ML032480796
| ML032480796 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 08/11/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Rosalyn Jones Duke Energy Corp |
| Shared Package | |
| ML032521014 | List: |
| References | |
| 50-269/03-301, 50-270/03-301, 50-287/03-301, NUREG-1021, Rev 9 50-269/03-301, 50-270/03-301, 50-287/03-301 | |
| Download: ML032480796 (47) | |
See also: IR 05000269/2003301
Text
Administrative Documents
OCONEE JUNE 2003 EXAM
50-26912003-301
JUNE 16 .
27. 2003
4/
Exam Preparation Checklist ....................
d
.
Exam Outline Quality Checklist
. . . . . . . . . . . . . . . . .
4
.
Exam Security Agreement .....................
A .
A .
Administrative Topics Outline (Final) . . . . . . . . . . . . . ES-301-1
Control Room Systems and Facility Walk-through Test Outline
(Final) ....................................
Operating Test Quality Check Sheet . . . . . . . . . . . . . ES-301-3
./6 .
Jf .
Simulator Scenario Quality Check Sheet . . . . . . . . . . ES-301-4
Transient and Event Checklist . . . . . . . . . . . . . . . . . . ES-301-5
df
J 9 .
Competencies Checklist ......................
dl @ Written Exam Review Worksheet . . . . . . . . . . . . . . . . ES-401-9
&@Written
Exam Grading Quality Checklist . . . . . . . . . . ES-403-1
-40 . Written Exam Quality Check Sheet . . . . . . . . . . . . . . ES-401-7 + -b
4
. Post-Exam Check Sheet ......................
\\
Examination Preparation Checklist
Form ES-201-1
Target
Date*
-180
Facility: Oconee Nuclear Station
Examinations Developed by:
Facility: Operating Exam I NRC : Written
Date of Examination: June 16-26,2003
Chief
Initials
rfa
Task Description I Reference
Examiner's
1. Examination administration date confirmed (C.1.a; C.2.a & b)
-120
-120
-120 I 2. NRC examiners and facility contact assigned (C.1.d; C.2.e)
I
rfa
3. Facility contact briefed on security & other requirements (C.2.c)
4. Corporate notification letter sent (C.2.d)
rfa
rfa
-45
-30
-14
-14
-14
[-go] I [5. Reference material due (C.1.e; C.3.c)l
I
rfa
-
~
~
8. Proposed examinations, supporting documentation, and
9. Preliminary license applications due (C.l .I; C.2.g; ES-202)
I O . Final license applications due and assignment sheet prepared
11. Examination approved by NRC supervisor for facility licensee
12. Examinations reviewed with facility licensee (C.1 .j; C.2.f & h; C.3.g)
rfa
reference materials due (C.1.e. f, g & h; C.3.d)
rfa
rfa
(C.1.l; C.2.g; ES-202)
rfa
review (C.2.h; C.3.f)
rfa
-75
1 6. Integrated examination outline(s) due (C.1.e & r; C.3.d)
I
rfa
-7
--70-
1 7~Exam~ation
&tline(s) reviewed by NRC and feedback provided
to facility licensee (C.2.h; C.3.e)
15. Proctoring/written exam administration guidelines reviewed with
facility licensee and authorization granted to give written exams
(if amlicable) (C.3.k)
13. Written examinations and operating tests approved by
-7
I
NRC supervisor (C.2.i; C.3.h)
I
14. Final applications reviewed; assignment sheet updated; waiver
-7
I
letters sent (C.2.g, ES-204)
16. Approved scenarios, job performance measures, and questions
-7
I
distributed to NRC examiners (C.3.i)
Target dates 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 to examinations prepared by the NRC.
1
23 of 25
NUREG-1021, Draft Revision 9
Task Description
a.
Verify that the outline(s) fit@) the appropriate model per ES-401.
1 N 6 7 r Q L $ u d n , m C
Examination Outline Quality Checklist
Form ES-201-2
Initials
a
b
c#
Ll
I b.Sh
Item
1.
w
R
i
T
T
E
N
2.
s
i
M
,bo 3.
I
- . T
-
4.
G
E
N
E
R
A
L -
n
I
/ I -
0
Assess whether the OLtllne was systemat cally ana ranoomly prepare0 in accordance w lh
Seciion D 1 of ES-401 and whether a WAcategones are appropriately samp eo.
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. (i, I
I IA I
-
I
I
I
d.
Assess whether the justifications for deselected or rejected WA statements are appropriate.
fi\\
a. Verify that:
(1) the outline(s) contain@) the required number of control room and in-pian1 tasks,
(2) no more than 30% of the test material is repeated from the last NRC examination,
(3) no tasks are duplicated from the applicantsaudit test s , and
b. Verify that:
(1) the tasks are distributed among the safety function groupings as specified in ES-301,
(2) one task is conducted in a low-power or shutdown condition,
(3) 4 - 6 (2-3 for SRO-U) of the tasks require the applicant to implement an alternate path
the licensees exam banks.
or abnormal condition, and
equired administrative topics are covered, with emphasis on performance-
I
r
i
e.
Check the entire exam for balance of coverage.
a. Author
b. Facility Reviewer ()
c. NRC Chief Examiner (#)
d. NRC Supervisor
Note:
- Not applicable for NRC-developed examinations.
- independent NRC reviewer initial items in Column c:
chief examiner concurrence required,
Examination Outline Quality Checklist
Form ES-201-2
s-201
inal Submittal
Facility: Oconee
Date of Examination: June 16, 2003
Item -
1.
W
R
I
T
T
E
N
2.
S
I
M
-
-
3.
w
/
T
Task Description
NRC examination,
are distributed among the safety function groupings as specified in ES-301,
is conducted in a low-power or shutdown condition.
for SRO-U) of the tasks require the applicant to implement an alternate path
or abnormal condition, and
a. Author
b. Facility Reviewer (*)
6- 5-&03
c. NRC Chief Examiner (#)
d. NRC Supervisor
Note:
- Not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column "c:" chief examiner concurrence required
NUREG-1021, Draft Revision 9
a,
5
I I I I I I
I I I I I I
a
a
3-301
Administrative Topics Outline
Form ES-301-1
Facility: Oconee
Examination Level (circle one): RO / SRO
Date of Examination: June 16,2003
Operating Test Number:
Administrative Topic
Conduct of Operations
GEN 2.1.23 (3.9/4.0)
Conduct of Operations
GEN 2.1.7 (3.714.4)
Equipment Control
GEN 2.2.12 (3.013.4)
Radiation Control
GEN 2.3.4 (2513.1)
Describe activity to be performed
CRO-203, Calculate Final SFP Boron Concentration
OP/1&2/Al1104/006 C (SFP Makeup), Enclosure 4.9 (SFP
Makeup With DW) (group activity) (new) (IO min)
CRO-043, Perform Manual RCS Leakage Calculation;
PT/0600/010 (RO Only) (group activity) (18 min)
CRO-204, Perform weekly surveillance test to
determine RIA40 setpoint
PT/230/001 Encl. 13.10 (Operation of RIA-40)
(new) (20 min)
CRO - 205, Calculate the Maximum Permissible Stay
Time Within Emergency Dose Limits (group activity)
(new) (20 min)
Note: All items (5 total) are required for SROs. RO applicants require only 4 items
unless they are retaking only the administrative topics, when 5 are iequired.
