ML14350A158
| ML14350A158 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/16/2014 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| Shared Package | |
| ML14350A180 | List: |
| References | |
| 50-324/14-301, 50-325/14-301 50-324/OL-14, 50-325/OL-14 | |
| Download: ML14350A158 (55) | |
Text
ES-201, Page 24 of 27 ES-201 Examination Preparation Checklist Form ES-201-1 Facility:
Date of Examination:
Examinations Developed by: Facility / NRC (circle one)
Target Date*
Task Description (Reference)
Chief Examiners Initials
-180 1.
Examination administration date confirmed (C.1.a; C.2.a and b)
-120 2.
NRC examiners and facility contact assigned (C.1.d; C.2.e)
-120 3.
Facility contact briefed on security and other requirements (C.2.c)
-120 4.
Corporate notification letter sent (C.2.d)
[-90]
[5.
Reference material due (C.1.e; C.3.c; Attachment 2)]
l
{-75}
l 6.
Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, l
ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and l
ES-401-4, as applicable (C.1.e and f; C.3.d) l
{-70}
l
{7.
Examination outline(s) reviewed by NRC and feedback provided to facility l
licensee (C.2.h; C.3.e)}
l
{-45}
l 8.
Proposed examinations (including written, walk-through JPMs, and l
scenarios, as applicable), supporting documentation (including Forms l
ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference l
materials due (C.1.e, f, g and h; C.3.d)
-30 9.
Preliminary license applications (NRC Form 398's) due (C.1.l; C.2.g; l
-14
- 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; l
-14
- 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)
-14
- 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)
-7
- 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)
-7
- 14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm l
qualifications / eligibility; and examination approval and waiver letters sent l
(C.2.i; Attachment 4; ES-202, C.2.e; ES-204) l
-7
- 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)
-7
- 16. 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 l
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.
l Brunswick October 2014 PGC PGC PGC PGC PGC PGC PGC PGC PGC PGC PGC PGC PGC PGC PGC PGC
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Brunswick Nuclear Plant Dale o1ExamlnaUon Oct-2014 Initials Item task Description 1.
a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 fl.1_
W R
- b. Assess whether the outlIne was systematically and randomly prepared in accordance with j
I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics, d.
Assess whether the justifications for daselecled 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, S
and major transients.
M b.
Assess whether there are enough scenario sets (and spares) to test the projected number u
and mix of applicants In accordance with the expected crew composition and rotation schedule i.
without compromising exam Integrity, and ensure that each applicant can be tested using A
at least one new or significantly modified scenario, that no scenarios are duplicated r
from the applicants audit test(s), and (hat scenarios will not be repeated on subsequent days,
0 c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative R
and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
/
3.
a.
Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks W
distributed among the safety functions as specified on the form I
(2) task repetition from the last two NRC examinations Is within the limits specified on the form fl t
(3) no tasks are duplicated from the applicants audit test(s)
I (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 err the form.
b.
Verify that the administrative outline meets the criteria specified on Form ES-301-I:
(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task Is repeated from the last two NRC licensing examinations
c.
Determine If there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
4,
- a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
b.
Assess whether the 10 CFR 55.41143 and 5545 samplIng is appropriate.
N C.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
d.
Check for duplication and overlap among exam sectIons.
A
- e. Checktheentlroaxamforbalanceofcoverage.
L L
f.
Assess whether the exam fits the appropriate job level (ROorSRO).
4Z) f dnted N Slqoature l)ate
- a. Author Robert 8dm fr4
- b. Facility Reviewer ()
Jerry PIerce 41,,.4
- c. NRC Chief Examiner (#)
Pi.l 6 Ck.r4f g a
oi ri
- d. NRC Supervisor
(-i.R.Q\\
ç JoJcfrj Note:
- Independent NRC reviewer Initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines ES-201, Page 26 of 28
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Brunswick Date of Examination: October 2014 Examination Level:
R0 SRO Operating Test Number: FINAL Administrative Topic Type Describe activity to be performed (see Note)
Codee Conduct of Operations ft M Calculate GAFS and T.S. Assessment (COO-O1) 2.1.23 Ability to perform specific system and integrated (RO, then SRO) plant procedures during all modes of operation.
Conduct of Operations ft M Verifying SLC Operating Parameters 2.1.7 Ability to evaluate plant performance and make (COO-02) operational judgments based on operating characteristics, reactor behavior, and instrument (RO) interpretation.
Conduct of Operations R M Evaluate Plant Chemistiy Limits During Resin
Intrusion (COO.O3)
SRO 2.1.34 Knowledge of primary and secondary plant
(
)
chemistry limits.
Equipment Control R, M Evaluate a CRD Clearance (RO and SRO) 2.2.13 Knowledge of tagging and clearance procedures.
Radiation Control R M Oete,ine Total Dose for ALARA (RO, then SRO) 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions Emergency ProcedureslPlan ft N Classify an Emergency per PEP-2.1 (SRO Only) 2,4.29 Knowledge of the emergency plan.
NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
Type Codes & Criteria:
(C)ontrol room, (5)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs:
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1: randomly selected)
Conduct of Operations (CQO-O1) CR0 1 then SRO)
Calculate GAFs and Tech Spec Assessment R, M K/A 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation.
This is a modified JPM that requires the Examinee to calculate Gain Adjustment Factors (GAFs) per OPT-Ol.8C, and then the SRO determines the Tech Spec implications based on the calculations. Numbers were modified to provide different values for calculated GAFs and different GAFs that were out of spec.
Conduct of Operations (CO0-02) CR0)
Verifying SLC Operating Parameters K/A 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
This is a modified JPM that requires the RO to verifying SLC Tank operating parameters. This is part of the RO DSR. Parameters were changed to provide satisfactory results.
Conduct of Operations CCOO-03) (SRO)
Evaluate Plant Chemistry Limits during Resin Intrusion R, M 2.1.34 Knowledge of primary and secondary plant chemistry limits.
This is a modified bank JPM that was that requires the Examinee to evaluate plant chemistry limit lAW OAOP-26.O, High Reactor Coolant Or Condensate Conductivity and then determine the determine applicable actions required by OAl-81, Water Chemistry Guidelines, related to plant operations.
Equipment Control CR0 and SRO)
Evaluate a Clearance Boundary 2A CR0 Pump P, M K/A 2.2.13 Knowledge of tagging and clearance procedures.
This is a bank JPM that was used on the 2008 NRC exam. Given a boundary request form and a written clearance, the Examinee must evaluate the clearance for safety and accuracy. Modified to switch suction and discharge valve order.
Radiallon Control (RO and SROJ Determine Total Dose for ALARA R, M K/A 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
The is a bank JPM that was used on the previous NRC Exam (2012).
It requires the Examinee to determine the travel path which gives the lowest dose, ALARA.
Added section for SRO only to determine if Drywell dose exceeds Protection of Valuable Property limit.
Emergency Procedures/Plan (SRO only)
Classify and Emergency lAW OPEP-2.1 R, N K/A 2.4.40 Knowledge of SRO responsibilities in Emergency Plan implementation.
This is a new JPM that requires the SRO Examinee to classify and emergency.
Although classification JPMs have been use in previous exams, the classification requirements for this JPM are new.
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Brunswick Date of Exam ination: OCT 2014 Exam Level: RO SRO-t SRO-IJ I Operating Test No.: FINAL Control Room Systems (8 for RO); (7 for SRO-l)
System I JPM Title Type Code Safety Function
- a. Start second Recirc Pump S, P, A I
- c. Emergency Equalize around MSIYs S, P 3
- e. (RO only) Terminate PC venting S, D 5
fBE3-offeedrr-to-D Place RPS to Alternate 5 0
- g. PlaGe-RP4Q-Altecna4e Bus E3 Normal feeder to DG3 5,D 6
- h. Perform PASS lineup 5, N 9
In-Plant Systems (3 for ROISRO-l)
I. SEP-09 with RB Accessible ft D, E 2
- j. Secure Condensate Pump IAWAOP-32 (Bkr Failure) ft A, E, 0 7
- k. Place IA Dryer in Sweep Mode ft N, E 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all SRO-U systen,s must serve different safety functions: in-plant systems and ftinctions may overlap those tested in the control room.
Type Codes Ctitoria for RO I SRO-l I SRO-tJ (A)ltemate path 4-61 4-1 2-3 (C)ontrol roam (D)irectfrcmbank 9i8Is4 (E)mergency or abnormal In-plant 1 1 a 1 1 a 1 (EN)gineered safety feature
- I I al (control room system)
(L)ow-Power / Shutdown 1 / a 1 I a I (N)ew or (M)oditled from bank including 1(A) a 21 a 2 / a 1 (P)revious 2 exams 3/
3 1 2 (randomly selected)
(R)CA al/al/al (S)imulator
a.
