28461 910.457.3698 DEC 1 52016 Serial: BSEP 16-0116 U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1 257

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Reactor Operator and Senior Reactor Operator License Post-Examination Documentation and Comments

Reference:

Letter from Gerald J. McCoy (NRC) to William R. Gideon (Duke Energy),

Brunswick Steam Electric Plant Notification of Licensed Operator Initial Examination 05000325/2016301 and 05000324/2016301, dated June 17, 2016, ADAMS Accession Number ML16173A365

Dear Ms. Haney:

In accordance with the guidance contained in Revision 10 of NUREG-1021, Operator Licensing Standards for Power Reactors, Section ES-402, Administering Initial Written Examinations, and ES-501, Initial Post-Examination Activities, Duke Energy Progress, LLC (Duke Energy), is providing the NRC the specified documentation for the reactor operator and senior reactor operator written examinations, which were administered at the Brunswick Steam Electric Plant on Wednesday, December 14, 2016. The examination documentation enclosures are being provided only to Mr. David R. Lanyi, with his copy of this letter. Duke Energy has post exam comments relating to the written examination included with this submittal letter as Enclosure 2.

The master examination and answer key are provided in Enclosure 6 of this letter, with annotations. All substantive comments made by the applicants following the written examination are included with Enclosure 2. Lastly, the original ES-201-3 forms, Examination Security Agreement, with all the pre- and post-examination signatures will be provided via email, as previously discussed with the NRC chief examiner on December 7, 2016.

This document contains no regulatory commitments.

Enclosures Contain Operator Examination Material Withhold from public disclosure until completion of examination

U.S. Nuclear Regulatory Commission, Region II Page 2 of 3 Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager Regulatory Affairs, at (910) 457-2487.

Sincerely, William R. Gideon WRG/mkb

Enclosures:

1. ES-403-1, Written Examination Grading Quality Checklist

2. Written Examination Performance Analysis Results (with recommended substantive changes)

3. Graded Written Examinations and Applicants Answer Sheets

4. Applicants Questions Asked and Answers Given During the Written Examination

5. Written Examination Seating Chart

6. Master Examination and Answer Key

7. ES-20 1 -3, Examination Security Agreement

U.S. Nuclear Regulatory Commission, Region II Page 3 of 3 cc (with enclosures):

U.S. Nuclear Regulatory Commission, Region II ATTN: Mr. David R. Lanyi, Chief Examiner 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 cc (without enclosures):

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission, Region II AUN: Mr. Gerald J. McCoy, Chief Operations Branch 1 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission AUN: Mr. Andrew Hon (Mail Stop OWEN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27626-0510 swatson@ncuc.net