NUREG-1021, Draft Revision 9
Administrative Topics Outline
Form ES-301-1
inial Submittal
Facility: Oconee
Examination Level (circle one): RO / SRO
Date of Examination: June 16,2003
Operating Test Number:
Administrative Topic
Conduct of Operations
GEN 2.1.23 (3.914.0)
Conduct of Operations
GEN 2.1.3 (3.013.4)
Equipment Control
GEN 2.2.12 (3.013.4)
Radiation Control
GEN 2.3.4 (2.5/3.1)
GEN 2.4.38 (2.2/4.0)
Describe activity to be performed
CRO-203, Calculate Final SFP Boron Concentration
OP/1&2/A/I 104/006 C (SFP Makeup), Enclosure 4.9 (SFP
Makeup With DW) (group activity) (new) (10 rnin)
JPM-003, Evaluate Overtime Eligibility
OMP 2-01 Attachment "C", NSD 200 (SRO only)
(25 rnin)
CRO-204, Perform weekly surveillance test to
determine RIA40 setpoint
PT/230/001 End. 13.10 (Operation of RIA-40)
(new) (20 min)
CRO - 205, Calculate the Maximum Permissible Stay
Time Within Emergency Dose Limits (new)
(20 min)
SRO-206, Determine Emergenqy Classification and
'rotective Action Recommendations (SRO only)
- group activity) (new)
120 min)
Jote: All items (5 total) are required for SROs. RO applicants require only 4 items
inless they are retaking only the administrative topics, when 5 are required.
NUREG-1021, Draft Revision 9
Control Roomlln-Plant Outline
Form ES-301-2
'inial Submittal
Facility: Oconee
Date of Examination:
Exam Level (circle one): RO l SRO(I) l SRO(U) Operating Test No.:
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title
Type Code*
Safety
Function
@ CRO-200, Makeup to the LDST
OP/l103/004 (Soluble Poison Control)
[KA: 004 A4.13 (3.312.911 (new) (15 min)
1
(..&
CRO- 083, Re-establish RCS letdown flow
AP/32 (Loss of Letdown)
[KA: 004 A2.07 (3.4/3.7)] (IO min)
M, A, S
2
c. CRO- 066, Perform Required Actions for RCS Pressure S
3
550 psig EOP End. 5.1 (ES Actuation)
[KA: EPEOll EA1.13 (4.1/4.2)] (15 min)
D, A, S
3 CRO-013, Align MDEFDWP Suction to the Hotwell and
Feed the SGs
D, L, F !L
4s
EOP End. 5.9 [KA: APE054 AA1.01 (4.514.411 (IO min)
'-e.
CRO-201, Restart RCP
--
EOP, Encl. 5.8 [KA: 003 A4.06 (2.9*/2.9)] (new) (20 min)
I
4p
@ CRO-009, Following a Keowee Emergency Start Transfer
from CT-4 to CT-5
OP/O/NI 106/079 Encl. 4.12
[KA: 062 A4.01 (3.3/3.1)] ( I O min)
g. CRO-202, Reset RIA40 setpoints and enter the OAC Pri to
Sec Admin Limit
PT/230/001 Encl. 13.10 (Operation of RIA-40)
[KA: 073 A4.02 (3.7/3.7)] (new) (IO min)
D, L, S
N, S
6
7
@ CRO-114 Align Intake Canal For Recirc On Dam Failure
AP/13 (Dam Failure), [KA: 075 A2.01 (3.0/3.2)] (15 min)
D, L, A, S
8
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
NLO-022, Station ASW Pump Alignment
(last exam) (12 min)
supply power to the SSF ASW and SSF RCMU pumps
, AP/25, [KA: 062 A2.11 (3.7/4.1)] (IO min)
Service Air Header
D
8
AP/32, Encl. "Emergency Start of the Diesel Air Compressor",
[KA: APE-065 AA1.04 (3.5*/3.4*)] ( I O min)
EOP Encl. 5.10 [KA: APE054 AA1.01 (4.5/4.4)]
D. R, L
4s
3 CRO-47, Emergency start SSF Diesel Generator and
0
NLO-007, Start Diesel Air Compressor And Align To
M, A, L
6
Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room,
S)imulator, (L)ow-Power, (R)CA
NUREG-1021, Draft Revision 9
Control Roomlln-Plant Outline
Form ES-301-2
inial Submittal
Facility: Oconee
Date of Examination:
Exam Level (circle one): RO / SRO(I) l SRO(U) Operating Test No.:
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
-~
System l JPM Title
@ CRO-200, Makeup to the LDST
OP/1103/004 (Soluble Poison Control)
[KA: 004 A4.13 (3.3/2.9)] (new)
N, S
1
T
C
E
-
083, Re-establish RCS letdown flow
AP132 (Loss of Letdown)
[KA: 004 A2.07 (3.4/3.7)]
M, A, S
2
a
CRO- 066, Perform Required Actions for RCS Pressure .S
3
550 psig EOP Encl. 5.1 (ES Actuation)
[KA: EPEOII EA1.13 (4.1/4.2)]
D, A, S
4s
L A
7
CRO-013, Align MDEFDWP Suction to the Hotwell and
Feed the SGs
EOP End. 5.9 [KA: APE054 AA1.01 (4.5/4.4)]
D, L, 9
3. CRO-201, Restart RCP
EOP, End. 5.6 [KA: 003 A4.06 (2.9*/2.9)] (new)
-~
f.