Recovery from Recirc System Runback 202001 A4.01 AbUity to operate and/or monitor in the control room:
Recirculation Pumps This is a previous exam (2012) simulator alternate path JPM that will have the examinees preparing to start the second recirc pump.
When the pump is started and the discharge valve is being throttled open the only running pump will trip requiring a reactor manual scram. This JPM was randomly selected from the 2012 exam.
- b. Start HPCI with Exhaust Diaphragm failure 206000 A3.09 Ability to monitor automatic operation of HPCI including response to system isolation This is a banked JPM that will require the examinee to start HPCI for injection per the Hard Card and restore RPV water level. As an alternate path the exhaust diaphragm breaks and HCI does not auto isolate requiring manual isolation of HPCI.
c.
Emergency Equalize around MSIVs 239001 A4.01 Ability to manually operate and or monitor in the Control Room:
MSIVs This is a banked simulator JPM that will require the examinee to perform the control operator actions associated with emergency equalization around the MSIVs. This JPM was randomly selected from the 2010-2 exam.
- d. SDC restoration with RHR valve overload 295021 AA1.04 Ability to manually operate Alternate Heat Removal Methods This is a low power banked simulator JPM that will require the exarninee to perform Alternate Shutdown Cooling lAW OAOP-15.O.
As an alternate path the RHR pump has on overload condition.
e.
(RO only) Terminate PC venting 295024 EA1.19 Ability to operate/monitor Containment Atmosphere Control System as it applies to High Drywell Pressure This is a banked simulator JPM that will require the examinee to terminate Primary Containment Venting, using SEP-01, Section 4.
- 3. A Bus E3 Normal feeder to DG3 264000 A4.04 Ability to manually operate and/or monitor in the control room Manual start, loading, and stopping of emergency generator.
This is a banked simulator JPM that will require the examinee to place E3 on the DG.
f % Place RPS to Alternate 212000 A2.02 Ability to predict the impacts of RPS bus power supply failure on RPS System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations.
This is a banked simulator JPM that will require the examinee to transfer RPS alternate power to alternate.
Ii. Perform PASS lineup 295038 EA1.05 Ability to manually operate and/or monitor in the control room: Post Accident Sampling System (PASS).
This is a new simulator JPM that will require the examinee to lineup the Post Accident Sampling System for taking a sample.
1.
SEP-09 with RB Accessible 295009 AAI.02 Ability to operate or monitor the CRD System as it applies to low reactor water level.
This is a banked in-plant JPM that will require the examinee to simulate performing SEP-09, CRD System flow maximization using two pumps and the reactor building accessible. This JPM is performed in the RCA.
j.
Secure Condensate Pump lAW AOP-32 (Bkr Failure) 295016 AA1.06 Ability to operate and/or monitor the following as it they apply to Control Room Abandonment-Reactor Water Level.
This is a banked in-plant JPM that will require the examinee to simulate the actions associated with AOP-32. This JPM is alternate path in that the condensate pump does not trip requiring additional actions to trip the pump. This JPM is performed in the RCA.
Ic.
Place IA Dryer in Sweep Mode 300000 A2.01 Ability to predict the impacts of Air Dryer and filter malfunctions on the Instrument Air System and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations.
This is a new in-plant JPM that will require the examinee to simulate setting the Service Air Dryer maximum sweep value to zero JAW OAOP-20.0. This JPM is performed in the RCA.
ES-301 Operating Test Quality ChecklIst Form ES-301-3 Facility: Brunswick Dat of Examination: Oct-2014 Operating Test Number: Final initials
- 1. General Crlte,la a
b c#
a.
The operating test canfomis with the previously approved outline; changes are consistent with sampling requirements (e.g.. 10 CFR 55.45, operational importance, safety function distribution).
b.
There Is no dayto-day repetition between this and other operating tests to be administered J
during this examInation.
c.
The operating test shall not duplicate items from the applicants audit test(s). (see Section D,1.a.)
t d.
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 lime allowed for completion) and specific designation If deemed to be time-critical by the facility lIcensee j5 73 7) 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 en the sequence of steps, If applicable b.
Ensure that any changes from the previously approved systems and administrative walk-through ft outlines (Forms ES-301-l and 2) have not caused the test to deviate from any of the acceptance D 49 1-Y) 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 I Signature Date a.
Author Robert Bolln b.
Facility Reviewer()
Jerry Pierce c.
NRCChiefExamlner(#)
Cii/
os i d.
NRC Supervisor (EJ\\) Co..\\
.D 0 Qtc C Io/i)zi1 NOTE:
The facility signature is not applicable for NRC-developed tests.
Independent NRC reviewer initial items in Column c, chief examiner concurrence required.
ES3O1, Page 24 of 27
ES.301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Brunswick Date of Exam: Oct-2014 Scenario Numbers:
I i 2 1 3/4 operating Test No...
QUAUTAIlVE ATfRIBUTES
Initials a
b c#
1.
The Initial conditions are realistic, in that some equipment andtor instrumentation may be out of service, but it does not cue the operators into expected events.
2.
The scenarios consist mostly of related events.
M i1 3.
Each event description consists of the point in the scenario when It Is to be initiated the malfunction(s) that are entered to Initiate the event the symptornalcues that will be visible to the crew the expected operator actions (by shift position) the event temiination point (If applicable) 4.
No more than one non-mechanistic failure (e.g., pipe break) is incorporated Into the scenario without a credible preceding Incident such as a seismic event.
5.
The events are valid with regard to physics and thermodynamics.
6.
SequencIng and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
7.
if time compression techniques are used, the scenario summary dearly so Indicates.
Operators have sufficient time to carry out expected activities without undue lime constraints.
Cues are given.
8.
The sImulator modeling is not altered.
9.
The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open sImulator 11 performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity Is maintained while running the planned scenarios.
10.
Every operator will be evaluated using at least one new or significantty modified scenario.
All other scenarios have been altered In accordance with Section D.5 of ES-3D 1.
11.
All Individual operator competendes can be evaluated, as verified using Form ES-3016
]2 4 tL tsubmit the form along with the sImulator scenarios).
/
12, Each applicant will be significantly involved In the minimum number of transients and events 42 specified on Form ES301-5 (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.
Thtalmalfunctlons(58) 9 j 8 / 8/8 2.
Malfunctions after EOP entry (12) 3
, 2 / 3 / 2 15 fZ 3.
Abnormal events (24) 2
/ 3 3/ 3 4.
Major tcansients(1-2) 2
/ 2 1 112 %.
5.
EOPs entered/requiring substantive actions(12) 1 2
2/2 6.
EOP contingencies requiring substantive actions (02)
1
/ 2 t 2/ 2 ji 7.
Critical tasks (23) 2 v 2 / 412 A4 I
ES-301, Page 25 of 27
ES-301 Transient and Event CheckIst Form ES-301-5 FaciUty: Brunswick Nuclear Plant Dale of Exam: October 2014 Operating Test No: Final A
E Scenarios P
V
p 1
2 3
4 T
M L
N CREW POSITION CREW POS)TION CREW POSITION CREW I
T POSiTION I
c
M T
L u
v S
A B
S A
B S
A B
S A
B N
R T
0 R
T 0
R T
0 R
T 0
T p
a c
P 0
C P
0 C
P 0
C P
R IU E
RX 5
1 1
10 ROl NOR 2
1 111 Todd I/C 18
3,5,7
6 4
4 2
BIzzall MAJ 7,8 7
3 2
2 1
TS 0022 RX 1
1 110 RO 2 NOR
6
.i I I L 1/C 2,4,7 2,6,7 4,6,8 9
4 4
2 Rob Lax MAJ
7,8
-- 7 7 TS 0022 RX 5
1 2
110 SRO4JI NOR 6
2
1 I L I/C 1234 3456 12 4
4 2
Richard 7,8 7,8 Barrett MAJ 7,8
7
7 TS 2,3 3,4 4022 pJ(
4 1
1 10 R03 NOR 2
1 111 I/C 3,5,8 3,5,7 6
4 4
2 Hunter
Monis MAJ 7,8 7
3 2
2 1
TS 0022 RX
1 1
1 10 R04 NOR 6
1 2
1 1
1 I/C 2,4,7 2,6,7 4,6,8 9
4 4
2 Jason
Wiftiamson MAJ 7,8 7,8 7
5 2
2 1
is 0022 RX 4
1 2
110
$RO-U2 NOR 1
2
2 1
1 1
I/C 2,3,5,6, 3,4,5,6, 12 4
4 2
Jason 7,8 7,8 llms MAJ 7.8 7
3 2
2 1
[
TS 0,3 3,4 4
0 2
2
ES-301 Transient and Event Checklist Form ES-3O15 Facility: Brunswick Nuclear Plant Dale of Exam: October 2014 Operating Test No.: Final A
E Scenarios P
V
P E
1 2
3 4
T M
L N
CREW CREW POSLTION CREW CREW N
I T
POSmON
POSmON POSmON A
T S
A B
S A
8 S
A B
S A
8 L
A R
T 0
R T
0 R
T 0
R T
0 M
N 0
C P
0 C
P 0
C P
0 C
P T
R IU E
RX S
1 21 10 SRO-l1 NOR 6
. I I L
/C 1,2,3,4 2,6,7 4,6,8 12 4
4 2
Kyle
,7,8 Cooper 7
T 2
2 1
TS 2,3 2022 R)(
5 4
2 1
10 SRO-12 NOR
2
2 1 1 I/C 1,3,8 2,3,5,6, 3,5,7 12 4
4 2
Lucas 7,8 Hoggard MAJ
T 7 7 TS 0,3 2022 pJ(
4 1
2110 SRO-13 NOR
6 2
2 1
1 1
1/C 2,4,7 3,5,8 3,4,5, 12 4
4 2
Brian 6, 7,8 Moschet 78
7,8
T 7 7 T TS 3,4 2022 f)(
5 4
2110 SRO 14 NOR 6
1 1
1 1
I/C 1,2,3,4 3,5,8 9
4 4
2 Sabrina
,7,8 Salazar MAJ
78
T 7 7 E TS 23 2
0 2
2 RX 5
4 2
1 1
0 SRO 15 NOR
1
I I I L t/C 138 2356 9
4 4
2 Jason 78 Witte MM
78 78
4 2
2 1
rs
03 2022
C
Instructions:
1.