CRO-202, Reset RIA40 setpoints and enter the OAC Pri to
PT/230/001 Encl. 13.10 (Operation of RIA-40)
[KA: 073 A4.02 (3.7/3.7)] (new)
g. CRO-IIA, Align Intake Canal For Recirc On Dam Failure
Sec Admin Limit
N, S
7
\\ AP/13 (Dam Failure), [KA: 075 A2.01 (3.0/3.2)]
D, L, A. S
8
n-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
0
NLO-022, Station ASW Pump Alignment
EOP Encl. 5.10 [KA: APE054 AA1.01 (4.5/4.4)]
D, R, L
4s
(last exam)
supply power to the SSF ASW and SSF RCMU pumps
AP125, [W 062 A2.11 (3.7/4.1)]
NLO-007, Start Diesel Air Compressor And Align To
Service Air Header
D
8
AP132, Encl. "Emergency Start of the Diesel Air Compressor",
[KA: APE-065 AAI 04 (3.5*/3.4*)]
9
CRO-47, Emergency start SSF Diesel Generator and
M, A. L
6
7. a
Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path,
C)ontrol room, (S)irnulator, (L)ow-Power, (R)CA
NUREG-1021, Draft Revision 9
Control Room/ln-Plant Outline
Form ES-301-2
3 NLO-022, Station ASW Pump Alignment
EOP Encl. 5.10 [KA: APE054 AA1.01 (4.5/4.4)]
(last exam)
inial Submittal
Facility: Oconee
Date of Examination:
Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.:
D, R, L
4s
~
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title
@ CRO- 083, Re-establish RCS letdown flow
AP/32 (Loss of Letdown)
[KA: 004 A2.07 (3.4/3.7)]
b CRO- 066, Perform Required Actions for RCS
'
Pressure 5 550 psig EOP Encl. 5.1 (ES Actuation)
[KA: EPEOII EA'f.13 (4.1/4.2)]
a
CRO-202, Reset RIA40 setpoints and enter the
OAC Pri to Sec Admin Limit
PT/230/001 End. 13.10 (Operation of RIA-40)
[KA: 073 A4.02 (3.7/3.7)] (new)
n-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
Type
Code*
N, S
Safety
Function
2
@ NLO-007, Start Diesel Air Compressor And Align
To Service Air Header
AP132, End. "Emergency Start of the Diesel Air
Compressor", [KA: APE-065 AA1.04 (3.5*/3.4*)]
8
Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path,
C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
NUREG-1021, Draft Revision 9
Operating Test Quality Checklist
Form ES-301-3
1. GENERAL CRITERIA
t-
a.
The operat'ng test conforms w lh the prev.ous {approved OLI :ne; changes are cons'stent wltn
sampling req. rements (e.9.. 10 CFR 55.45, operat ona. importance, safety f.nct on distrnbution).
There is no day-to-oay repetit on between th's and other operating tests 10 De admin'stered
dLr.ng th s examhat on.
Tne operating test shall nor dcpliwte items from the appliwnls' aLo:t test(s)(see Section D.l .a).
Overap w'tn the wrillen exam nat on and Detween different parts of the operat ng lest is w Ih n
acceptable lim'ts.
b
C.
d.
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:
w
. 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
. specific performance criteria that include:
- detailed expected actions with exact criteria and nomenclature
- system response and other examiner cues
- statements describing imporiant 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.
Repetition from operating tests used during the previous licensing examination is within
acceptable limits (30% for the waltthrough) and do not compromise test integrity.
Printed Name / Signature
Date
a. Author
5-s-J-3 *;
b. Facility Reviewer(*)
c. NRC Chief Examiner (#)
d. NRC Supervisor
44/03
NOTE:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column "c:" chief examiner concurrence rewired.
NUREG-102?, Draft Revision 9
Operating Test Quality Checklist
Form ES-301-3
- inal Submittal
1. GENERAL CRITERIA
k-
Initials
I
a.
The operating test conforms with the previously approved outline; changes are consistent with
sampling requirements (e.g.. 10 CFR 55.45, operational importance. safety function distribution).
There is no day-to-day repetition between this and other operating tests to be administered
during this examination.
- W-
b.
b
C.
d.
The operating test shall not duplicate items from the applicants' audit test(s)(see Section D.1.a).
Overlap with the written examination and between different part9 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 CRiTERlA
-
L4
a.
Each JPM includes the following, as applicable:
. initial conditions
. initiating cues
. references and toois. 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
specific periormance criteria that include:
- detailed expected actions with exact criteria and nomenclature
- system response and other examiner cues
- statements describing impoltant 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.
Repel'l.on from opera1 ng less used dJr ng the previos licens'ng examinat on 's witnin
acceptab e I m m (30% for the walk-lhro-gh) and (10 not comprom se lesi integrity.
At least 20 percent of the .PMs on eacn test are new or s gnifcanl y moa'fed.
w-
C.
w
3. SIMULATOR CRITERIA
..
a.
Tne assouateo simLlator operathg tests (scenario sets) have oeen reviewed 'n accoroance w lh
Form ES-301-4 and a copy s attached.
Printed Name / Signature
Date
a. Author
(63'-Jc@
b. Facility Reviewerr)
c. NRC Chief Examiner (#)
d. NRC Supervisor
NOTE:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column "c:
chief examiner concurrence required.
NUREG-1021, Draft Revision 9
/&/ne
C&.L
Simulator Scenario Quality Checklist
Form ES-301-4
QUALITATIVE ATTRIBUTES
Initials
a
b*
c#
1
Tne msa conditions are realist c. in thal some eq!.
pment andlor instr.Imenlation may oe OLI
of
sew ce, but I does not c.e
me operators mlo expected events
1Bwu/
9.
The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator
performance deficiencies have been evaluated to ensure that functional fidelity is maintained
while running the planned scenarios.
2.
The scenarios consist mostly of related events.
ll%
Y
3.
Each event description consists of:
.
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.
the point in the scenario when it is to be initiated
the malfunction(s) that are entered to initiate the event
the symptomslcues that will be visible to the crew
the expected operator actions (by shifl position)
the event termination point (if applicable)
4.
@w
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).
I
I
I
5.
The events are valid with regard to physics and thermodynamics.
\\
fin
6.
Sequencing and timing of events is reasonable, and allows the examination team to obtain
complete evaluation results commensurate with the scenario objectives.
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.
TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO SEE SECTION D.5.d)
Actual Attributes
--
_.
I-
I
i
8.
The simulator modeling is not altered.
._
I "
I
i
I O .
Every operator will be evaluated using at least one new or significantly modified scenario. All
other scenarios have been altered in accordance with Section 13.5 of ES-301.
I-
I
I
13.
The level of difficulty is appropriate to support licensing decisions for each crew position.
I
I^
I
1
1.
Total malfunctions (5-8)
7 I 7 1 7
6.
EOP contingencies requiring substantive actions (0-2)
NUREG-1021, Draft Revision 9
S-301
Simulator Scenario Quality Checklist
Form ES-301-4
QUALITATIVE ATTRIBUTES
Initials
a
b'
c#
1
The in 1 al condir ons are realist c in that some eqL pment ano or mtrmentation may oe OJI of
sew.ce, bL1 it does not cLe the operalors nlo expected events
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 symptomslcues that will be visible to the crew
the expected operator actions (by Shift position)
the event termination 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.