Check the applicant level and enter the operating test number and Form ESD-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-tho-controIs (ATC) and baIance-ot-pIant (BOP) positions; lnstant SROs 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 Instant SRO additionally serves in the BOF posrtion, one hG 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 1-for-i 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.
ES-301 Coinpetencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: October 2014 Operating Test No.:FinaI APPLICANTS RO-1 R02 RO-3 RO-4 Todd Bizzell Rob Lax Hunter Morris Jason Williamson Competencies Q.NiO_
1 234123412341234 lnterpretlDiagnose
2,4, 2,6, 4,6, 3,5, 3,5, 2,4, 2,6, 4,6, Events and 8
7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,5 7,5 Conditions Comply \\Nith and 1,3,5, 2,3, 2,4, 1,2.
1,4, 3,4, 2,3, 2,4, 1,2, 1,4, Use Procedures (1) 7,8,
57.
¶ Operate Control 2,3, 2,4, 1,2, 1,4, 3,4, 2,3, 2,4, 1,2, 1,4, Boards 2 7,8, 5,7, 6,7, 6,7, 6,7, 5,7, 5,7, 6,7, 6,7, 6,7,
8 8
8 8
8 8
8 8
8 Communicate ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Supervisory Ability (3)
Comply With and N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Use Tech. Specs. (3)
=
n
======_
=
Notes:
(1) includes Technical Specification compliance for an RO.
(2>
Optional for an SRO-U.
(3)
Only applicable to SROs.
Instructions:
Check the appllcantslicen.se type and enter one or more event numbers that will al/ow the examiners to evaluate every applicable competency for every applicant.
ES3OI Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: October 2014 Operating Test No, :Final APPLICANTS SRO-I1 SRO-12 SR013 SRO-14 Kyle Cooper Lucas Hoggard Brian Moschet Sabrina Salazar Competencies 1
23 4123412 341 234 Interpret/Diagnose 1,2,3, 2,6,7 4,67 1,3,7 0,2, 3,5,7 2,4,7 3,5,7 3,4,5, 1,2,3 3,5,7 Events 4,7,8
.8
,8
.8 3,S,
.8
,8
,8 6,7,8
,4,7,
.8 and Conditions 6,7,8 8
Comply With and ALL 1,2,6 1,4,6 1,3,5 ALL 2,3,5 2,4,6 3,4,5 ALL ALL 3,4,5 UseProcedures(1)
,7,8
.7,8
,7,8,
.7,8
,7,8
,7,8
,7,8
Operate Control N/A 1,2,6 1,4,6 1,3,5 N/A 2.3.5 2,4,6 3,4,5 N/A N/A 3,4,5 Boards(2)
Communicate ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate ALL N/A N/A N/A ALL N/A NIA N/A ALL ALL N/A Supervisory Ability (3)
Comply With arid 2,3 N/A N/A N/A 0,3 N/A N/A N/A 3,4 2,3 NIA Use Tech. Specs. (3)
= S
=
=
=
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 morn event numbers that will allow the examiners to evaluate every applicable competency for every applicant
ES-301 Competencies Checkllst Form ES-301 -6 Facility: Brunswick Date of Examination: October 2014 Operating Test No, :Final APPLiCANTS SRO-l5 SRO-Ul SRO-U2 Jason Witte Richard Barrett Jason Kerns Cornpetencies
1 2
3412 3412341234 Interpret/Diagnose 1,3,7 0,2, 1,2,3 3,4.5, 0,2, 3,4,5
,8 3,5,
.4,7, 6,7,8 3,5,
,6,7, 6,7,8 8
6,7,8 8
and Conditions Comply With and 1,3,5 ALL ALL ALL ALL ALL UseProcedures(1)
.7,8,
Operate Control 1,3,5 N/A N/A N)A N/A NIA Boards(2)
,7,B, Communicate ALL ALL ALL ALL ALL ALL and Interact Demonstrate NIA ALL ALL ALL ALL ALL Supervisory Ability L
Comply With and N/A 0,3 2,3 3,4 0,3 3,4 Use Tech. Specs. (3) =
= = =
C =
C =
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.
E$-401 BWR Examination Outline FORM ES-4O11 Facility Name: Brunswick Date of Exam: 10/2212014 RO K/A Category_Points SRO-Only_Points Tier Group K
K1K K
K K
A A
A A
G 1
2 1. 3 4
5 6
1 2
3 4
Total A2 G
Total 1
433 43 3
20 3
4 7
Emergency &
Abnormal 2
1 2
1 N/A 1
1 N/A 1
7 1
2 3
Plant
Evolutions Tier Totals 5
5 4
5 4
4 27 4
6 10 1
32322222332 26 2
3 5
2.
Plant 2
11111112111 12 0
1 2
3 Systems
TierTotals43433334443 38 3
5 8
- 3. Generic Knowledge and Abilities 1
2 3
4 1
2 3
4 Categories 3
3 2
2 10 1
2 2
2 Note:
1 Ensure that at least tM 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-anly outline, the 9ler ThIals in each K/A category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that specified In the table.
The final point total for each group and tier may devIate by t1 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 idenbfied on the assocIated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not Included on Ihe 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 shalt be selected.
Use the RD and SRO ratings for the RD and SRO-only portions, respectively.
8.
Select SF10 topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.
The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K1A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1.b of ES-401 for the applicable K/As, 8.
On the following pages, enter the K/A numbers,.a brief description of each topic, the topics importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment Is sampled in other than Category A2 or G on the SRO-onty exam, enter it on the left side of Column A2 for net 2, Group 2 (Note #1 does not apply>. Use duplicate pages for RD and SF10-only exams.
9.
For TIer 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401, Page 17 of 34
ES.401 BWR Examination Outline Form ES-401-1 Emer9ency and Abnormal Plant Evolutions - Tier 1/Group I (RO)
E!APE #1 Name! Safety Function G
KJA Topic(s)
IR 295001 PartIal or Complete Loss of Forced 0
Powerttlow d plritution 3,3 1
Core Flow Circulation I I & 4 2
95Q03 Partial or Complete Loss of AC 16 Whether a psrtie or complete loss of AC. power hoe ocwrrd 3,9 1
295004 PartIal or Total Loss of DC Pwr I 6 A.C &ectrtcai distribulion 3,4 1
295005 Main Turbine Generator Trip / 3 1
Preasure effects on reactor power 4
1 29500SSCRAM/1
Shutdownmarçri
!9501 6 Contml Room Abandonment / 7 Remote shutdown panel P1sntSpecitis 4.4 1
295018 Partial or Total Loss of CCW / 8
Backup systems 3.3 1
Ability to diagnose and recognIze trends in an accurate and 295019 PartIal or Total Loss of Inst. AIr / 8 timely manner uti zmng the appropdate cntrcl room tolerance 4.2 1
. material 295021 Loss of Shutdown Coollng/4 Natural oecuefon 3.6 1
!95023 Refueling Acc / 8 Radiation rnonitoftng equipment 3.4 1
295024 1-Ugh Dryweil Pressure/S Drwei ventilation system 3.4 1
295025 High Reactor Pressure / 3 HPCt operation Ptmt-Speoflc 3.8 1
295026 SuppressIon Pool High Water
- 1. Knowledge of the purpose and function of major system 4 1 1
rem p. /5 28 components end controls.