The events are valid with regard to physics and thermodynamics.
5.
8w M
%
%
gwv /IK
n
6.
Sequenw'ng and liming of events is reasonable, and allows the examination team to obtain
complete evaluation results commensurate with the scenario objectives.
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.
%
9.
The scenarios have been validated. Pursuant to 10 CFR 55.46(d). any open Simulator
performance deficiencies have been evaluated to ensure that functional fidelity is maintained
while running the planned scenarios.
IO.
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.
All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit
the form along with the Simulator scenarios).
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).
11.
12.
I.
I
I
8.
The simulator modeling is not altered.
n wJ*e 9
UVW
8
I -
I
I
13.
The level of difficulty is appropriate to support licensing decisions for each crew position.
~
NUREG-1021, Draft Revision 9
Transient and Event Checklist
Form ES-301-5
Normal
Instrument/
Component
OPERATING TEST NO.: 1
I b h m L 9 4
0
1
1,
2*
3,6 2,4
2,3 1,4
Applicant
Type
Reactivity
Normal
Evolution I Minimum I
Scenario Number
0
I *
1
Instrument/
Component
2*
3,6
2, 5
Major
1
1 7 , ~
j
Reactivity
0
Normal
I*
1
1
Instrument/
Component
2*
3,6
2 4
2,4
Type
I Number I
BOP 8
3
RO -
~
L
-. .
~
Reactivity
Normal
1
2,3 I&
4
T
I
4*
I
Instrument/
Component
1.4
Major
I
1
I
Reactivity
1
I *
1
1
5 I
I
I 6
1
2,3 1,4 tti
6, 7 6, 7
As RO
Major
I
1
1
1 7, 8 I 7,8 I
I 7, 8 1 7.8
SRO-I
As SRO
384
1:(
1.4
SRO-U
5 1
I
Instructions:
(1)
Enter the operating test number and Form ES-D-1 event numbers for each evolution
conditions (refer to Section J.5.d) but must be significant per Sectjon C.2.a of
Appendix D. *Reactivity and normal evolutions may be replaced wlth additional
inntriirnent or cornnnnent malfunctions on a one-for-one basis
- Pe. . .
eactivity manipulations ma be conducted under normal or controlled abnormal
(2)
~
~~~~
.r
~.
.~
. . ~.
~.
(3)
Whenever practical, both instrument and componenimaifmctions shoLld be
includea: only those that require ver'faole acrions mat provide insight to the
apalicant's competence count toward the minimum requirement.
Author:
L
NRC Reviewer:
NUREG-I 021, Draft Revision 9
'w
Applicant
Type
a
a
6, 7 6, 7
Normal
I*
Instrument/
Component
2*
Major
1
Normal
Instrument/
SRO-U
I*
1
2*
293
I
Major
1
1 7 3 I
Transient and Event Checklist
Form ES-301-5
Final Submittal
OPERATING TEST NO.: 1
Evolution
Minimum
Type
Number
Scenario Number
2
I
3
1
RO I
BOP .:
r
Reactivity
Normal
I 3 , 5 I 2 , 4
Instrument/
Component
Major
1
6
1
I
Reactivity I
I *
1
1
~
1
Instrument/
3,5 2,4
Component
AsRo I
Major
7.8 7,a
I
Reactivity
1
0
I SRO-I
I
1
2'3
4,5
6
~
7, a
As SRO
I
Reactivity I
0
Component
4,5
6
Instructions:
(1)
Enter the operating test number and Form ES-D-1 event numbers for each evolution
conditions (refer to Section J.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.
Whenever practical, both instrument and component malfunctions should be
included; only those that require verifiable act!ons that provide insight to the
- pe. . .
eactivity manipulations ma be conducted under normal or controlled abnormal
(2)
(3)
icant's competence count toward the minimum requirement.
i/
Author:
NRC Reviewer:
NUREG-1021, Draft Revision 9
I N I f / 4 L
/-dZ
Form ES-301-6
Competencies Checklist
L
L
SCENARIO
SCENARIO
2
3
1
2
3
1
2, 3
4, 5
6. 7
3, 5
6, 7
8
2, 3
5, 6
8
2.3
5.6
7
2,4
7. 8
2,3
Interpret I Diagnose
4, 5
Events and Conditions
6,7
8
3,4
Comply With and
5,6
Use Procedures (1)
7,8
Operate Control
Boards (2)
2,4
5, 6
7
3, 5
6, 7
8
2, 3
5, 6
7
la, I b
4, 5
4, 5
4, 5
3, 5
6, 7
8
2,3
5,6
7. a
2. 3
5, 6
7
1,2
4, 7
8
Communicateand
1 F!
Interact
3,4
Demonstrate
Supervisory
5, 6
Ability (3)
7, 8
la, I b
2,3
4, 5
6 7 , 8
3,4
5 6
7. a
2,3
4, 5
6, 7
8
2,3
4, 5
6. 7
Ib, 2
3,4
5,6
7,8
5
2
3
Comply With and
Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Onlv armlicable to SROs.
Instructions:
Circle the applicant's license type and enter one or more event numbers that will allow the examiners to
evaluate every applicable competency for every applicant.
Author:
-NRC
Reviewer:
NUREG-I 021, Draft Revision 9
'L
L
SCENARIO
Final Submittal
SCENARIO
SCENARIO
Competencies Checklist
Form ES-301-6
Competencies
Interpret / Diagnose
Events and Conditions
Comply With and
Use Procedures (1)
Operate Control
Boards (2)
Communicate and
Interact
~
Demonstrate
Supervisory
Ability (3)
Comply With and
Use Tech. Specs. (3)
1
2.3
4,5
6, 7
8
3.4
5, 6
7, 8
3
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
2
1
3
Ib. 4
1,4
5, 6, 8
6, 7
6.7
4,5
4. 5
6, 7 I
Instructions:
Circle the applicant's license type and enter one or more event numbers that will allow the examiners to
evaluate every applicable competency for every applicant.
Author:
J
NRC Reviewer:
NUREG-1021, Draft Revision 9
Final Submittal
Written Examination
Form ES-401-6
Quality Checklist
Date of Exam: 06/27/03
Exam Level: SRO
- acility:
Oconee Nuclear Station
-
the audit exam was systematically and randomly developed; or
-
the audit exam was completed before the license exam was started; or
comprehension/analysis level; the SRO exam
may exceed 60 percent if the randomly selected
WAS S U D D O ~ ~
the hiaher cognitive levels; enter
the actual RO / SRE) question distribution(s) at
(32%)
(68%)
'
right
Referenceslhandouts provided do not give away answers
Question content conforms with specific WA statements in the previously
approved examination outline and is appropriate for the Tier to which they are
8.
9.
- $w
assigned; deviations are justified
1
10.
11.
Question psychometric quality and format meet ES, Appendix 6, guidelines
The exam contains, the required number of one-point, multiple choice items; the
total is correct and agrees with value on cover sheet
I
Printed Name I
Signat re
a. Author
b. Facility Reviewer (3
/A/
c. NRC Chief Examiner (#)
d. NRC Regional Supervisor
Michael E. Ernstes
EL;.6-
Larry S. Mellen ip.- LA S d ,
Ronald F. Aiello 1 Hw
Note:
- The facility reviewer's initialslsignature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column '"c;" chief examiner concurrence required.
300f 34
NUREG-1021, Draft Revision 9
Final Submittal
Written Examination
Form ES-401-6
Quality Checklist
Facility:
Oconee Nuclear Station
Date of Exam: 06/27/03
Exam Level: RO
Initial
Item Description
1.
2.
Questions and answers technically accurate and applicable to facility
a. NRC WAS referenced for all questions
b. Facility learning objectives referenced as available
SRO questions are appropriate per Section D.2.d of ES-401
Question selection and duplication from the last two NRC licensing exams
appears consistent with a systematic sampling process
Question duplication from the license screeninglaudit exam was controlled as
indicated below (check the item that applies) and appears appropriate:
-
the audit exam was systematically and randomly developed or
-
the audit exam was completed before the license exam was started or
X- the examinations were developed independently; or
-the
licensee certifies that there is no duplication; or
3.
4.
5.
-
-
other (explain)
Bank use meets limits (no more than 75 percent
from the bank at least 10 percent new, and the
rest modified); enter the actual RO I SRO-only
auestion distribution(s) at right
6.
7.
Between 50 and 60 percent of the questions on
the RO exam are written at the
comprehensionlanalysis level; the SRO exam
may exceed 60 percent if the randomly selected
WAS support the higher cognitive levels; enter
the actual RO I
SRO question distribution(s) at
right
Memory
(44%)
(56%)
'p
I
6.
Referenceslhandouts provided do not give away answers
\\a
9.
Question content conforms with specific WA statements in the previously
approved examination outline and is appropriate for the Tier to which they are
assigned; deviations are justified
Question psychometric quality and format meet ES, Appendix E, guidelines
The exam contains, the required number of one-point, multiple choice items; the
total is correct and agrees with value on cover sheet
I O .
11.
Printed Name I
Signat
Date
a. Author
Larry S. Mellen
c. NRC Chief Examiner (#)
Ronald F. Aiello / /&
b. Facility Reviewer (3
/
d. NRC Regional Supervisor
Michael E. E r n s t e d h A / E-
6(/r/ol
Note:
- The facility reviewer's initialskignature are not appl:cable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column "c: chief examiner concurrence required.
300f 34
NUREG-I 021, Draft Revision 9
,
N ,
fl4L
roJ Mia#?@
Written Examination
Form ES-401-7
Quality Checklist
u y
7.
- I Between 50 and 60 percent of the questions on I
Memory
CIA
Facility: Oconee Nuclear Station
Dateof Exam: 061
03
Exam Level: SRO
I
Referenceslhandouts provided do not give away
approved examination outline and is appropriate for the Tier to which they are
Question psychometric quality and format meet ES, Appendix B. guidelines
8.
answers
9.
Question content conforms with specific KIA statements in the previously
assigned; deviations are justified
IO.
11.
"
&The exam contains 25, one-point, multiple choice items; the total is correct and
Item Description
I
A
I
I
h
9
b
-I
\\B
s that there is n
percent from the bank at least 10 percent new,
and the rest modified);
enter the actual question twNi ~ , ~ a i ~ ~ 9 4 ~
1
1
the exam are written at the
comprehensionlanalysis level; enter the actual
question distribution at right
I
Printed Name lignaturq
Date
a. Author
5/7/3
b. Facility Reviewer r)
c. NRC Chief Examiner (#)
d. NRC Regional Supervisor Michael E. Ernstes
Note:
The facility reviewer's initialslsignature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column "c:" chief examiner concurrence required.
a,
$ n o Liwm MA/'
E f i c m Q Z 68 9,
y,
r,q ,a p#,>r ~ K d m
coflm*'ws I
U
~
orp p4:-f
r * u ~ p , p ? ~ n ~ a ' e
7-3
c/9
, , + r i g ~
s u ~ * . M '
Written Examination
Form ES-401-7
Quality Checklist
Facility: Ownee Nuclear Station
Dateof Exam: 061
03
Exam Level: RC
I
indicated below (check the item that applies) and appears appropriate:
-
the audit exam was systematically and randomly developed; or
z t h e examinations were developed independently; or
the audit exam was completed before the license exam was started; or
6.
Bank use meets limits (no more than 75
percent from the bank at least 10 percent new,
Date
a. Author
5 7 2 h
b. Facility Reviewer C)
c. NRC Chief Examiner (#)
d. NRC Regional Supervisor Michael E. Ernstes
Note:
The facility reviewer's initialslsignature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column '"c:" chief examiner wncurrence required.
c
u
ii
q c e C
m
A
W
Written Examination
Review Worksheet for Oconee Nuclear Station (Initial)
Q#
1.
2.
3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.
7.
LOK
LOD -
(C/M) (1-5) Stem Cues T/F
Cred. Partial Job- Minutia
- /
Back- Q= SRO U/E/S
Explanation
Focus
Dist.
Link
units ward
KIA Only
~
~~
~.
~
,
~
,
~
~,~
~
.
~
The stem lacks sbffident 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 (;.e., clues, specific determiners. phrasing, length, etc).
The answer choices are a collection of unrelated trbe/false statements
3#
~
~~
~
~~
More than one distractor is not credible.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem),
The question is not linked to the job requirements &e., the question has a valid WA 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.
4.
Check the appropriate box if a job content error is identified:
5.
6.
Check auestions that are samuled for conformance with the approved WA and those that are desisnated SRO-only (WA and license level mismatches
are unacceptable).
Based on the reviewers judgment, is the question as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement, or
(S)atisfactory?
1.
2.
3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.
7.
LOK LOD
(C/M) (1-5) Stem Cues T/F Cred. Partial Job- Minutia
- / Back- Q= SRO u/E/S
Explanation
Focus
Dist.
Link
units ward WA Only
7.