295027 HIgh Containment Temperature! 5
0 295028 High Drywell Temperature I 5 Reactor water level indication 3.6 1
295030 Low Suppression Pool Wir Lvi / 5 i(nowfedge of condfione and limitatIons itt tha factclly license.
3.6 1
295031 Reactor Low Water Level I 2 Reactor pressure 4.2 1
295037 SCRAM Condition Present arid 0
Reactor Power Above APRM Oownscale or 1
Reactor Protection System 4.6 1
Unknown I 1 95038 High Off-site Release Rate 19 Control morn ventilation Isolation: Ptant-Specitic 3.7 1
600000 Plant Fire On Site /8
0 Thegr,seaient of potential operational damage to plant i
700000 Generator Voltage and Electric Grid 0
V Reactor ord turbine tsp crterla 3.9 1
Disturbances 1 6 1
IK1ACategyT0taI5:
EILIEIEE L GroupPolntTotal:
201 ES-401, Page 18 of 34
a ES.401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions
- Tier 1/Group 2 (RO)
E1APE #1 Name / Safety Function G
KiA Topic(s)
IR 295002 Loss of Main Condenser Vac I 3 0
295007 High Reactor Pressure I 3 0
295008 HIgh Reactor Water Level 12 Reactor water level 3 9 1
295009 Low Reactor Water Level /2 0
295010 HIgh Drywell Pressure/S 0
295011 High Containment Temp 1 5 0
295012 High Drywell Temperature 1 5 0
295013 HIgh SuppressIon Pool Temp. I 5 0
295014 Inadvertent Reactivity Addition/ 1 nomal reaclkily addUon.
3.8 1
95015 Incomplete SCRAM / 1
çss&gTodinseftiorblocks 3.4 1
295017 HIgh Off-stte Release Rate / 9 0
295020 Inadvertent Cont. Isolation 1 5 & 7 0
295022 Loss of CRD Pumps / I a
295029 HIgh Suppression Pool Wtr LullS 0
295032 HIgh Secondary Containment Area 0
3.6 1
emperaturels 4
295033 High Secondary ContaInment Area
- 04. Ability to prioritize atid interpret The ilqnilicence f cacti 4
i Radiation Levels /9 45 anrurrdator or etarm.
95034 Secondary ContaInment Ventilation
0
S8TRVS Fant Speorc 4 3 1
High Radiation I 9 3
!95035 Secondary Containment High Differential Pressure I 5
!95036 Secondary Containment High 0
Radweste 2.8 1
Sump/Area Water Level / 5 3
500000 HIgh CTMT Hydrogen Conc. /5 0
RJA Category Totals:
1 2
1 1
1.
1 Group PoInt Total:
7 ES-401, Page 19 of 34
ES..401 BWR Examination Outline Form ESIa i-i Plant Systems - Tier 2iGroup I (RO)
KKKKKKAAAA System#/Name 1
2 3
4 5
1 2
3 0
K1ATopis)
IR 03000 RHRILPCI. injection Mode Suppression pool sssl: Pump disarge pressure 2
205000 Stiuldown CoolIng 0
Rescici cooldosin rate 3.6 1
5 0
0 TwtnUclcirqj,lsBWR.2 3,4;Hifisuppresalon 2.5; 2
4 poollamparalweOWR*2.,4 39
07000 lsoUon(Emeencv),
0 ondenser
?0900i LPCS Sptrmvenli,g 2,5 1
tm p09002 HPCS 0
211000 SLC s&ccnsrci 4.2 1
?12000RP$
RPSmoiorgeneratocoais 3.2 1
15003 IRM Reactorvaasel 3
1
!1 5004 Source Range Monitor
2
!15005APRM/LPRM Rev nfowc onelsupocate 3.4 1
nur 9TeWe iOT.JJ1ItLO 1 7000 RC1C 0
2 7
Q4 condbors for emergency nd abnormal opera1in 45
!1 8000 ADS ADS valve acoustical monfor opee: Ptarn-Specthc 3.7 1
23002 PCIS/Nudear Steam Supply 02.
effect of makilenance activiUes audi as deaded power sources, on Ue statuS of bntitlng 3.1 1
,nU On onditlons før vperstions.
239002 SRVs Plant air systems-PianI.Specific: C. power PlantSpedf,c 2
159002 Reactor Water Level Control Readorwrleveflndcation 3,4 I
61 000 SGTS Plimaryconlammontprasatjra 3,2 1
62001 AC Electrical Distribution Syschropeinctudtirgundeandin of runn og and 4
1
!62002 UPS (AC/DC)
Static kiverter 2,7 1
163000 DC Electrical Oistnbution Banery diar cliargag ste 2.5 1
264000 EDGe Load shaddw and oequnvg 3.2 1
300000 Instrument Air
. Contoinmentait system 2,7 1
100000 Component Cooling Water
- 4 ::r° 3
1
=
=
=
=
=
KIA Category Totals:
3 2
3 2
2 2
2 2
3 3
2 Group Point Total:
26 P
9 ES-401, Page 20 of 34
=-
ES.-401 BWR ExamInation Outline Form ES-401-1 Plant Systems
- Tier 2/Group 2 (Ri))
KKI(Ki<KAAAA System #1 Name 1
2 3
4 5
6 3
4 6
KIA Topic(s)
IR 01001 CR0 Hydrautc 0
0100RMCS Ovemilreactorpower 3.6 1
01003 Control Rod and Drive Mechanism Low reactor pressure 32 1
01004 RSCS o
01005 RCIS 0
01006 RVdM Steam how Input: PSpecNotBWR6) 2,7 1
02001 Recirculatton 0
02002 Reclrculation Flow Control 0
04000 RWCU 0
14000 RPIS C
ml red drive temperature 2.8 1
15001 TraversIng In-core Probe 0
15002 RBM 0
16000 Nuclear Boiler Inst.
ln,crurnenj tne pluggIng 2.9 1
19000 RHRILPCI: Tonis/Pool Cooling 2.5 1
lode 1
3001 PrimaryCTMT and Aux.
0 26001 Rt-IRILPCI; CTMT Spray Mode 0
30000 RHRIIPCI: Torus/Pool Spray Mode Valve eperation 3.4 1
33000 Fuel Pool CoolIng/Cleanup 0
34000 Fuel Handling Equipment 4
0 3g001 MaIn and Reheat Steam 0
39003 MSIV Leakage Control 0
41000 Reactor/Turbine Pressure Regulator 0
45000 MaIn Turbine Gen. I Aux.
Plant air systemS 2.5 1
56000 Reactor Condensate Control ol erriracilon steam 2.8 1
59001 Reactor Feedwater Turt.ra operaUca TORFPs.OnIy 2 8 1
68000 Radwaste 0
710000tfgas Condensacuuin 3.5 1
t72000 RadIatIon MonitorIng 0
166000 FIre Protection 0
B8000 Plant VentIlation 0
90001 Secondary CTMT 4
Knowledge of annunciator earne.
lIOflS (
4.2 1
90003 Control Rooni HVAC a
190002 Reactor Vasel Internals 0
IIII_IIIiIII II
</A Category Totals; I
1 ij 1 j I 1
1 I 21 1
1 1
Group PolntTotal 12 ES-401, Page 22 of 34
ES-401 BWR EaminaUon Outline Fern, ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group I (SRO)
K K
K A
A E/APE # / Name / Safety Function G
KJA TOpics) iR 12312 295001 Partial or Complete Loss of Forced 01.
Ability to interpret and execute procedure steps.
4 6 1
Core Flow Circulation / 1 8 4 20 295003 Partial or Complete Loss of ACI 6 0
295004 Partial or Total Loss of DC Pwr / 6 0
- 02. Knowledge of limiting conditions for operations and 4.7 1
295005 Main TurbNie Generator TrIp? 3 221 safety limits.
- 95006 SCRAM! 1 0
295016 Control Room Abandonment? 7 0
295018 PartIal or Total Loss of CCW /8 0
295019 PartIal or Total Loss of Inst. Air? 8 0
95021 Loss of Shutdown Cooling! 4 0
295023 Refueling Ace/B 0
295024 HIgh Drywell Pressure! 5 0
U4 Ability to priorilize and Interpret the significance of each 43 1
295025 High Reactor Pressure! 3 45 annuncIator or atanTr.
295028 Suppression Pool High Water emp,15 Suppressicnpoolwaler temperature 4.2 1
295027 HIgh Containment Temperature! 5 0
295028 High Drywell Temperature? 5 0
295030 Low Suppression Pool Wtr Lvi /5 2
Suppression pool temperature 3 9 1
UT CVTL ICTU TU yLTT UdTdTLTS 04.
that must be reported to Internal organizations or 295031 Reactor Low Water Level I 2 4.1 1
30 external agencies, such as the State, the NRC, or the 295037 SCRAM Condition Present
and Reactor Power Above APRM 0
Downscala or Unknown! I
0 295038 High Off-site Release Rate / 9 Radiation levels 4.3 1
3 500000 Plant Fire On Site I 8 0
1A 700000 Generator Voltage and Electric Grid 0
Disturbances! 8 11</A Category Totals:
0 0
0 0
3 j 4 Group Point Total:
I ES-401, Page 18 of 34
4.3 G
K/A Topic(s)
IR 04.