At a minimum, explain any U ratings (e.g., how the Appendix 6 psychometric attributes are not being met).
c
3
c
4
c
3
c
3
c
3
c
3
c
3
c
3
c
3
M
3
M
3
c
3
- /
_ _ _ ~ ~
3. Psychometric Flaws
Back.
--
Stem Cues TIF
Jist. I
X
4. Job Content Flaws
-
ob-
dinutia
-
-
-
-
dother
6.
7.
UIEIS 1
-
-
E
II
Explanation
E
E
-
U
U
-
S
U
-
E -
E
E
E
S
~000028AK1.01
II
3. Psvchometric Flaws -
'ark
4. Job Content Flaws ' -
-
&'Other
6.
7.
UIEIS I
Explanation
-
-
U
-
U
U
U
I
I
I
II
3. Psychometric Flaws
,tern Cue: 7
1
4. Job Content Flaws\\
Minutia -
-
-
(Other
6.
7.
Explanation
-
-
U
-
U
U
U
00402.4.11
This question has nothing to do with knowledge of abnormal
condition procedures.
-
U
E
U
-
U
S
007K1.03
I1
I1
12
L3
$4
15
46
47
48
Ainutia -
c
M
c
M
--
C
c
c
'/ Back- Q= SRO
UIEIS
Explanation
Y
N
Y
N
Y
N
Y
N
Y
N
Y
N
S* 1 ? s l k c k to see if the backup string is off of the vital
11
3. Psychometric Flaws
S
4. Job Content Flaws
EW/E13EA2.1
pip
unit!
S
11
G2.1.11
6. I
S
7.
62.1.32
,.- II
S
G2.1.6
UIEIS I
Explanation
-
-
U
I
E
U?
I Is this 0
a < 1 hr TS?
II
3. Psychometric Flaws
- /M)
(1-5) Stem Cues
Focus
X
4. Job Content Flaws\\ -
-
Other
6.
U/E/S
~~
7.
Explanation
S
lG2.3.2
II
S
lG2.4.12
II
S
U
S'
37 Yellow: An enhancement is required or question needs dispositioned
before ONS receives.
47 Red: Implausible questionidistractors, WA is wrong, Question has a
technical issue.
16 Green: None to very minor enhancements.
Question requires Utility input
Written '&..dination
Final Review Worksheet for Oconee Nuclear Station
With Validation Comments in /talks
Form ES-,_ /9
Draft Revision 9
1.
2.
3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.
7.
Q#
LOK
(cw (1-5)
U/E/S
Explanation
Stem Cues T/F
Cred. Partial Job- Minutia
- /
Back- Q= SRO
Focus
Oist.
Link
units ward
WA Only
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
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).
Check the appropriate box if a psychometric flaw is identified:
8 The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
e
The stem or distradors contain cues (Le.. clues, specific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated truelfalse statements.
. One or more distractors is not credible.
. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
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 KIA 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 (Le.. 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.
Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are
unacceptable).
Based on the reviewer's judgment, is the question as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement, or
(S)atisfactory?
7. At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met).
1.
2.
3.
4.
5.
6.
Page 1 of 12
3. Psychometric Flaws
4. Job Content Flaws
q-mxqw
units
/
i. Other I 6. I
7.
4 I
Explanation
nlyl
I
IESTIONS
S
000003G2.4.1
No utility comments.
Changed correct answer to "C". Modified "C" and
" B to ensure only one correct answer. Verified
resuonse on simulator. Changed to RO Question.
U
000008AA2.22
-
ICE 'concurred.
I S ~000009G2.1.31
No utility comments.
Attachment required:
EOP Encl. 5.1 Page 5, Figure 1 (Required HPI Flow
EOP has changed and ONS no longer bumps
RCPs.
Replaced with Bank question 164. CE concurred.
KA does not match. KA is for a LBLOCA. At ONS
we have Boiler Condenser cooling instead of
Reflux Boiling. 200 gpm leak will not saturate the
plant. Added SBLOCA to stem. TA and TB
Switchgear locked out added to stem to eliminate
cue in stem that made "C" and " D
not plausible.
Chanaed to SRO onlv. Changed to KA
X
E
000009EA2.15
U
000009EK1.01
X
U
OOOOIIEK1.01
No utility comments.
Page 2 of 12
,
X
E
000025AK3.01
Added SEE A'ITACHMENT
pachment: Page 27 of 29 of EOP tab TBF. SRO
E
Modified stem to remove reference to Immediate
Manual Actions because entering an AP is not an
Immediate Manual Action. Reworded distractors to
000027AK1.01
Added "indication" to stem. Suggest cog level is
CIA. CE concurred.
Added "indication" to PZR Saturation
readability. CE concurred.
dded Drocedure titles to AP/20 and AP/25.
E
U
E
U
concurred.
000028AK1.01
Added "slowly increasing" to stem and "A" and "B
choices. Pressure would slowly increase if PZR
level is increasing. Changed to KA 000028AK2.02
CE concurred.
000029EA2.09
EOP no longer has a limit on SO level during UNPP
Replaced modified bank question 199. CE
concurred. Changed to RO.
000029EK3.12
Editorial changes to match current EOP
designations. CE concurred.
000033AA2.11
ONS no longer has Intermediate Range detectors.
KA no longer applicable to ONS. Suggest new KA
000036AA2.02. Replaced with new question. CE
concurred.
Pressure.
00028AA2.01
dded "with SASS in auto" and "due to an internal
F
insure " D is the only correct answer. CE
power failure" to stem to clarify question and to
Page 3 of 12
S
E
S
U
U
lnew question that matches KA. CE concurred.
c 1000056AA2 47 ONS has hydro electric versus
\\J
000038EA1.19
No utility comments.
Added "?A Main FDWpump operating"to stem t8
clarify plant status.
000040AA2.1
Removed refer to attachment. Attachment not
required. Removed tab letter designations from
distractors, not used at ONS. Changed " B
to "Los!
of Subcooling Margin" to reflect ONS EOP tab. CE
concurred.
000051AA2.02
No utility comments.
000054AK3.03
Replaced question because EFDW valve
controllers have been replaced and no longer
operate as the question assumes. NO longer an
AP119, information moved to EOP. Bank CF025004
000055EA2.01
Question does not meet the KA. Question deals
with cycling TBVs due to emergency CCW flow
during a blackout. The KA specifies valve position
during a loss of IA as a result of a blackout.
Conditions stated in question are no longer
addressed in current procedure. Replaced with a
v
E
U
Page 4 of 12
EDGs. Therefore, CE determined this KA
acceptable because ONS load sheds up front vs
sequencing loads. Intent of KA met.
0000576.2.1.8
Remove "RPS Channel testing is also due during
your shift" from stem. Has no bearing on question.