Knowtedge of the opecalionel Impticatlona of COP warnings, 20 cautions, and rotsa CR0 system afatun 02 AbIlity to Intenpret corttrcf room indicatiorn to verity the status and operation ole uystem, end rindecatand how operator actions
and directcaea affec* plant and system condlions 3.4 4.4 E)APE #1 Name / Safety Function ES-401 BWR Examination Outline Form ES.401..1I Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
95002 Loss of Main Condenser Vac 1 3 K
1<
K 123 II 0
295007 High Reactor Pressure / 3 295008 High Reactor Water Level I 2 295009 Low Reactor Water Level /2 295010 HIgh Drywell Pressure) 5 295011 HIgh Containment Temp / 5 295012 High Drywell Temperature/S 295013 HIgh Suppression Pool Temp. /5 295014 Inadvertent Reactivity Addition 1 1 295015 incomplete SCRAM / I 295017 High Off-site Release Rate / 9 95020 Inadvertent Cont. isolation / 5 & 7 295022 Loss of CR0 Pumps / 1 295029 High Suppression Pool Wtr Lvl/ 5 295032 High Secondary Containment Area omperaLure /5 295033 High Secondary Containment Area Radiation Levels) 9 0
0 0
0 0
0 0
0 0
0 1
0 U
295034 Secondary Containment Ventilation High Radiation/S 0
295035 Secondary Containment High Differential Pressure / 5 5036 Secondary Containment High Sum p/Area Water Level / 5 500000 HIgh CTMT Hydrogen Conc. /5 1K/A Category Totals:
0 f 0
0 0
1 2JGrouP Point Total:
0 0
0 3
ES-401, Page l9of 34
ES-401 BWR Examination CuiJIrie Fonti ES401-1 Plant Systems
- Tier 2/Group 1 (SRO)
K K
K 1<
K K
A A
A Ai System #1 Name 1
2 3
4 5
6 1
2 3
4 K/A Topic(s) iR 03000 RHR/LPCI: Injection Lass ot coolant acckent 4.5 1
05000 Shutdown Cooling Mode 0
06000 HPCI 0
07000 IsolatIon (Emergency) 0 ondenser 209001 LPCS 0
09002 HPCS 0
11000SLC 0
12000 RPS 0
UUWiUU UI flYOhIU JtflItU 14.3 UflIpull %Iflrpuun3pIaJ lId 15003 1RM 04 musIberspoteontemaiora:iooscrextemal 4 1 1
30 agencies. eich as the State, the NRC. o the ttansmssion 15004 Source Range Monitor 0
15005 APRM / LPRM Knoladge at condttons and thstahors m the tacibty 45 1
17000 RCIC 0
18000 ADS 0
23002 PCIS/NucJear Steam Supply 0
Shutoff 39002 SRVs 0
59002 Reactor Water Level Control 0
61000 SGTS
- 02. Knoiede of conditions and tmtaUons a the tacitly 45 1
62001 AC Electrical DIstribution 0
62002 UPS (AC/DC) 263000 DC Electrical Distribution o
64000 EDGs 0
300000 Instrument AIr 0
1400000 Component Cooling Water
[055 f CCW punp 3,4 1
jK/A Category Totals 0
0 0
0 0 f 0 J 0 2
0 0
3 Group Point Total 1
ES-401, Page 20 of 34
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems Tier 2/Group 2 (SRO)
System #1 Name Q
K/A Topic(s)
IR 01001 CR0 Hydraulic C
01002 RMCS 0
01003 Control Rod and Orlvo Mechanism 0
01004 RSCS 0
01005 RCIS 0
sunny no uagnnso gnu newpnizs USITOS In an acsrpw aria 01006 RWM Ilmely manner ulilizing the appropsale control room 4.2 1
.,,..i.,4-.I
02001 Recirculation 0
02002 Recitculatlon flow Control U
04000 RWCU 0
14000 RPIS I) 15001 TraversIng In-core Probe 0
15002 R8M 0
16000 Nuclear Boiler Inst.
0 19000 RHRILPCI: ThruslPool CoolIng de 23001 PrImary CTMT and Aux.
0 26001 RHRILPCI: CTMT Spray Mode 0
30000 RHR1I PCI: ToruslPvol Spray Mode 0
33000 Fuel Pool Coollng!Cleariup 0
34000 Fuel HandlIng Equipment 0
39001 MaIn and Reheat Steam 0
39003 MSIV Lea)rage Control 0
41000 Reactor/TurbIne Pressure Regulator 0
45000 MaIn TurbIne Gen I Aux 0
56000 Reactor Condensate 0
- 59001 Reactor Feedwater 0
68000 Radwasle a
71000 Offgas 0
72000 RadIation Monitoring
a 00 Fire Protection 0
88000 Plant VentilatIon 0
0001 Secondary CTMT nilenpret the significance of eacfln 4.3 1
0003 Control Room HVAC InWatiorufafiunc of fire orolection system 3.3 1
90002 Reactor Vessel Internals 0
1<1A CategoryTotals; 0
0J oI at Oj Oj 0 1
Oj 0 2
Group PolntTolaI:
1 ES-401, Page 21 of 34
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility Name Brunswick Date of Exam 10/22/2014 Category KIA#
Topic fO2!L 2.1 25 P.bmflty to interpret reference rratenals, Sucti graphs, curves, tables, etc.
3.9 1
2.1 27 Knowledge of system purpose and/or 3.9 1
2 1 31 iocate conlrd/5. end Indications, and to determine 11151 4 6 1
- 1.
they cornectty reflect the desired plant Iirrmjp.
Conduct of 2 1 Operations
2.1 2.1 39 Knowledge of conservative deciSion making practices, 4.3 1
Subtotal 3
1
2.2.
13 Knowledge of tagging arid clearance procedures.
4.1 1
2.2.
03 Knowledge of the design, procedural, and operational differences between unIts.
3.8 1
2.
2.2. 41 AbIlity to obtain and Interpret station electrical snd mechanical drawings 3.5 1
Equipment 2 2 Control 2.2. 03 Knowledge of lIre design, procedural, and operational differences between units.
3,9 1
2.2. 37 Atstlty to determine operability andior aelebility of safety related equipment.
4.6 1
Subtotal 3 $
2 Knmvedge of radiological sd/ely procedures pertaining to licensed operator dunes. liudi 2.3. 13 as response to radiation monitor alarms. cuntalmnenf entry requvements, fuel handling 3,4 1
esimi. acossa a ll ad Niafl-rethallon aresy IOri5 oLeni. er
A Knowledge of radiation or contamination hazards that may wise during normal, abnormal, 1
C..s..
or emergency condiitona or activities.
2.3.
Radiation 2 3 Control
2.3. 04 lriowledge of radiation enpesure limits under normal or emergency conditions, 3.7 1
5 Knowledge of radiation or contamination hazards that may arise during normal, abnormal,
or emergency conditions or actintles, Subtca 2
2 2.4.
Knowledge of tow power/shutdown implications in adent (e.g., toss ol coolant accident
or iota of rsidua) heat rernovel) mitigation strategies 3.8 4.
Emergency Procedures 1
rrfowiedge at the parameters arid logic used 10 assess the Stalds ci safety functions, iii
2.4. 21 as reactielfy control, core cooling and heat remouai, reactor cOolant system integrity.
4 1
td/rrmricvditons. md uc/:fv rd/ease oonird. pic.
2.4.
2.4.
2.4. 27 Xnowiedgeofflreintheplantprocedures 3.9 Subtotal 2.4. 45 Ability to prioritize and Interpret the lgnifkarrcs ci eedr annundator or alarm.
Point Total 4.3 2
ES-401 Record of Relected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group S&ected K/A SROT1 G 1 295001 G2.01.27 Cannot write an SRO knowtedge question to this KA 213114 CE provided replacement KIA of (32.01.20 SROT2G 1 21 5005G2.02,02 Cannot write an SRO knowledge question to this KA 2.13114 CE provided replacement KIA ol (32.0238 ROT2G2 290001 G2.04.34 No RO tasks far Secondary Containment outside Control Room 614114 CE replaced with (32.04.31 SROT2G1 261 000G2.02.39 Cannot write SRO level question on 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS 614114 CE replaced with (3202.38 ROTI GI 295021 AK1.04 Loss of SDC procedure does not address thermal stratllication, Per CE changed to 295021 AK1 04 instead.