Attach reference OP/3/A/l107/004, Enel. 4.15
(System Drawing) CE concurred.
000057M1.06
ICs has been upgraded and loss of KI no longer
requires use of Aux Shutdown Panel. Replaced
with bank question STG636. CE concurred.
H
4
F
2
H
3
X
F
2
F
3
F
2
H
3
F
3
H
4
H
3
E
00059AK3.01
dded (LPSW DISCH) to stem. CE concurred.
00061K1.01
No utility comments.
U 000062AA1.07
Operability determinations are performed by SROs.
+------
ReDlaced with modified bank auestion 605 that
Added "requiring activation of the SSF" to stem to
ensure proper path in the AP. CE concurred.
E
000067G2.4.27
S
000067AK3.04
U 001A2.13
No utility comments.
Two correct answers ("B and "D"). Replaced with
new question. CE concurred.
Added procedure title. Changed "returned to
service" to "restarted" to clarify stem. Changed
RHR to DHR. Made Units designations match in
E
003K5.04
-
btem. CE concurred.
LJ
1003A3.02
-
~
Instrumentation mentioned in question is not
monitored by the operator. Replaced with bank 162
CE concurred.
Need procedure number from facility
Reworded stem to improve readability. Added
procedure number and title. CE concurred.
E
004G2.4.11
Page 5 of 12
U
004K2.02
,_
Does each ACB have its own transfer switch? If
so, should switch be switches? Should is in
AUTO be Are in AUTO
The question concerned how aux power was
supplied to the Keowee units. The KA concerned
the power supply to the RCS Makeup pumps. Wrotc
a new question that matched the KA. CE
concurred.
No utility comments.
Removed the following bullets LPI H D R IA
INJECTION FLOW LO alarm (01A1310) LPI
H D R 18 INJECTION FLOW LO alarm (01A1311
from stem. They will not alarm unless ES has
actuated.
S
00662.1.7
Reworded stem and answers to improve
readability. CE concurred.
No utility comments.
No utility comments.
Corrected question by rewording stem, C and D
choice. ONS does not have auto isolation of CC to
individual RCPs. In D with CC-718 closed there
would be no CC flow. CE concurred.
S
005K3.07
S
006A4.05
S
007K1.03
U
008A201
S
008A4.01
E
Page 6 of 12
E
S
U
S
S
S
IJ
S
I-
/
011K3.02
The status of SASS is required to answer this
question. Added "with SASS in manual" to stem.
CE concurred.
012K5.01
No utility comments.
012K6.04
Question assumes only one SID Bypass Key
Switch. Each RPS Channel (4) has a SID Bypass
Key Switch. Question reworded, modified stem and
rewrote all distractors. CE concurred.
013A1.06
No utility comments.
013K3.03
Reworded stem for clarification. CE concurred.
015G2.1.32
No utility comments.
016A2.01
Question concerned SASS operation with a failure
of Thot. SASS no longer swaps Thot. Thot is now
median selected. Wrote new question on failure of
PZR temperature and SASS. CE concurred.
022A1.04
Original KA not applicable. Changed to KA
08K3.02. CE concurred.
H
3
F
3
H
3
H
4
H
3
F
3
H
3
F
2
F
3
H
3
F
3
F
3
Page 7 of 12
S
S
S
E
02662.1.27
No utility comments.
026K3.01
No utility comments.
029K1.04
No utility comments.
03462.1.27
RO duties during refueling no longer include
activities in the RB or SFP. Therefore the KA was
changed to 034GEN2.2.27. Replaced with modified
bank question 359. CE concurred.
E
Iconcurred.
S b56A2.04
v
35A4.05
Caps and bolded KEY. Added "with a subcooled
RCS" to stem to clarify plant conditions. CE
concurred.
Added 'Yo prevent overcooling" to stem to clarify
question. This question is written based on an
ONS plant event. This event concerned
overcooling during a low decay heat natural
circulation. During normal approach to natural
circulation, "C" would be correct.
\\No utility comments.
S b59A1.03
S
E
E
INO utility comments.
U 1061A3.01
039K1.02
No utility comments.
Changed the word 'Tinoperative" to
'Tnoperable" in the stem to match ONS
terminology.
039K5.01
Modified stem to improve readability. CE
concurred.
055A3.03
Reworded "C" to improve plausibilitv. CE
U
Page 8 of 12
Question no longer correct due to plant mods. KA
does not match. Replaced with bank question 43 to
match KA. Requires memorization of procedure.
CE concurred.
061K6.01
Original question had FDW-3151316 failing open.
Question explanation discussed ARC valve failure.
No correct answer. Wrote new question to address
ARC valve failure with a correct answer.
CE concurred.
U
U
062K4.02
Jlncorrect logic for "c**
LPI pump start. No auto star
- /
062A2.10
Does the gauge have power? If so, could " B be
correct?
CE: Facility check to make sure distractor "8" not
correct also.
Question setup not plausible. I&E working in an
electrical cabinet would not affect the air supply to
the MS gauge. Does not match KA. Replaced with
bank question 735 that matches KA. CE concurred
on "C" LPI pump. Rewrote-stem and distractors to
make correct. Changed cog level to CIA.
CE concurred.
INO utility comments.
U 1063K2.01
.
S
E
S
U
~~~
~.
In stem loss of power was to aux oil pump not the
TDEFDW Pump. Tripping throttle valve would stop
all steam flow to turbine. No correct answer.
Rewrote answer choices to ensure a correct
choice. Added Aux oil pump to stem to clarify what
lost power. CE concurred.
064K4.03
No utility comments.
071K4.01
Capped and bolded NOT in the stem. Added
"initially" to "D". CE concurred.
075K1.01
No utility comments
076A2.01
Not required for the operator to have this
information memorized. This question would
require 4 attachments. This information is in the
OP L&P because of complexity of operability
determination. If the OP is given it would be a
direct lookup. Replaced with new question.
API024 (Loss of LPSW) is the procedure used to
mitigate the consequences of this malfunction. CE
concurred.
Page 9 of 12
'F
F
2
F
2
F
2
X
X
3
F
3
H
3
F
3
H
4
H
3
H
3
H
3
S
078K1.04
-
hanged cog level to CIA. CE concurred.
U
U
E
S
E
S
U
S
U
E
078K3.02
Ldded (IA and AIA) to stem to clarify question. CE
II
concurred.
079A2.01
At ONS IA does not backup SA. Original KA is not
applicable. Changed KA to 014A1.02. Replaced witt
bank question 367. CE concurred.
086K4.03
This question requires the recall of knowledge that
is too specific for the closed reference test mode.