ES-401, Page 27 of 33
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Brunswick Date of Exam. 10/22/14 Exam Lavet RO IZI SROZI Initial lam Description a
b c
1.
QuestIons and answers are technically accurate and applicable to the facility.
2.
a.
NRC K/As are referenced for all questions.
b.
Facility learning objectives are referenced as available, 3,
SRO questions are appropriate In accordance with Section D.2.d of ES-401 I.j 4.
The sampling process was random and systematic (If more than 4 RO or 2 SRQ questions A
were repeated from the last 2 NRC lIcensIng exams, consult the NRR DL program office).
5, Question duplication from the license screenlngiaudit 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 the licensee certifies that there is no duplication; or other (explain) 6.
Bank use meets limits (no more than 75 percent Bank I ModifIed I
New from the bank, at east 10 percent new, and the rest 1
I 9
)Sji new or modified); enter the actual RC) I SRO-only 35 8 I 2
/
3 I 38 / 14 question distribution(s) at right.
I I
7.
Between 50 and 60 percent of the questions on the RC)
Memory C/A exam are written at the comprehension! analysis level:
I the SRO exam may exceed 60 percent If the randomly I
,é 92 1L selected K/As support the hIgher cognitive levels; enter 30 1
6 I
45 1
19 the actual RD / SRO question distribution(s) at right.
I
B.
References/handouts provided do not give away answers 52 yt_
or aid In the elimination of distractors.
9.
Question content conforms with specific K/A statements in the previously approved
,44 99 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 9.
A 11.
The exam contains the required number of one-point, multiple choIce items; 92 jj the total Is correct and agrees with the value on the cover sheet.
Printed Name! Signature Date
- a. Author Robert Bohn
- b. Facility Reviewer >
Jerry PIerce ii/o,/,9
- d. NRC Regional SupervIsor (31zdi i.-
- c. NRC Chief Examiner (#)
Note:
- The facility reviewers Initials/signature are not applicable for NRC-developed examinations,
- Independent NRC reviewer Initial items In Column c; chief examiner concurrence required.
ES-401, Page 29 of 33
ES-401 Written Examination Review Worksheet Form ES-401-9 Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only RO Three of the five preliminary submittal RO test items were PRELIMINARILY determined to be unacceptable IAW NUREG 1021 for the following reasons:
Cred Dist: Q#s 4 & 5 K/A mismatch: Q#s 3, 4, & 5 LOD=1: Q#s 4 SRO Five of the five preliminary submittal SRO test items were PRELIMINARILY determined to be unacceptable IAW NUREG 1021for the following reasons:
Cred Dist: Q#s 7 SRO-only: Q#s 6, 7, 8, 9 & 10 Q=K/A: Q#s 6 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 using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
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:
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).
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).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
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 that are designated SRO-only (K/A and license level mismatches are unacceptable).
- 6.
Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
- 7.
Based on the reviewers 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 ratings (e.g., how the Appendix B psychometric attributes are not being met).
ES-401 2
Form ES-401-9 Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 1
H 2
N S
201002 REACTOR MANUAL CONTROL SYSTEM Al Ability to predict and/or monitor changes in parameters associated with operating the REACTOR MANUAL CONTROL SYSTEM controls including:
04 Overall reactor power 2
F 2
X B
E 201003 CONTROL ROD AND DRIVE MECHANISM A2 Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
09 Low reactor pressure The word single is not used in the I.A.s section. Change to use the word one in distractor A If one control rod scrams.
9/29 Agreed to change wording.
3 F
3 N
S 201006 ROD WORTH MINIMIZER SYSTEM (RWM)
K6 Knowledge of the effect that a loss or malfunction of the following will have on the ROD WORTH MINIMIZER SYSTEM (RWM):
05 Steam flow input 4
H 3
N S
203000 RHR/LPCI: INJECTION MODE Al Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI: INJECTION MODE controls including:
05 Suppression pool level
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 5
- 1P F
2 X
M?/B S
203000 RHR/LPCI: INJECTION MODE (A3) Ability to monitor automatic operations of the RHR/LPCI:
INJECTION MODE including:
(03) Pump discharge pressure.
The change to this question does not meet the criteria to be considered modified.
Change stem. 2nd sentence to read Reactor pressure is lowering.
3rd sentence. Delete RHR pump discharge and change to reactor pressure that will allow RHR injection flow to be seen on FI-XXX at Panel XX?
R: Licensee agrees that this is a bank question. Will change on QA sheet. Not modified.
7/24/14 Changes made by the licensee.
6 H
3 X
N E
S 205000 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)
K4 Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which provide for the following:
05 Reactor cooldown rate Does the stem need to contain information that shows that a heatup is occurring and Reactor water level? Why does the 2nd fill in the blank end with a ?.
9/24 Agreed to remove the question mark, no other corrections needed. No other modifications needed. The question is OK as written.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 7
F 3
X B
E S
206000 HIGH PRESSURE COOLANT INJECTION SYSTEM A2 Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
08 High suppression pool temperature: BWR-2,3,4 B does not appear plausible. Why would someone with GFES knowledge pick this? Choice C & D in comparison are related to high temperature issues.
9/24 Reworded distractor plausibility statement to better define benefit of warm water.
8 F
2 N
S 206000 HIGH PRESSURE COOLANT INJECTION SYSTEM K2 Knowledge of electrical power supplies to the following:
04 Turbine control circuits: BWR-2,3,4 9
F 3
N S
209001 LOW PRESSURE CORE SPRAY SYSTEM K5 Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM:
05 System venting 10 H
2 X
N E
S 211000 STANDBY LIQUID CONTROL SYSTEM A4 Ability to manually operate and/or monitor in the control room:
02 SBLC control switch A is not plausible. If someone thought that in distractor A that squib valve A failed to fire, why would they choose to place the corresponding pump to run? Shouldnt choice A state pump B?
9/24 Accepted distractor reasoning as is.
11 F
3 B
S 212000 REACTOR PROTECTION SYSTEM K2 Knowledge of electrical power supplies to the following:
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 12 H
2 N
E S
214000 ROD POSITION INFORMATION SYSTEM A4 Ability to manually operate and/or monitor in the control room; 03 Control rod drive temperature The question states that guidance is contained within the App. This is not true, the app references OP-8.0 to raise flow rate.
9/24 Agree the reference to the OP from the App is good enough.
13 F
2 B
S 215003 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM K1 Knowledge of the physical connections and/or cause effect relationships between INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM and the following:
07 Reactor vessel 14 F
1?
X X
B U
E 215004 SOURCE RANGE MONITOR (SRM) SYSTEM K3 Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM) SYSTEM will have on following:
02 Reactor manual control Isnt the highest number correct by default? LOD=1 R: Remove the words or above.
15 H
3 N
S 215004 SOURCE RANGE MONITOR (SRM) SYSTEM K5 Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM)
SYSTEM:
03 Changing detector position 16 H
3 N
S 215005 AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM A2 Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
06 Recirculation flow channels upscale
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 17 F
3 B
S 216000 NUCLEAR BOILER INSTRUMENTATION A2 Ability to (a) predict the 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:
02 Instrument line plugging BW does not have a procedure for a plugged instrument line, so this question was accepted to predict the effect on level indication and associated annunciators illuminated.
18 H
3 M
S 217000 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC)
A4 Ability to manually operate and/or monitor in the control room:
07 Reactor pressure 19 H
3 N
S 217000 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC)
G2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
20 H
3 N
S 218000 AUTOMATIC DEPRESSURIZATION SYSTEM A3 Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:
03 ADS valve acoustical monitor noise.
21 F
N S
219000 RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE K2 Knowledge of electrical power supplies to the following:
01 Valves 22 H
B S
223002 PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF G2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
23 H
N S
230000 RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY MODE A3 Ability to monitor automatic operations of the RHRILPCI:
TORUS/SUPPRESSION POOL SPRAY MODE including:
01 Valve operation
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 24 F
B S
239002 RELIEFISAFETY VALVES KI Knowledge of the physical connections and/or cause effect relationships between RELIEF/SAFETY VALVES and the following:
05 Plant air systems 25 F
B S
239002 RELIEF/SAFETY VALVES K6 Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES:
03 A.C. power 26 F
N S
245000 MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS KI Knowledge of the physical connections and/or cause effect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following:
07 Plant air systems 27 H
N S
256000 REACTOR CONDENSATE SYSTEM K4 Knowledge of REACTOR CONDENSATE SYSTEM design feature(s) and/or interlocks which provide for the following:
06 Control of extraction steam 28 H
N S
259001 REACTOR FEEDWATER SYSTEM K5 Knowledge of the operational implications of the following concepts as they apply to REACTOR FEEDWATER SYSTEM:
03 Turbine operation 29 H
B S
259002 REACTOR WATER LEVEL CONTROL SYSTEM K3 Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following:
07 Reactor water level indication 30 H
B S
261000 STANDBY GAS TREATMENT SYSTEM Ki Knowledge of the physical connections and/or cause effect relationships between STANDBY GAS TREATMENT SYSTEM and the following:
11 Primary containment pressure
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 31
- 2P H
4 X
N E
S 262001 A.C. ELECTRICAL DISTRIBUTION (A4) Ability to (a) predict the impacts of the following on the A.C.
ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (02) Loss of coolant accident.
Delete Orders sent out to crosstie E2 to E4.
Change Maint to the MAINT position for the 1202 and 1206 times.
Change Which onethat E4 can.. to that E4 is allowed to R: OK once changes have been confirmed.
7/24/14 Changes made by the licensee.
32 H
3 X
B E
S 262002 UNINTERRUPTABLE POWER SUPPLY (A.C. / D.C.)
K6 Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (AC/D.C.):
03 Static inverter The Big Notes drawing shows these as UPS not as inverters. Do you expect the applicant to know the DS numbers without reference to the drawing?
R: Will check and make changes if appropriate.
33 F
2 N
S 263000 D.C. ELECTRICAL DISTRIBUTION Al Ability to predict and/or monitor changes in parameters associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including:
01 Battery charging/discharging rate 34 H
B S
264000 EMERGENCY GENERATORS (DIESEL/JET)
K4 Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for the following:
(CFR: 41.7) 05 Load shedding and sequencing
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 35 H
X B
E S
271000 OFFGAS SYSTEM K3 Knowledge of the effect that a loss or malfunction of the OFFGAS SYSTEM will have on following:
(CFR: 41.5 /45.3) 01 Condenser vacuum Only one distractor is different from the others. Leading to the correct answer. Need to add another condensate/main condenser distractor.
R: Changed to remove diminish from stem. Not necessary. Accept Main Condenser vacuum.
36 H
N S
290001 SECONDARY CONTAINMENT G2.0431 Knowledge of annunciator alarms, indications, or response procedures.
37 F
?
E 295001 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION AKI Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
02 Power/flow distribution 2 Pedigrees listed? New & Bank (Which one is it?)
38 H
B S
295003 PARTIAL OR COMPLETE LOSS OF A.C. POWER AA2 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER:
05 Whether a partial or complete loss of A.C. power has occurred 39 H
B S
295004 PARTIAL OR COMPLETE LOSS OF D.C. POWER AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER:
03 A.C. electrical distribution
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 40 F
B U
S 295005 MAIN TURBINE GENERATOR TRIP AK1 Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP:
01 Pressure effects on reactor power Q84 is similar. Bases for Hi Lvl trip from main turb Trip. Need to change one of these.
Need to rewrite to prevent overlap with Q84.
Rewrote 2nd part to eliminate overlap.
41 H
N S
295006 SCRAM AK1 Knowledge of the operational implications of the following concepts as they apply to SCRAM:
02 Shutdown margin 42 H
B S
AA2 Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL:
01 Reactor water level 43 F
X N
E S
295014 INADVERTENT REACTIVITY ADDITION AK1 Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTIVITY ADDITION :
06 Abnormal reactivity addition C seems obvious when compared to choice A. Change A to insert control rods? This is also an IA to prevent a scram.
R: Agreed to change A to Insert control rods.
44 F
B S
295015 INCOMPLETE SCRAM AK3 Knowledge of the reasons for the following responses as they apply to INCOMPLETE SCRAM:
01 Bypassing rod insertion blocks 45 F
B S
295016 CONTROL ROOM ABANDONMENT AK2 Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following:
01 Remote shutdown panel
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 46 H
M E
S 295018 PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:
01 Backup systems Extra space on distractors C & D prior to DG4.
R: Not showing in LXR. No change needed.
47 H
N S
295019 PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR G2.04.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
48 F
X B
U S
295021 LOSS OF SHUTDOWN COOLING AK1 Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING:
02 Thermal stratification Doesnt match the KA. Where does thermal stratification enter into this?
R: There is no direct link to the KA for thermal stratification. The KA has been changed to better reflect the primary affect due to NC (AK1.04).
49 F
B S
295023 REFUELING ACCIDENTS AK2 Knowledge of the interrelations between REFUELING ACCIDENTS and the following:
03 Radiation monitoring equipment 50 H
X N
E 295024 HIGH DRYWELL PRESSURE EA1 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:
14 Drywell ventilation system Are the switches referred to as Override switches or a DW Cooler control switches?
R: DW Cooler control switch bullet not needed and will be removed.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 51 H
N S
295025 HIGH REACTOR PRESSURE EK3 Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE:
03 HPCI operation 52 H
N S
295026 SUPPRESSION POOL HIGH WATER TEMPERATURE G2.01.28 Knowledge of the purpose and function of major system components and controls 53 H
B S
295028 HIGH DRYWELL TEMPERATURE EK2 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following:
03 Reactor water level indication 54 H
X N
E S
295030 LOW SUPPRESSION POOL WATER LEVEL G2.2.38 Knowledge of conditions and limitations in the facility license Change to say LCO & PCCP entry required or PCCP entry ONLY.
R: Change 2nd question to match above.
55 H
N S
295031 REACTOR LOW WATER LEVEL EA2 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:
03 Reactor pressure There is no correlation for determining reactor pressure from level indication but there is from the opposite direction therefore I accepted this question to meet the K/A.
56 H
N S
295032 HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EK2 Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA TEMPERATURE and the following:
04 PCIS/NSSSS 57 F
B S
295033 HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 58 H
N E
S 295034 SECONDARY CONTAINMENT VENTILATION HIGH RADIATION EK2 Knowledge of the interrelations between SECONDARY CONTAINMENT VENTILATION HIGH RADIATION and the following:
03 SBGT Alarm window in the explanation is incorrect, not (5-4), should be (3-5).
59
- 3P H
3 X
B S
295036 SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL (EA1) Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL : (03) Radwaste Distractor B not plausible. SCCP doesnt list this action; none of the EOIs list this action.
R: Licensee explained that Isolate primary system discharge is in the procedure, must reset RPS to achieve but cant with High DW press.
60 H
N S
295037 SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN EA1 Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:
01 Reactor Protection System 61 H
X N
E S
295038 HIGH OFF-SITE RELEASE RATE EK3 Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE:
03 Control room ventilation isolation by processing intake air through the filter trains is in all distractors and is not needed. Should B2 & D2 state both the MCR and all areas? Otherwise, it is not plausible to have a combination of MCR only with isolating ventilation in the control bay.
R: Change wording to match areas of the plant.
62 H
N S
300000 INSTRUMENT AIR SYSTEM K3 Knowledge of the effect that a loss or malfunction of the INSTRUMENT AIR SYSTEM will have on the following:
01 Containment air system
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 63 H
B S
400000 COMPONENT COOLING WATER SYSTEM (CCWS)
A3 Ability to monitor automatic operations of the CCWS including:
01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS 64 F
X N
E S
600000 PLANT FIRE ON SITE AA2 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:
04 The fires extent of potential operational damage to plant equipment Change A to CSW Pump 1B to make distractor A more plausible.
Change D to CRD Pump 1B to make distractor D plausible.
R: Agreed to change as noted.
65 H
B S
AK3 Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:
01 Reactor and turbine trip criteria 66 H
X B
E S
G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Change to give exact generator pressure and MWe values.
R: Will put in actual values.
67 F
B S
G2.1.27 Knowledge of system purpose and/or function 68 H
B S
G2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup 69 F
B S
G2.2.03 (multi-unit license) Knowledge of the design, procedural, and operational differences between units.
70 F
N S
G2.2.13 Knowledge of tagging and clearance procedures
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 71
- 4P F
1 3
X X
U S
G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.
LOD 1. GFES question. Distractors C & D not very plausible. KA not met. This question is answered w/o reference required.
R: Suggested ways to rewrite using a P&ID reference.
7/24/14 New question written that is a LOD > 1 and meets the KA.
72 F
N S
G2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
73
- 5P F
2 X
X E
S G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
Does not meet the KA statement.
A not plausible, only performed while SD or in an outage.
C not plausible, stem conditions dont support any HWC items to support a HWC malfunctions D not plausible, only performed while SD or in an outage.
This is a conductivity question per the plausibility distractor analysis.
Only need to know that resin affects conductivity to answer the question. The KA is for radiation or radiological contamination. Also, not a HCL.
R: OK with question, add radiation affects to plausibility statements.
Chemicals are added at power therefore original reasoning for unsat removed.
74 H
N S
G2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
75 H
3 N
S G2.4.21 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.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 76
- 6P F
3 X
X X
N U
S 201006 ROD WORTH MINIMIZER SYSTEM (RWM) G2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
Does not meet the KA. Does not test ability to diagnose/recognize trends; the 1st sentence in the stem is not needed. Question is not technically correct as the LPAP is not entered at 19.1% steam flow.
(Its actually in the transition zone). Also the question as written in not operationally valid. Uses backwards logic.
Note: LP gives information pertaining to inverse video when in the transition zone.
R: Reword question to include CR reference to apply transition zone criteria.
7/24/14 Changes made by the licensee.
77 F
B U
S 203000 RHR/LPCI: INJECTION MODE A2 Ability to (a) predict the impacts of the following on the RHR/LPCI:
INJECTION MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /45.6) 16 Loss of coolant accident Doesnt appear to meet the KA on 1st pass. Only a one part question, part (b) is not addressed. How does this predict the impact on RHR/LPCI injection Mode?
R: Upon review with licensee, agreed with license logic for relationship with LPCI logic.
78 H
N S
215003 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM G2.04.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
79 F?
X N
U E
215003 AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM G2.2.38? Knowledge of conditions and limitations in the facility license.
Question KA does not match sample plan approved number.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 80 H
2 N
E S
261000 STANDBY GAS TREATMENT SYSTEM G2.02.38 Knowledge of conditions and limitations in the facility license.
Distractor B does not appear plausible. You tell them this is a 31 day ST so why would someone think it is a monthly ST?
9/4/14 Reviewing still to replace B distractor.
Question modified to change distractor B.
81 H
3 N
E S
290001 SECONDARY CONTAINMENT G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.
Stem Focus: Go over all the items listed and verify they are needed for either the answer or the distractor analysis. With the information given, do you need to tell them the release if via the blowout panels?
9/4/14 Remove blowout panels and change 1st question to would be considered 82 H
2 X
N U
E S
290003 CONTROL ROOM HVAC A2 Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
04 Initiation/failure of fire protection system.
Changes made to correct updated logic changes to the system..
83 H
2 M?
2010-2 NRC E
S 295001 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION G2.1.20 Ability to interpret and execute procedure steps.
Did not include the question that this question was modified from. I cant analyze that this meets the modified criteria w/o the original question.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 84 F
2 X
N U
E S
295005 MAIN TURBINE GENERATOR TRIP G2.2.22 Knowledge of limiting conditions for operations and safety limits.
A is also a correct answer. Subset issue: 23% power is defined as part of MODE 1 therefore this is also correct. 2nd part of question stem is confusing. You state hi water level twice. This is unnecessary. The basis for the indirect high water level scram from the main turbine trip instrumentation is to Need to change choice of hi level trip to protect turbine to something else, the correct choice is obvious by eliminating hi level trip to protect the turbine.
9/4/14 Changed wording in 2nd question to simplify the question.
85 H
2 X
B 2010-1 NRC Exam U
E S
295015 INCOMPLETE SCRAM G2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.
Could this be answered solely through use of procedure hierarchy?
The only info given is that an ARP is in alarm using the EOPs.
Would you go use an OP is this situation? OP-19 is not referenced in this ARP. OP-17(RHR) is referenced for draining the Torus.
Also, the HPCI System lesson plan states that Operation below 2100 rpm may result in failure of the AOP due to repeated cycling.
This does not agree with your plausibility for choice C & D. If anything, someone could confuse this with bearing damage also.
9/4/14 Changed choice to HPIC Hard card for injection.
86 H
2 X
X B
2008 NRC Exam U
E S
295022 LOSS OF CRD PUMPS AA2 Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS: 02 CRD system status.
Wouldnt an RO know that he can control the CRD flow controller in manual via the normal OP? Add the words to 2nd half question to state its following a loss of a CRD Pump. AOP-2.0 step that reference OP is not included as reference.
9/4/14 Licensee agreed to add the words to the 2nd part to improve plausibility of the 2nd question.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 87 H
3 X
M 2004 NRC Exam E
S 295025 HIGH REACTOR PRESSURE G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.
Wording of 1st question is weak and could lead to subset issue.
Change to say that To obtain the above indications, Rx pressure reached a maximum pressure of no less than.
9/24 Agreed with wording on the question that the license used.
88
- 7P H
2 X
X N
U S
295026 SUPPRESSION POOL HIGH WATER TEMPERATURE (EA2) Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: (01)
Suppression pool water temperature.
C is not plausible. This would meet the RO responsibility. If the RO is responsible for knowing that at 95 degrees the alarm is received and expected for placing HPCI in test mode then distractor A is not plausible. Otherwise, you could never perform the test and not be a TS condition to suspend the test.
Also the correct answer D is a non-LCO entry criterion. Could argue there is no correct answer.
R: Plant is still reviewing.
7/24/14 Changes made by the licensee. Not SRO Only. Distractor C
& D determined as untrue using RO Knowledge of immediate Rx trip criteria and determination of what SP bulk water temperature.
Will hold question until validation results come in? Will ask the SRO validators if RO knowledge to eliminated choice C & D.
9/4/14 Licensee stated that the RO would not know this is TS required information.
89 H
3 B
2007 NRC Exam S
295030 LOW SUPPRESSION POOL WATER LEVEL EA2 Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:
02 Suppression pool temperature.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 90 H
2 X
N E
S 295031 REACTOR LOW WATER LEVEL G2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
In the stem, state that the Rx mode switch is placed in SD as directed per GOI Verified GP procedure contains step to place mode switch in SD.
Also changed A to 4 hrs vs. 1 hr.
91 H
3 N
E S
295033 HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS G2.02.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
Missing Attachment referenced in the question? Also, verify this is not a direct lookup.
Reference provided.
92 H
3 N
S 295038 HIGH OFF-SITE RELEASE RATE EA2 Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: 03 Radiation levels 93 F
2 N
S 400000 COMPONENT COOLING WATER SYSTEM (CCWS)
A2 Ability to (a) predict the impacts of the following on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: 01 Loss of CCW pump.
Only addresses the 1st half of the KA statement. OK 94
- 8P H
3 X
M?
BFN Bank U
E S
G2.1.39 Knowledge of conservative decision making practices.
ROs IAs are to trip the unit if THI is entered.
R: Will rewrite question for scram but that is not RO knowledge.
7/24/14 Changes made by the licensee. Modified? Original question not included.
A comma is required in choice A. (WithMODE 1,). What procedure contains the criteria to scram the unit?
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 95 F
2 N
E S
G2.2.3 (multi-unit license) Knowledge of the design, procedural, and operational differences between units.
The combination in Distractor C does not seem plausible.
9/4/14 Agree with plausibility.
96
- 9P H
3 X
M?
2008 NRC Exam U
E S
G2.2.37 Ability to determine operability and/or availability of safety related equipment.
Dont need to give Limit (Secs) in the stem, this is given in the TS.
Position misspelled.
Distractor D not plausible. LCO 3.1.5 never directs BOTH actions.
Distractor C is technically correct. It does have to be declared SLOW or INOP.
R: Plant will continue working on to clear up.
7/24/14 Changes made by the licensee. Remove the reference provided from all questions on the exam. INOPERABLE is always correct for this question therefore A & C not plausible.
Will reword to say will SLOW or not SLOW.
97 F
2 B
2007 NRC Exam S
G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
98 H
2 B
2010-2 NRC Exam S
G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
B/M/N
- 7.
U/E/S
- 8.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 99
- 10P H
2 X
X B
2008 NRC Exam U
S G2.4.27 Knowledge of fire in the plant procedures.
Not SRO Only. C & D can be determined using RO knowledge.
Why do we need to tell them that they are in the General Fire Plan?
Stem states you do NOT enter AOP-32, therefore why would you enter the procedure after entering the two procedures given? Not logical.
R: Reviewing still to make corrections. Suggested asking basis for the mitigating action of a step within the procedure.
7/24/14 Changes made by the licensee.
100 H
2 X
N E
S G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.
4th bullet should be followed by 5th bullet Inboard and Outboard MSIV logic lights are illuminated.
ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility:
Date of Exam:
tG)2-1 lf Exam Level: RO1 SROL Initials Item Description a
b c
1.
Clean answer sheets copied before grading
- lc 2.
Answer key changes and question deletions justified and documented C°3 f) 3.
Applicants scores checked for addition errors rv2 (reviewers spot check> 25% of examinations) r 4.
Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail 7
flY 5.
All other failing examinations checked to ensure that grades f
are justified (i..io&iI 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 i6.er xk
- b. Facility Reviewer(*)
eieCe
- c. NRC Chief Examiner(*)
L43
-Ld
- d. NRC Supervisor (*)
vtC\\
I2//23i j
(*)
The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
ES-403, Page 6 of 6