Wrote new question. CE concurred.
BW/AOIAA1.2
Added delta to "A". Modified "C" to match "B. CE
concurred.
BW/AO4AA2.2
No utility comments.
BW/A05AK2.1
SSF Diesel Generator will not tie to the grid
but can tie to Unit 2's MFB #2. Added "Unit 2'!
MFB #2" to stem to match our nomenclature.
CE concurred.
Underlined "emergency" to emphasize start
method.
BWlEOZEK2.2
No utility comments.
BW/E04EK2.2
Three correct answers. A, B, and C. Modified " A
and "B" to make incorrect. CE concurred.
BW/E04EK3.3
No utility comments.
BW/E08G2.4.18
Answer incorrect. Modified stem and distractors tc
improve readability and make "A" correct. Added
ONS specfic nomenclature. CE concurred.
Added "controller" to "0"
to clan@ location of
manual control.
Page 10 of 12
~~
S
E
E
BWlE13EA2.1
x
i
No utility comments.
Changed "C'?
to read "tab SA (Subsequent
Actions) I' to match current EOP nomenclature.
Added "(HPI)" to D. This is the Rule 6 title.
G2.1.11
Is this Q a c I hr TS?
CE: faci/ity verify this Q is c I hr TS, ofhewise
G2.1.12.
Original question did not meet KA GEN 2.1.11.
Selected bank question to meet KA GEN 2.1.11.
CE concurred.
G2.1.14
Added (s) to notification to indicate one or more
notifications. CE concurred.
In the stem changed "RO supervising" to rea
%perator overseeing" because RO do not
bupervise.
S IG2.1.27
3 e F
84
85
86
87
88
89
90
91
92
-
F
F
F
H
F
H
F
F
H
Page 11 of 12
S
S
S
S
E
E
No utility comments.
G2.1.32
No utility comments.
G2.1.6
No utility comments.
G2.2.12
No utility comments.
G2.2.17
Removed "You are the Plant Supervisor." from
stem not required to answer the question.
Reworded stem to improve readability. CE
concurred.
G2.2.2
Changed stem to "FDW Calibrating Integral" due tq
new ICs. Changed "Bailey" to "Master" in " D to
match current plant designations. CE concurred.
G2.3.2
Added "SEE ATTACHMENT" Alara Manual
Appendix "C" Section 4.4 (General Dose Reductio]
Methods) CE concurred.
S
S
S
S
E
E
U
E
v
x
_.
J
4
J
J
J
X
J
J
X
i/
G2.3.3
No utility comments.
G2.4.12
No utility comments.
G2.4.23
No utility comments.
G2.4.25
Cog level change to memory. CE concurred.
G2.4.3
Redesigned the stem to improve readability.
Added "ES' to the stem. Added "and 2 have
actuated" to stem to make "C" correct and "D'
plausible. CE concurred.
G2.4.41
Added "SEE ATTACHMENT" to stem. CE
concurred.
G2.4.6
The question requires the recall of knowledge that
is to specific for the closed reference test mode.
Replaced with bank question 190. CE concurred.
G2.4.7
Added "RCP to stem. Should be SRO question
because it is asking for actions of the procedure
director who is an SRO. Cog level should be CIA.
CE concurred.
"1
F
4
F
2
H
2
Page 12 of 12
F
3
H
4
F
3
F
3
Item Description
Written Examination Grading
Form ES-403-1
Qualitv Checklist
a
Facility:
Oconee Nuclear Station
Date of Exam: 06/
03
Exam Level: RO
Initials
2.
Clean answer sheets copied before grading
(LXRTest machine graded)
Answer key changes and question deletions justified and
documented (No changes or deletions were made)
Applicants' scores checked for addition errors
(reviewers spot check > 25% of examinations)
(LXRTest machine graded)
Grading for all borderline cases (80% +/- 2%) reviewed in
detail
(No failures or borderline cases)
All other failing examinations checked to ensure that grades
are justified
(No failures or borderline cases)
Performance on missed questions checked for training
deficiencies and wording problems; evaluate validity of
questions missed by half or more of the applicants
2.
3.
4.
5.
6.
Printed Name / Signature
a. Grader
Ronald F. Aiello 4-
b. NRC Reviewerr)
Gerard W.
Laska /A
c. NRC Chief Examiner (*)
Ronald F. Aiello
d. NRC Supervisor (*)
NIA *
-
NIA 2
9
%
h
-
b -1
c
+
I
+
I
Date
- 07/02/03-
(*)
The facility reviewer's signature is not applicable for examinations graded by the
NRC; two independent NRC reviews are required.
Written Examination Grading
Form ES-403-1
Quality Checklist
Facility:
Oconee Nuclear Station
Date of Exam: 061
03
Item Description
1.
Clean answer sheets copied before grading
(LXRTest machine graded)
Answer key changes and question deletions justified and
documented (No changes or deletions were made)
Applicants' scores checked for addition errors
(reviewers spot check > 25% of examinations)
(LXRTest machine graded)
Grading for all borderline cases (80% +/- 2%) reviewed in
detail
(No failures or borderline cases)
All other failing examinations checked to ensure that grades
are justified
(No failures or borderline cases)
Performance on missed questions checked for training
deficiencies and wording problems; evaluate validity of
questions missed by half or more of the applicants
2.
3.
4.
5.
6.
Printed Name 1 Signature
Exam Level: SRO
initials
'B
Date
a. Grader
Ronald F. Aiello
- 07/02/03-
b. NRC Reviewerr)
c. NRC Chief Examiner (*)
Ronald F. Aiello
d. NRC Supervisor (*)
7 / Y / a J
(*)
The facility reviewer's signature is not applicable for examinations graded by the
NRC; two independent NRC reviews are required.
Post-Examination Check Sheet
Form ES-501-1
(Facility: Oconee Nuclear Station ~ Date of Exam: 06/16-24/03)
Task Description
Date
Complete
1.
Facility written exam comments or graded exams received and I
07/01/03
ll
verified complete
6.
7.
Management (licensing official) review completed
License and denial letters mailed
I
II
2.
Facility written exam comments reviewed and incorporated and
NRC grading completed, if necessary
ll
N/A
Yh ? / M O 3
~
lr
~
-.
~
3.
Operating tests graded by NRC examiners
8.
Facility notified of results
9.
Examination report issued (refer to NRC MC 061 0)
I
07/09/03
(1
071 1 7/03
8
/I//.-.
0 3
II
4.
NRC Chief examiner review of written exam and operating test 1
grading completed
07/09/03
10.
Reference material returned after final resolution of any appeals
II 5.
Resoonsible suoervisor review comoleted
I
07/11/03
11
N/A (CD)